table of contents · fema rac briefing at the eof news center. august i1, 1992 0730 exercise...

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TABLE OF CONTENTS Schedule of Exercise Events Exercise Rules Objectives Scenario - Sequence of Events Radiological Assessment # Assessment, Submersion and Inhalation # Estimate of Projected Offsite Dose * Dose Assessment at 6 miles * Basis for Dose Projections Exercise Data and Messages Field Monitoring (10-mile EPZ) Data Meteorological Data Radiation Monitor DATA Ingestion Pathway Data Post-Accident Sampling (Liquid and Gaseous) Data Simulator Data (Trial Run) Critique Information e 9212040053 920625 PDR ADOCK 05000269 F PDR

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Page 1: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

TABLE OF CONTENTS

Schedule of Exercise Events

Exercise Rules

Objectives

Scenario - Sequence of Events

Radiological Assessment

# Assessment, Submersion and Inhalation

# Estimate of Projected Offsite Dose

* Dose Assessment at 6 miles

* Basis for Dose Projections

Exercise Data and Messages

Field Monitoring (10-mile EPZ) Data

Meteorological Data

Radiation Monitor DATA

Ingestion Pathway Data

Post-Accident Sampling (Liquid and Gaseous) Data

Simulator Data (Trial Run)

Critique Information

e 9212040053 920625 PDR ADOCK 05000269 F PDR

Page 2: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

SCHEDULE OF EXERCISE EVENTS

August 10. 1992 NRC arrival onsite. Site specific training to team members. Issue badges. Tour facilitics.

FEMA RAC briefing at the EOF News Center.

August I1, 1992

0730 Exercise begins.

1330 Day I of excrcise is terminated.

1430 Day 3 of exercise begins.

1700 Day 3 of exercise ends.

August 12, 1992

0700 - 1700 Controllers meet with players and evaluators

0800 - 1100 Post Accident Sampling (Gas)

1300- 1600 Post Accident Sampling (RCS)

0900 Day 5 (IPZ) at the EOF

1200 Day 9 (IPZ) at the EOF

1500 Termination

August 13, 1992

0800 Controller Critique, OOB-Room 316

1300 DPC Player/NRC Critique-OOB-Room 316

FEMA Critique (Public/Participant) at the EOF News Center

August 14, 1992

0800 NRC Exit

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EXERCISE RULES

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EXERCISE 92-4 RULES

Initial plant conditions will be given to players prior to the start of the drill. This

information will only be given to those persons that would normally be aware of such information.

2. Controllers will be available in the Technical Support Center.

Operational Support Center, Simulator Control Room, Emergency Operations Facility, and field monitoring vchicles. Controllers will verbally provide

information contained on message sheets. data sheets, on sitc/off site radiological data, or other information, as appropriate, for players use. Scenario data will only be provided to players after they have gone to the persons or places where that data would be available in an actual emergency.

3. Player response should be real time, with no simulated actions unless directed otherwise by the controller. Generally, emergency response activities should be performed fully and not simulated unless personnel safety, plant safety, or unit

operation would be jeopardized.

Examples of Do's and Don'ts for Drill Participants

DO * Obtain actual instrument readings where information has not been provided by con trollers/evalua tors

* Go to the work area/location or as close as possible without entering Radiation Areas

*~ Perform actions in the simulator control room as necessary

* Make sure you understand controller/evaluator messages before any actual manipulations are done

DON'T * Operate valves

Flip switches and breakers

*~ Cause the actual Control Rooms to have false alarms

Operate any device affecting station operation without actual Control Room Operator permission

* Remove any component from service.

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EXERCISE 92-4 RULES (CONTINUED)

4. For ALARA reasons. drill participants should not enter actual high radiation areas. Instead, plaVCrs should go to the general area and ma kc the controller aware of their intended responsc.

5. If a procedure must he simulated. it is the playcr's responsibility to ensure that the controller is fully aware of any actions taken. If information is needed for player response, it is appropriate to ask questions of the controller. HOWEVER, DO NOT TALK TO CONTROLLERS UNLESS ABSOLUTELY NECESSARY.

6. Respirators (1o not have to he worn by drill participants. Administrative controls for respirator issue will he followed. Radiation Protection will issue a tag to indicate that a respirator is being worn, and tag out the respirator being issued. Air bottles will be real time (approximately 60 minutes per bottle).

7. Disposal of uncontaminated Anti-C's creates a problem. Controllers will determine which jobs will require actual donning of Anti-C's. Badges are available for use when simulating the wearing of Anti-C's.

8. All phone and radio communications required by procedure will be made unless directed otherwise hy the controller. Calls generally should not be made to persons, groups, or organizations that are not participating in the (irill. Communications should begin and end with the statement, "THIS IS A DRILL".

9. Once Site Assembly has been achieved, those persons not directly participating in the drill will be told to return to their normal work area.

10. Site evacuation of non-essential personnel, if required, will be carried out on a modified basis. Two people from designated sections will relocate as directed by the Emergency Organization.

I 1. Players will be identified by badges or colored arm bands showing their group or position name. Controllers/evaluators will be identified by appropriately labelled badges or arm bands.

12. The siren system and EBS will be tested during the exercise.

13. The State of South Carolina, Oconee County and Pickens County, and the NRC Response Team will fully participate in the exercise.

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OBJECTIVES

0

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DUKE POWER COMPANY OCONEE NUCLEAR SITE

EXERCISE OBJECTIVES

A1..K2

MAJOR COMPONENTS OF EMERGENCY PLAN 1991 1992 1993 1994 1995

A. EMERGENCY RESPONSE ORGANIZATION

a. Demonstrate ability to mobilize staff (TSC, OSC, EOF, JIC) and activate facilities as required by Figure B-5 in ONS Emergency Plan after declaring an Alert or higher emergency classification.

b. Demonstrate the ability to fully staff facilities and maintain staffing around the clock.

c. Demonstrate precise and clear transfer of responsibility from the Shift Supervisor in the Control Room to the Emergency Coordinator in the TSC.

d. Demonstrate precise and clear transfer of responsibility from the

Emergency Coordinator in the TSC to the EOF Director in the EOF.

e. Demonstrate the ability to assess the incident and determine/ implement mitigation strategies.

B. EMERGENCY CLASSIFICATION

a. Demonstrate the ability to properly classify emergency situations

in accordance with plant procedures.

b. Demonstrate the ability to notify counties and state within 15 minutes after declaring an emergency or after changing classification.

c. Demonstrate proper use of message format and authentication , ,

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A1..K2

MAJOR COMPONENTS OF EMERGENCY PLAN 1991 1992 _ 1993 1994 1995

methodology for messages transmitted to state and counties.

C. COMMUNICATIONS

a. Test onsite and off site communications equipment:

- Selective Signaling

- Duke Offsite Radio System

(FMTs and TSC/EOF)

- Duke Onsite Radio System

- SC State Decision Line

- FTS 2000 System:

HPN

ENS i

- AT&T

- ONS Switchboard

- Intercom Systems

b. Demonstrate the ability to communicate with all appropriate --locations, organizations, and field personnel.

c. Demonstrate the ability to notify the NRC not later than 1 hour after declaring one of the emergency classes.

d. Demonstrate the ability to provide current plant data to appropriate

locations, organizations, and field personnel.

0 0 0

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A1..K2

MAJOR COMPONENTS OF EMERGENCY PLAN 1991 1992 1993 1994 1995

e. Test adequacy and operability of emergency equipment/supplies.

D. ACCESS AND CONTROL

a. Demonstrate the ability to account for onsite personnel within 30

minutes.

b. Demonstrate the ability to locate unaccounted personnel _X

determined by site assembly.

c. Demonstrate the ability to effect an orderly evacuation of

non-essential personnel.

d. Demonstrate the ability to provide controlled access to the plant

site and EOF.

E. RADIOLOGICAL MONITORING

a. Onsite:

- Demonstrate appropriate equipment and procedures for determining ambient radiation levels.

- Demonstrate appropriate equipment and procedures for

measurement of airborne radioiodine concentrations.

- Demonstrate the ability to provide offsite dose projections in

accordance with site procedures.

- Demonstrate the ability to continously monitor and control

emergency worker exposure.

- Demonstrate the ability to make the decision (based on

predetermined criteria) whether to issue KI to emergency workers and then to issue same.

b. Offsite:

0 0 0

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A1..K2

MAJOR CO0-MPONEN-TSOF EEGNYPA S1O9EERE N1992 1993 1994 1995

- Demonstrate the ability to mobilize teams in the 10-mile EPZ to

locate and track the plume for noble gases and radioiodine concentrations in a timely manner.

- Demonstrate appropriate equipment and procedures for

collection, transport, and analysis of samples of soil, vegetation, snow, water, and milk as determined by specific scenario

requirements.

- Demonstrate the ability to transmit field measurement data to TSC/EOF.

c. Dose Calculations and Protective Action Recommendations:

- Demonstrate the ability to project dosage to the public via

ingestion pathway exposures.

- Demonstrate the ability to project damage to the public based on

plant and field data for public via ingestion pathway exposure.

- Demonstrate the ability to provide timely and appropriate

protective action recommendations in accordance with site

procedures.

F. OFFSITE AGENCY ASSISTANCE

a. Demonstrate the ability to identify need for, request, and obtain lk Federal assistance.

b. Demonstrate the adequacy of response to a medical injury involving contamination with transport to an offsite medical facility (contamination and/or radiation consequences).

c. Demonstrate the adequacy of response to a fire outside the

protected area utilizing volunter fire department support.

d. Demonstrate county and state participation in exercises/drills.

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A1..K2

MAJOR COMPONENTS OF EMERGENCY PLAN 1991 1992 1993 1994 1995

Full _

Partial

G. JOINT INFORMATION CENTER

a. Demonstrate the ability to brief the media in a clear, accurate, and

timely manner.

b. Demonstrate the ability to provide advance coordination of

information released.

c. Demonstrate the ability to establish and operate rumor control in a coordinated fashion.

H. RECOVERY AND REENTRY

a. Demonstrate the ability to determine and implement appropriate measures for controlled recovery and reentry.

b. Demonstrate the ability to take post-accident liquid samples under accident conditions.

c. Demonstrate the ability to take post-accident gaseous samples under accident conditions.

d. Demonstrate adequate equipment and procedures for decontamination of workers, equipment, etc.

e. Demonstrate the ability to estimate total population exposure.

f. Demonstrate the capability to respond to simulated Appendix R Scenarios to test a portion of the planned response:

- Turbine/Auxiliary Building Fire

- Turbine Building Fire

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A1..K2

MAJOR COMPONENTS OF EMERGENCY PLAN 1991 1992 1993 1994 1995

- Fire in West Pentration Room or SSF cable trench

- Reactor Building Fire

- Fire at CT-4 Transformer

1. EXERCISE/DRILL MANAGEMENT

a. Semi-annually an ERF activation drill will be scheduled to begin

after normal working hours (between 1800 - 0600 hours or on weekends/holidays). This drill is announced.

b. The Annual Exercise will be scheduled during different seasons of

the year.

c. Once every 6 years, an Exercise will be scheduled to begin during the time of 1800 hours through 0400 hours.

d. Drills/exercises will be under the control of a Drill/Exercise Director. Controllers/Evaluators will be utilized to keep the scenario on

track and to allow for "free play".

e. Critiques will be held after all drills/exercises to determine any

corrective actions that may need to be made.

f. Drill scenarios should include response to chemical, hazardous wastes, spent fuel shipments, and security incidents, as well as radiological and reactor incidents.

g. Demonstrate participation in an Ingestion Pathway Exercise:

-Full

- Partial

Page 13: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

SCENARIO - SEQUENCE OF EVENTS

Page 14: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

INGESTION PATHWAY EXERCISE DUKE POVER COMPANY OCONEE NUCLEAR SITE ANNUAL EXERCISE 92-4

INITIAL CONDITIONS AT 0800:

I. UNIT I AT 100%

LCO: Standby Shutdown Facility is out of service. Due back by 0540 on 8/21/92. See Unit 2 status.

LCO: Turbine Driven Emergency Feedwater Pump is out of service. Due back 8/11/92 at 1800.

LCO: Keowec Unit I taken out of service for unscheduled maintenance.

2. UNIT 2 in refueling shutdown.

Fuel transfer canal filled with 2SF-I & 2SF-2 open. Making final preparations for

starting defueling.

Condenser cooling water intake isolated and drained for outage work. SSF out of service for piping modification, diesel generator preventative ma intena nce, and breaker preventative maintenance. Main transformer 2T backcharged. CT2 out of service for doble testing.

3. Unit 3 at cold shutdown for high pressure feedwater heater repairs. Condenser vacuum broken, condensate system shutdown. 313 I feedwater heater manway removed with tube repairs in progress.

SEQUENCE OF EVENTS

0730 Unit I operating at 100%, no major problems.

0735 Dispatcher contacts Control Room. 100KV line (CT-5) has been taken out of service for Transmission Service Inspection and OCB preventive maintenance. Should return to service by I530 hours.

0745 Switchboard operator receives outside phone call claiming that a bomb is planted in the Radwaste Facility.

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0805 - 0830 Search of area (dctailed by the phone cal) inside the Protected Area reveals a

"suspicious" package that appears to be a bomb. An emergency classification of "ALERT" should be declared (lie to "Discovery of bomb in the protected aren." This classification requires activation of the Emergency Responsc Organization and site assembly. Workers in the Unit I West Penetration Room installing a nd cutting hangers for the Instrument Air up-grade inadvertently leave their acetylene and oxygen bottles on and the lines charged when they report for Site Assembly.

Approximately 0830 - 0930

State of South Carolina Emergency' Preparedness. Oconee County Emergency Preparedness, Pickens County Emergency Preparedness should be notified of the event. NRC should be notified within one hour of the emergency classification. Security will also activate the Security Contingency Plan. Calls should be made to a "bomb" squad to assist in defusing the bomb. The Emergency Response Organization should be activated with turnover in place between the Technical Support Center anrd the Control Room within 75 minutes of the Alert classification. The Emergency Operations Facility should be staffed and operational within 75 minutes of the emergency classification. Turnover may not have taken place.

Areas of concern for Emergency Coordinator:

# Evacuating people from the Radwaste Facility # Getting people here to "disarm" the bomb * Large number of people onsite for two outages

Approximately 0915

Unit I is operating at 100% power. ITA bus (6900V) lockout (spurious overcurrent relay trip) occurs and trips normal incoming breakers and blocks startup incoming breakers from closing. Reactor coolant pumps IAl and I BI trip. Reactor protective system channels trip but control rod drive breakers fail to open. Operators enter the Emergency Operations Procedure and take actions to try to shutdown the reactor. Turbine is manually tripped and auxiliarics transfer to CT-1. Reactor coolant system pressure increases to > 2450 psig. DSS channels I & 2 should actuate. DSS fails to de-energize regulating group rods. The reactor cannot be tripped from the Control Room and the control rods cannot be inserted from the Control Room. The reactor is tripped by manually removing power to the control rods in the cable room and the turbine building. Main feedwater pumps may trip during the ATWS event. Emergency feedwater pumps start and supply the once through steam generators if the main feedwater pumps trip. Some failed fuel (less than I %) is assumed to have occurred as a result of the ATWS.

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Approximately 0930 - 0945

The emergency classification of "Site Area Emergency" should be declared due to "ATWS - 2 or more RPS channels trip without automatic reactor trip AND control rods remain withdrawn and cannot be manually tripped or inserted from the Control Room."

Approximately 1045

Unit I is being maintained at. Hot Shutdown, main feedwater or emergency feedwater is feeding the once-through steam generators. Two reactor coolant pumps are providing forced circulation cooling.

Unit I startup bus faults (insulator fails) in the isolated phase bus. El and E2 breakers receive trip signal. PCB (17 and 18) trip to isolate fault. Main feeder bus monitor panel will monitor main feeder bus undervoltage for 20 seconds. After that time, it will initiate an emergency start on the Kcowce unit tied to the underground. CT-4 becomes energized. SK-1 and SK-2 close in and energizes Unit I standby bus. After an additional 10 seconds, SI and S2 close in to the main feeder bus. Main feeder buses are now energized from CT-4.

Keowee Unit I is out of service. Kcowec Unit 2 trips from 86 E-2 caused by an 87G-2 relay target.

CT-5 is not energized. 100kv line has been taken out of service by the dispatcher for Transmission Inservice Inspection and OCB 101 scheduled maintenance.

Power is lost to the following equipment: hotwell and condensate booster pumps, motor driven emergency feedwater pumps, emergency safeguard pumps including the high pressure injection pumps. The turbine driven emergency feecdwater pump is out of service due to a 72-hour LCO and will not. be available until 8/11/92 at 1800.

Approximately 1100 - 1115

An emergency classification of "General Emergency" should be declared by the Emergency Operations Facility. The classification should be based on "Failure of offsite and onsite AC power along with the total loss of emergency feedwater makeup capability." Protective action recommendation to shelter out to five miles should be made initially to offsite groups (State of South Carolina, Oconee County and Pickens County via an emergency notification form.)

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Approximately 1115

Reactor coolant makeup pump to Unit I trips on emergency high vibration. With no makeup to the reactor coolant pump seals, a large LOCA occurs

(approximately 2000 gpm). Core uncovery is imminent unless power is restored to

vital equipment. (Note: At the rate of 2000 gpm. it will take I hour and 45 minutes to uncover the core.)

Jobs in progress to restore cooling to the unit:

Turbine driven emergency feedwater pump repairs

CT-1 (Will take approximately 2 hours to determine the problem. Can either replace the insulator or open 7KV transformer gang.)

Kcowcc Unit I is out of service due to unscheduled maintenance. Keowee 2 failed to start on emergency start signal. (NOTE: Controller will not allow power to be restore( until the core is uncovered to provide the amount of activity needed to drive the ingestion pathway exercise).

100KV line is out of service for transmission service inspection. OCB101 is out of service for scheduled maintenance.

Problems that will have to be addressed by the Emergency Response Organization for a loss of power scenario:

4 Radiation monitors used for (lose assessment (except RIA 57-58 high range monitors) will not have power.

* Dose calculations will have to be done based on what was being seen offsite

* Assume release in progress based on RIA 57-58 on scalc and a large-break LOCA will cause pressure in the building to increase. Very little activity (if any) will be seen by field monitoring or onsitc RP teams.

* Data system will be operable but readings given for radiation monitor readings will be bogus data.

With a core uncovery imminent (approximately 2 hours) and projections that power may be restored in 2 hours. the EOF Director should recommend at a minimum that people living 2 miles around the site and 5 miles downwind should be evacuated. Less than 20% gap activity is in containment. Containment is intact. However, he may be pro-active and recommend that 5 miles around the and 10 miles downwind should be evacuated based on the fact that if the core is uncovered before power can be restored, greater than gap activity would be released to containment.

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* Approximately 1245

A spark ignites the gaseous mixture of acctylenc and oxygen in the West Penetration room. (See 0805-0900 sequence of events). The explosion blows the siding off the West Penetration room and rips holes (equivalent to a 4" or 5"

diameter opening) in the reactor building purge (Iuctwork at Reactor building penetration #19 between valves I PR-5 and I PR-6, resulting in a radioactive release to the environment. The explosion causes I PR-6 to allow slight leakage from the containment building to enter the (Luctwork. Fire Brigade responds to the

explosion/fire, but the radiation levels prevent action. The fire quickly burns itself out.

Protective action recomnmendations at this time from the Emergency Operations Facility would be:

If people were not evacuated out to five miles and ten miles downwind, with a release in progress greater than gap, a recommendation to shclter people until the plume passed may be in the best interests of the residents of Oconee and Pickens Counties. This would have to be discussed with t he State of South Carolina by the Emergency Operations Facility Director.

Between 1300 and 1330

Power is restored to CT-I by opening 7KV disconnect at CTI or by replacing insulator on the isolated phase bus. High pressure injection and emergency feedwater are re-established. Reactor building spray and containment cooling will place radioactive iodine into solution. It will take approximately 12 hours to reach cold shutdown. The OSC will work to scal the containment leak at RB penetration #19.

Approximately 1300

Release should stop after Operations cycles PR6 to close.

The Operational Support Center would begin to develop a temporary patch to the side of the building.

1330 Plume Exposure Pathway Exercise terminated. Recovery will be entered into by negotiating with offsite agencies and the Nuclear Regulatory Commission.

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RADIOLOGICAL ASSESSMENT

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0 ENCLOSURE I

ASSESSMENT

SUBMERSION AND INHALATION

Source term assessment is based on a LOCA.

969 Ci/sec Xenon 133 equivalent

6.43 Ci/sec lodine 131 equivalent

0.64 Ci/sec CS-137 (0.1 x 1-131 equivalent)

NOTE:* The activity is discharged through the damaged west penetration room wall. Assume both ground lcVcl and unfiltered.

* METEOROLOGY DATA AND ASSESSMENT

Wind from 345 degrees

Wind speed 6 mph

Stability Class D (Delta T -0.50)

DISTANCE X/Q (sec/m3) DISTANCE X/Q (sec/m3)

(MILES) (MILES) 1 2.00E-5 6 1.67E-6

2 8.67E-6 7 1.33E-6

3 4.83E-6 8 1.12E-6

4 3.OOE-6 9 9.50E-7

5 2.33E-6 10 8.17E-7

Note*: 137CS approx. 0.643 Ci/sec = approx. 0.10 (Iodine 131 equivalent)

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ENCLOSURE 2

DUKE POWER COMPANY

OCONEE NUCLEAR SITE

ANNUAL EXERCISE 92-4

PLUME EXPOSURE PATHWAY

ESTIMATE OF PROJECTED OFFSITE DOSE

Distance Wholc Body Child Thyroid Whole Body Child Thyroid Dose Rate mr/hr Dose Rate mr/hr Dose mr Dose mr

Site Boundary 6.6E + 02 2.9E' + 05 1.6E+ 02 7.26E + 04

2 miles 2.31+02 1.31+05 2.0E+01 3.15E+03

5 miles 7.61+01 3.4E+04 1.9E+01 8.5E+03

10 miles 2.6E+01 1.21+04 6.61"-00 3.0+03

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ENCLOSURE 3

DUKE POWER COMPANY

OCONEE NUCLEAR SITE

DOSE ASSESSMENT AT 6 MILES

Noble Gas - Adult Whole Bodv

Dose Rate 54.6 mrcm/hr Dose 13.7 mrem

Iodine - Child Thvroid

Dose Rate 24.2 R/hr Dose 6.1 R

DOSE PROJECTIONS ARE BASED ON THE FOLLOWING:

1115-1300 RIA 49A approx. 8000 cpm RIA 49A correlation factor LOCA 1.5 hr after trip 2.26E-4 uci/cc/cpm

Leak rate 6.84E+09 ml/hr (approx. 4027 CFM) Duration of leak 15 minutes

1330+ RIA 57/58 276 R/hr

RIA 57/58 correlation factor (1.07 uci 133/cq/mi R/hr) R/hr

Iodine 131 equivalent / Xenon 133 equivalent ratio 6.63 E-3

Leak rate 1.39 El I ml/hr

Duration of leak 15 minutes

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ENCLOSURE 4

DUKE POWER COMPANY

OCONEE NUCLEAR SITE

ASSESSMENT

INGESTION PATHWAY EXERCISE

8/1I TO 8/12 1992

August 1. 1992

1400 Plume is 6 miles south southeast of Oconee. Wind shifts. New direction from 260 degrees. Wind speed increases to 12 mph.

Stability Class D Delta T -0.50

1600 Rain. Plume washed out in the Powdersville area.

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EN:~CLOSUR1E 5

,pF~lT,,'KiT S 7.~i FflT, 71M1E L a;2.: oo C~iUFREIIT EFFLL'E

-- 7~1!IT. 1 KCURRENT M'ET

- I ~ENTEF:L INE ..'iLUI

L iTDEC rnr

IIT I It. I'I~lI I. i 1.1.fE

A Ij II_ I-:. L 11 1

t_ G I 4D

77, W! is - nee

..~ .. 7".- -t*i

11D DEAY OF PPOwT0 OF E+

WELEOSE Hr. .0 ft. RELEWIT .- catainet

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ENCIOSUnR 6

WHL BOY 0EFTE -AT:--. 4.,PE-i7-G; ILC

[,:!..::'... 4......I CURRFENT MlET

G" L I!- Tf !. :;FEEl -- 0L~ p

I LI ;r.STBILITY' [ i

CETELINE HAL

1 5- -. 4

1. 1 2" 3,2E

II' LEnDI..4

.T rrl t r-",. I

............

.. ..: .......

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IENCLO0SUIRE 7

~::'plT .. ~TFEW .~.. TTK J L 245: 00 - 17!-FiiHT EFFLLE

CUR:RENT MET

S1 F.LE .- 0

L~~~~~~~~~

E TA rIVC~ :---F

E:i~ f

.:..~

DE

-. 7I

..~ .F .Ti .. .' .H .... ... . CL I Lj 2-1

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NUCLEAR FACILITIES Ec AFFECTING

Greenville C ene

SOUTH CAROLINA Pickens ,Sparteanbuirg

Don* Unon hastild l a rbr

F Anderson Laurena Dilon

F ADerli ngton

NewherryY

Marion AbbetileLee

reenwooFlorence

0 Saluda flehland li orry

Mecorm c - - LexingtonSrne

Is,~ dgefl

Calhoun k Clarendon Williamsburg

/Alken A. H.B. ROBINSON

Orangeburg B. OCONEE

C. McGUIRE (NC) w Bambergv Dorcheste Berkeley

GH D. CATAWBA

Allende

E. V.C. SUMMER colleton

F. BRUNSWICK (NC) Charleston

G. VOGTLE (GA) LEGEND

H. SAVANNAH RIVER SITE (DOE) afor SHADED AREAS : 50 MILE EPZ

I. CHARLESTON (DOD) INNER CIRCLE : 10 MILE EPZ

Miles 10 0 10 20 30 40 50

10 0 10 20 30 40 50 60 70

Kilo meters

Page 28: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

EXERCISE DATA AND MESSAGES

Page 29: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

EXERCISE DATA AND MESSAGES

Messages to be used in the excrcise are located in the Appendices of this plan. Messages will be provided to the players verbaliv. We havc found that giving players paper to read is not conducive to emcrgency situations. During a real emergency most instructions are verbal (either face to face or over the phone). For this reason, Oconee has moved away from written messages. Information will be provided to the players at the indicated times on the message shect utilized by the controller. Contingency messages will be provided, by the controllers as necessary to keep the scenario on track or to provide information contingent upon player actions.

The scenario will be driven by the simulator. Operators will receive indications directly from the simulator at the training center. Personnel at other locations will receive actual

data from the simulator through the data transmittal system or through other communications. Should problems occur with the simulator and/or data system, Reactor

Engineering is responsible for providing data that has been gathered from the simulator instrument readings. This information will be provided in hard copy to the TSC, OSC and EOF.

Offsite and onsite radiological monitoring data will be provided to players after an actual reading has been made. Radiological and Chemistry results will be provided after samples are pulled and anlayzed. Any exceptions will be noted in the exercise messages.

Page 30: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Sccuritv I

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1, 1992 Time: 0740

PLANT CONDITIONS: Unit I - 100% Power Unit 2 - Shutdown Unit 3 - Shutdown

TO: Switchboard Operator

FROM: Security Controller (Phone call)

MESSAGE: I have planted a bomb in the Radwaste Facility.

ACTIONS EXPECTED: Switchboard operator should report bomb threat to Security Supervision. Security should implement appropriate contingingency plan. Operations Shift Supervisor should be notified by Security Supervision.

Controller Note: The search needs to be completed and bomb discovered prior to 0830 hours. The ALert should be declared as close to 0830 as possible.

Page 31: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Security 2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: 1100

TO: Simulator Control Room (2718 or 2725)

FROM: Security Shift Supervisor

MESSAGE: Heard an explosion near CTI.

ACTIONS EXPECTED: Report to the OSC.

Page 32: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Security 3

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I 1, 1992 Time: Approximately 1245

TO: Simulator Control Room (2718 or 2715)

Security in the OSC

FROM: Security Shift Supervisor

MESSAGE: Loud explosion. Walking outside on the Unit I side and saw part of the siding blown away from the Penetration Room.

ACTIONS EXPECTED: Control Room should request the OSC to investigate. Security Manager should also notify the OSC Coordinator of the information received.

Page 33: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Page 1 of 2

Checked Control Copy

Date/Time

Unit

OP/1/A/1102/20

ENCLOSURE 5.7

CONTROL ROOM SRO TURNOVER SHEET

1. Perform the following whenever assigned unit(s) is above Cold Shutdown:

19-07 07-19

1. Review assigned unit's SRO and RO logs.

2. Review R&R logs, SRO and RO turnover

sheets for any LCO's.

3. Review the unit status with each Unit

Supervisor.

4. Make rounds in assigned Control Room. Inform

Unit Supervisor and/or Control Room Personnel of any abnormalities.

5. Review the printouts for the computer alarm

summaries, Unit Events Recorder alarm summaries and the Switchyard Events Recorder. Forward the printouts to the Unit Engineer.

2. UNIT STATUS @ 0600 18

Unit One

Rx Power /____

RCS Temperature

RCS Pressure /j 0__D

Unit Two

Rx Power

RCS Temperature

RCS Pressure ____1__

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Page 2 of 2

OP/1/A/1102/20

ENCLOSURE 5.7

CONTROL ROOM SRO TURNOVER SHEET

3. GENERAL NOTES

4. TURNOVER ITEMS

Unit One 62&5,

Unit Two 4Pe4eha /2

OFF-GOING ON-COMING

0700

1900

Page 35: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Page 1 of 2

Checked Control Copy

Date/Time .OP/1/A/1102/20

ENCLOSURE 5.13

SHIFT SUPERVISOR TURNOVER SHEET

1. Perform the following each shift:

19-07 07-19

1. Review each unit's SRO log.

2. Review each unit Supervisor's turnover sheets.

3. Review the unit status with each Unit Supervisor.

2. UNIT STATUS

Unit One ___

Unit Two , -S

f e~o ) leI c4eatr

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Page 2 of 2

OP/1/A/1102/20 ENCLOSURE 5.13

SHIFT SUPERVISOR TURNOVER SHEET

Unit Three __ _ __ _ __ _ __ _ _ __ _ __ _ __ _ _ __ _ __ _ __ _ _

3. GENERAL NOTES

OFF-GOING ON-COMING

0700 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1900 ___________________________________ _

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Page 1 of 3

Checked Control Copy . Date/Time______________

OP/l/A/1102/20

ENCLOSURE 5.1

UNIT SUPERVISOR TURNOVER SHEET

1.0 Unit Status-@ 0600 1800

Rx Power _ MWE _

RCS Pressure A42v __

RCS Temperature

2.0 Turnover Items (Examples: Nonroutine OPs or PTs, equipment out-of-service,

out of normal conditions or trends, or temporary operating

guidelines.)

Initial Addition/Deletion

2)-7 5F b d___/____

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Page 2 of 3

OP/l/A/1102/20 ENCLOSURE 5.1

UNIT SUPERVISOR TURNiOVER SHEET

2.0 (Continued)

Initial

Addition/Deletion

I in "Addition"______space___indicates____anitem___brought___forward___from_ _the __previous___day._

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Page 3 of 3

OP/1/A/1102/20 ENCLOSURE 5.1

UNIT SUPERVISOR TURNOVER SHEET

3.0 List any systems/components that are in a degraded mode of operation

as permitted by T. S. and applicable time limits.

Date/Time Required to be in

Date/Time Taken Service per T. S. Section - List Initial

System/Component Out-of-Service Date/Time T. S. Section Addition/Deletion

4.0 R&R Book has been reviewed for any equipment out of service which has/will

put the unit in a degraded mode of operation or could cause problems in

unit evolutions within the next 12 hours.

1900-0700

0700-1900

5.0 Unit Supervisor Turnover Sheet completed and corrected through the end of

shift with additions and deletions initialed.

OFF GOING ON COMING

0700

1900

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Page 1 of 4

Checked Control Copy

. Date/Time______________

OP/l/A/1102/20

ENCLOSURE 5.6

SHIFT TURNOVER SHEET

1.0 Unit Status @ 0600 1800

Rx Power /0070 ___ GWD Vent Header '§ r (Split or Crossconnected)

MWE__

RCS Pressure ___ CSAE drains L S

(TBS, CST)

RCS Temperature 49 _L Aux. Steam Header Supply 14L L (Unit 1, Unit 2, Unit 3,

Aux. Boiler)

2.0 Turnover Items (Examples: Nonroutine OPs or PTs, equipment out-of-service,

out of normal conditions or trends, or temporary operating

* guidelines.)

Initial

Addition/Deletion

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Page 2 of 4

OP/l/A/1102/20

ENCLOSURE 5.6

SHIFT TURNOVER SHEET

2.0 (Continued)

Initial Addition/Deletion

I in "Addition" __________________________________________ space____ inicts n tm rogt orad ro heprvou dy

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Page 3 of 4

OP/l/A/1102/20

* ENCLOSURE 5.6

SHIFT TURNOVER SHEET

3.0 List any systems/components that are in a degraded mode of operation

as permitted by T. S. and applicable time limits.

Date/Time Required to be in

Date/Time Taken Service per T. S. Section - List Initial

System/Component Out-of-Service Date/Time T. S. Section Addition/Deletion

4.0 List any systems/components that are required to be tested/inspected as a

result of operation in a degraded mode per Technical Specifications.

Initial

System/Component Frequency of Test or Inspection Addition/Deletion

__III___

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Page 4 of 4

OP/1/A/1102/20

ENCLOSURE 5.6

SHIFT TURNOVER SHEET

5.0 R&R Book has been reviewed for any equipment out of service which has/will

put the unit in a degraded mode of operation or could cause problems in unit

evolutions within the next 12 hours.

1900-0700

0700-1900

6.0 Shift turnover sheet completed and corrected through the end of shift

with additions and deletions initialed and the on-coming R.0. has reviewed

the general status of the Control Board.

OFF GOING ON COMING

0700

1900

7.0 Shift Turnover Sheet reviewed by Control Room SRO (if RCS > 200 0F).

OFF GOING ON COMING

0700

1900

Page 44: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Simulator I

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August I1. 1992 Time: 0735

PLANT CONDITIONS: Unit I 100% power Unit 2 - Shutdown Unit. 3 - Shutdown

TO: Shift Supervisor

FROM: Spartanburg Dispatcher

MESSAGE: 100KV line (CT-5) has been taken out of service for Transmission Service

Inspection and OCB Preventive Maintenance. Will be out of service until 1530.

ACTIONS EXPECTED: Notify Operations personnel.

Page 45: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Simulator 2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: 1050

TO: Simulator Instructor

FROM: Simulator Controller

MESSAGE: Enter Emergency start signal for Kcowec 2. Keowee 2 fails to start. 86E lockout received on Keowee Unit 2.

ACTIONS EXPECTED:

Page 46: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Simulator 3

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11. 1992 Time: 1115

TO: Simulator Control Room

FROM: Kcowec Operator

MESSAGE: Unit 2 has a 87G-2 relay target.

ACTIONS EXPECTED: Contact OSC to dispatch Power Delivery team to Keowee.

Page 47: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Operations I

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time: Approximately 0915

TO: Non-Licensed Operator

FROM: Operations Supervisor in the OSC

MESSAGE: De-energize control rod drive systen in the cable room, open the

Unit I AC and DC breakers.

ACTIONS EXPECTED: Go to the cable room and simulate opening CRD breakers and call Simulator control room.

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MESSAGE SHEET

MESSAGE NUMBER Operations 2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: Aftcr 0915

TO: Non-licensed operator

FROM: Opcrations Supervisor in the OSC

MESSAGE: De-cnergize control rod drive system at, 600V load center IX9 and 2XI.

Open CRD "normal" and alternate supply breakers.

ACTIONS EXPECTED: Go to IX9 and 2X1 and simulate opening control rod drive

breakers and call Simulator control room.

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MESSAGE SHEET

MESSAGE NUMBER Operations 3

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1, 1992 Time: Approximately 0920

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: Go to ITA bus. Look for targets and check on status of bus.

Targets found: 51X reilay located on ITA-2.. Lockout rciy 86 located on ITA-2 has operated.

ACTIONS EXPECTED: Go to ITA bus. Call Simulator control room to report finding.

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MESSAGE SHEET

MESSAGE NUMBER Opcrations 4

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: Shortly after 1045

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: CTI has tripped. Go and inspect. for darnage.

ACTIONS EXPECTED: No damage observed.

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MESSAGE SHEET

MESSAGE NUMBER Operations 5

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time: After power failure

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: Start diesel air compressor an(id place on header and open SA-143.

ACTIONS EXPECTED: Simulate above actions. Contact Simulator Control Room.

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MESSAGE SHEET

MESSAGE NUMBER Opcrations 6 (Contingency Message)

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcisc 92-4

Date: August I I 1992 Ti me: Aftcr 1100

TO: Non-licensed operator

FROM: Operations Supervisor in Control Room

MESSAGE: Assist clectricians with swapping leads to IA IP! pump from auxilliary service water switch gear.

ACTIONS EXPECTED: Simulate above actions.

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MESSAGE SHEET

MESSAGE NUMBER Operations 7

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: After I 100

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: Go to block house. Check on any main feeder bus targets.

ACTIONS EXPECTED: Go to block house. Report findings to Simulator Control Room.

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MESSAGE SHEET

MESSAGE NUMBER Operations 8

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time: After 1245

TO: Non-licensed operators

FROM: Announcement over PA system Radio pagers activated

MESSAGE: Respond to fire/explosion in Unit I West Penctration Room.

ACTIONS EXPECTED: RP should stop Fire Brigade from responding to the vest penetration room due to high ICcls of radiation. Explosion has caused a hole in the RB purge ductwork. Very high lcycis of activity are being released to the atmospherc.

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MESSAGE SHEET

MESSAGE NUMBER Opera tions 9

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August. I 1. 1992 Time: After I 100

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: Go to Unit I steam (lumps and operate per proceIure.

ACTIONS EXPECTED: Simulate above and c,'ll Simulator Control Room.

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MESSAGE SHEET

MESSAGE NUMBER Operations 10

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time: After 1100

TO: Non-licensed operator

FROM: Operations Supervisor in the OSC

MESSAGE: Go to SSF. Line tip Unit I RC makeup pump to Unit 1. (Use procedure AP/O/A/1700/25 - SSF Emergency Operating Procedure)

The RC makeup starts and runs for several minutes but trips on high vibration.

ACTIONS EXPECTED: Simulate aboyc activity. Notify Simulator Control Roon and OSC.

Note to Controller: Provide information about high vibration only if there is ain

indication on the control panel in tile SSF control room that would identify the problem with the pump.

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MESSAGE SHEET

MESSAGE NUMBER Radiation Protection I

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I 1, 1992 Time: 0800 - 1045

TO: RP Technicians/Su pervisors (sent out to su rveV/Sa m piC from the OSC)

FROM: RP Controller

M ESSAG E:

Direct radiation values: Current results from PSI or as posted.

Airborne values: As sampled or posted.

Smears: As sampled or posted.

RIA 47 - approximately 2.74E4 CPM

RIA 48 - approximately 8.0E2 CPM

RIA 49 - approximately L.0E4 CPM

RIA 49A - 0.0 cpm

ACTIONS EXPECTED: Technicians should record results and report results to the OSC.

Page 58: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Radiation Protection 2

DUKE POVER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time: 1045-ll 5

TO: RP tecinicians/Supcrvisors

FROM: RP Controller

MESSAGE: On location during RP surveys and RP coverage:

Direct radiation va lues: Current results from PSI or as posic(l.

Airborne values: As sampled or posted.

Smears: As sampled or posted.

RIAs: Unavailable (loss of power). (Screens in the Control Room vill show Magenta @@ @( W(@@ marks. Values from the OAC will be a zero.

ACTIONS EXPECTED: Record results and report to emergency response organization in the OSC.

Page 59: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Radiation Protection 3

DUKE POWER COMPANY

- OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11. 1992 Time: 1115 - 1245

TO: RP tech nicians/Supervisors

FROM: RP Controller

MESSAGE: Radiological information will be provided to RP technicians from attachments (8 pages: I page is the Site Area Map. 7 pages show plant elevation floor

pla n).

RIA information is unavailablc due to loss of power.

Note to controllers: OAC printout would show 0 for readings from all radiation monitors

except RIA 57 and 58. These two monitors are battery backed and would still have a

readout in the Control Room. All other monitors would show a magenta screen with

@q@a @@ signs on the screens indicating a loss of communication.

ACTIONS EXPECTED: Record results and report to emergency response organization in the OSC.

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Exercise 92-4 RP3 1115-1245 hours

OCONEE SITE AREA MAPS

3 R/hr 30 feet in yard

17 R/hr outsid wal

F--I

2 R/hr approx. 10 feet distance inside

- -auxilliary uilding

I

I

I l

11

I

I

I I

I ~

* I

I I L-----------------------x--

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Exercise 92-4 RP3 1115 -1245 hours

OCONEE SITE AREA MAPS

3 R/hr approx. 3) feet in yard

I

ID 17 R/hr out ide wall FT~

S2 R/hr appr )x. 10 feet'distance inside ) '---'auxilliar7 building

I,

I

I

II

10

II

L - - - - - - -- -- -- 115 - 124 ho r

I I

I I

3 R/hr aprxI ee nyr

I __ L 17R/rutieal I-

I I

I /rapr>.10fe istneisd

I --

L/

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Exercise 92-4 RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING BASEMENT HPI-LPI ROOMS - ELEVATION 758+0

2 R/hr approx. feet dit

n1a

17 R/hr outside . .

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Exercise 92-4i RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FIRST FLOOR 2 R/hr approx. 10 feet distance ELEVATION 775+0

U~l#11-2 UNIT-CAY HEAl REMOVAL

IAS4 DECAY HEAt REMOVAL IRIA13 OOLR ROOM COOLER RO(E

A U2ABHOUI

I 1

____121 291IU

17 R/hr outside O O O

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Exercise 92-4 RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

2 R/hr apprx. 10 feet distance AUXILIARY BUILDING - THIRD FLOOR ELEVATION 796+6

A39 ImaA IRIAll 32) 2RIAlI IRIA 336

a a

Illinfil a ap onu R A 3 5 s3 I

3127

0 0 1 R/h

10 IRIA/

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Exercise 92-4

RP3

1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

2 R/hr approx. 10 feet distance AUXILIARY BUILDING - SECOND FLOOR ELEVATION 783+9

(1.

2 LETDOWN FIL a PURIFICATIO 01MIN 1 E OWN FILTER

23 214 1

1JU 0000

ifi

17 R/hr outside

SPEN I FUEL FILTER

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Exercise 92-4 RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FOURTH FLO( 2 R/hr approx. 10 feet distance ELEVATION 809+3

0 C

o 0

17 R/hr

00

Page 67: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FIFTH FLOOR

2 R/hr approx. 10 feet distance ELEVATION 822+0

oa4

0 0)

a~ a oa3

0

17 R/hr outside

Page 68: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP3 1115 - 1245 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - SIXTH FLOOF ELEVATION 838+0

17 R/hr outside 2 R/hr approx. 10 feet distance

IRIAZ IRIA) 2RIA2 2R1A3

LJ -- 89

11

0 0

rau

Page 69: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Radiation Protection 4

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: 1245-1300 (approx.)

TO: Radiation Protection Technicians/S u pervisors

FROM: Radiation Protection Controller

MESSAGE: Radiological information will be provided to RP technicians from

attachment (Site area map).

ACTIONS EXPECTED: Record results and report to Emergency Response Organization

at the OSC.

Page 70: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP4 1245 - 1300 hours

OCONEE SITE AREA MAPS

-- - -~ -

Rad levels 800 R/hr

Gross swipes 800 mRad/hr

Rad levels 80 R/h

Gross swipes I 80 mRad/hr

040

* Rad levels '8 R/hr

Gross swipes

mRad/hr/ LI

Page 71: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER Radiation Protection 5

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I 1, 1992 Time: Approx. 1300-1400

TO: Radiation Protection Techni icia ns/Su perx'isors

FROM: Radiation Protection Con troller

MESSAGE: Radiological information will be provided to RP technicians from attachments (8 pages: I site area map and 7 pages showing elevation floor plan).

RIA 47 Offscale high

RIA 48 Offscale high

RIA 49 Offscale high

RIA 49A Approx. 3.4E4 cprn

ACTIONS EXPECTED:

Note to the controller: These readings will be provided to the players if power has been

restored. Continue with previous data until power is actually restored and power has been returned to the radiation monitors.

Page 72: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP5 1300 - 1400 hours

OCONEE SITE AREA MAPS

600 mR/hr approx. 30 feet distane in yard

I 3 R/hr

Rad level 8 R/hr ) Gross Swipes 800 mRad/hr

Rad level 100 mR hr

Gross Swipes 80 mRad/hr

Rad level 10

Gross Swipes 8 mRad/hr

SI

Page 73: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP5 1300 - 1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING BASEMENT HPI-LPI ROOMS - ELEVATION 758+0

400 m]R/h'r approx. 10 f 'e

.00 a 1O, OO , 0 0

3 R/hr ---

Page 74: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP5 1300 -1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FIRST FLOOR ELEVA~TION 775+0

400 mR/hr approx. 10 feet distance

IJ41 1-1 DEA3 lCAY HEAT REMOVAL

IRIA14 DECAY HEAT REMOVAL IPA3COOLER 00"~

6i4 li 12 2

(J D C2Q

le~-4J' q

QS 2914

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0 Exercise 92-4 RP5 1300 - 1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - SECOND FLOOR ELEVATION 783+9

400 mR/hr approx. 10 feet distance

LET006M FILTER PURIFICATION OfMIN LtDOWN FILIFR H A2 HATCH AREA HATCH AREA HAICH AREA

2 21J42 215V

3 R/hr

SENT FUEL FILTER

AND, DEMIN ROOM4

Or M

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Exercise 92-4

RP5 1300 - 1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - THIRD FLOOR ELEVATION 796+6

400 mR/hr approx. 10 feet distance

IPid9 3 IAIAJg IRIAII 323 2RIAI1 1AR9 336

11U

n a

gL 11 a

_ED

I 0RIAh A& F1GROSS SWIPE

800 mRad/hr

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Exercise 92-4 RP5 1300 - 1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FOURTH FLO ELEVATION 809+3

400 mR/hr approx. 10feet distance

0O

040

3 R/hr

FO

Page 78: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP5 1300 - 1400 hours

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUXILIARY BUILDING - FIFTH FLOOR ELEVATION 822+0

400 mR/hr approx. 10 feet distance

IRIAl

u u --- 00 0

a an _3_ 0 0

(EDi

3 R/hr

Page 79: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

Exercise 92-4 RP5 Sheet 7 of 7

1300 - 1400 hours ENCLOSURE 15

AUXILIARY BUILDING FLOOR PLAN LAYOUT

AUX1LIARY BUILDING - SIXTH FLOI ELEVATION 838+0

400 mR/hr approx. 10 feet distance

3 R/hr outside

SIRIIA2 IRIA3 2RIA2 2RIA3

0 0

I

Page 80: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER l&E I (contingency message if OSC-sends l&E todcterminC why control rod drive did not engage)

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August I1, 1992 Tinic: After 0915

TO: l&E Technicians

FROM: 1&E Controller

MESSAGE: Trouble shoot why DSS system did not trip.

DSS actuatcs however, the CRD gate drives are not de-energized. All control room indications and panel indications indicate that the trip action is complete. Control room alarms are received and indicator lamps on the output relays are illuminated and indicate correct operation of DSS.

ACTIONS EXPECTED: During an on-going emergency it is not immediately important to determine the root cause why the Control Rod Drives did not engage. However, for the purpose of this message the technicians may come to the following conclusion:

The DSS output relays contacts fail to change state but the system indicates that actuation has occurred. The failure is in the output relay. The output contacts failed to

operate. However, the relay indicator lamp is illuminated which indicates correct operation. The failure of the contacts would not remove the CRD gate drive signal and therefore the CRD does not drop.

Page 81: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE SHEET

MESSAGE NUMBER l&E 2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August 11, 1992 Timc: After 0915

Background: CRD breaker PM recentlv re adjusted the undervoltagc coil latch and cleaned all 6 breakers. Brcakers wcrc testcd and dcClar(d operable.

TO: I&E Technicians

FROM: l&E Controller

MESSAGE: CRD breakers AC-10, AC-11. CBI, CB2. CB3, and CB4 failed to open on an RPS Trip.

ACTIONS EXPECTED: Trouble shoot. May be able to determine that mechanical binding of the breaker latch mechanism has occurred.

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MESSAGE SHEET

MESSAGE NUMBER l&E 3

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1, 1992 Time: 0930

TO: OSC Powcr Delivery Team

FROM: l&E Controller

(Note to Controller) Team should go to the Unit I Control Room. Actually look at the

events recorder. When they do, then give the information below. Do not simulate going

to the control room.

MESSAGE: Unit I Plant. cvent recorder shows the following alarms:

1. Pt#201

2. PT#203

Relay 51X on ITA-2 and SWGR Lockout (86) has operated.

ACTIONS EXPECTED: Investigate problem. Determine possible causes. Suspect Overload relay defective.

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MESSAGE SHEET

MESSAGE NUMBER I&E 4

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August I 1, 1992 Time: 1045

TO: OSC Power Deliverv Team

FROM: I&E Controller

MESSAGE: Event recorder shows that 86BU I operated first, followed by 86CTI.

ACTIONS EXPECTED: Expect to find possible fault on 7KV isolated phase bus. Controller will allow team to trouble shoot the possible problems before providing information that will allow them to determine the problem.

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MESSAGE SHEET

MESSAGE NUMBER I&E 5

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August I I, 1992 Timc: After 1050

TO: OSC Power Delivcry Team

FROM: I&E Controller (Team should actually go to Kcowec Hydro Station to Unit

2 panel to look for the lockout).

MESSAGE: Keowce Unit. 2 has received an 86E lockout.

ACTIONS EXPECTED: Investigate the problem.

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MESSAGE SHEET

MESSAGE NUMBER l&E 6

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11, 1992 Time: 1 100

TO: OSC Power Delivery Team

FROM: l&E Controller (Note to controller: A message has been provided for security to contact the Control Room at I 100 to provide information that a loud explosion was

heard from CTI. This information about the explosion should be reported to the OSC

by the Simulator Control Room which in turn should be provided to the team prior to

dispatch from the OSC. You should not have to provide this information to the team. r However, if the information concerning an explosion from CTI will be pertinent to the

team determining the resolution to the power failure, you will have to determine a way

to provide it to them. Example: If the team has a radio. then you can tell them that they have been notified from the OSC that Security heard a loud noise from CTI around 1100.)

MESSAGE: Security reports to Simulator Control Room that they heard a loud explosion near CTI.

ACTIONS EXPECTED: Proceed to CTI and inspect transormer and bus work.

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MESSAGE SHEET

MESSAGE NUMBER I&E 7

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1, 1992 Timc: 1130

TO: OSC Power Delivery Team

FROM: I&E Controller

MESSAGE: Target on Keowce (Unit 2) 87G-2 relay.

ACTIONS EXPECTED: Determine cause of problei. Possible causes:

(1) Defective relay

(2) Defective current transformer

(3) Wiring

Note: Keowee Unit I is out of service and will take 6 hours to service.

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M.ESSAGE SHEET

MESSAGE NUMBER l&E 8

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August 11. 1992 Time: Approx. I 130 - 1145

TO: OSC Power Delivery Team

FROM: I&E Controller

MESSAGE: 7 KV bus inspection glass looks burnt. Will take approximately I hour to inspect bus on the 7KV side.

ACTIONS EXPECTED: Report information to the OSC.

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MESSAGE SHEET

MESSAGE NUMBER l&E 9

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I 1. 1992 Time: 1230

TO: I&E Power Delivery Team

FROM: I&E Controller

MESSAGE: Found burnt insulator on 7KV isolated phase bus.

ACTIONS EXPECTED: Replace insulator or isolate 7KV CTI BUS and power up CTI from 230 KV switchyard.

Note to controller: Power must not be returned to the system until 1300.

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* MESSAGE SHEET

MESSAGE NUMBER EP I

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Excrcise 92-4

Date: August 1. 1992 Time: 0700

TO: Vice-President. Site Managers

PLANT CONDITIONS:

I. Unit I is at 100/o power.

LCO: Standby Shutdown Facility is out of service. Due back for 0540 on 8/21/92. See Unit 2 status.

LCO: Turbine Driven Emergency Feedwater Pump is out of service. Due back 8/11/90 at 1800.

LCO: Keowee Unit I is out of service for planned maintenance. Return to service at 1730.

2. Unit 2 in refueling shutdovn.

Fuel transfer canal filled with 2SF-I & 2SF-2 open. Making final preparations for starting defueling.

Condenser cooling water intake isolated and (rained for outage work. SSF out of

service for piping modification, diesel generator preventative maintenance, and breaker preventative maintenance. Main transformer 2T backcharged. CT2 out

of service for doble testing.

3. Unit 3 at cold shutdown for high pressure feedwater heater repairs. Condenser

vacuum broken, condensate system shutdown. 3B31 feedwater heater manway removed with tube repairs in progress.

ACTIONS EXPECTED: Notify station personnel.

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MESSAGE SHEET

MESSAGE NUMBER EP2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercisc 92-4

Date: August I1. 1992 Time: Trip time

TO: Switchboard Operator

FROM: Simu lator Controllkr (coilntact Switchboard at 3636 when information comes

back to the Control Room that the unit has been tripped from the cable room or power breakers.)

MESSAGE: Request switchboard to make the following announcement:

"'Steam relief valves have just lifted on Unit I

ACTIONS EXPECTED: Make announcement.

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MESSAGE SHEET

MESSAGE NUMBER EP 0

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Exercise 92-4

Date: August I1. 1992 Time:

TO: Exercise Participants

FROM: Drill Controllers

MESSAGE: Provide the following phone numbers to be used when calls are to be made

to these locations (luring the exercise:

Shift Supervisor 3724

Simulator Control Room 2718 2725

Control Room - EOF Liasion 2068

Switchboard Operator 3636

ACTIONS EXPECTED: Controllers should provide numbers to players. Players should

use accordingly.

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MESSAGE NUMBER Chemistry - 1

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time AFTER 1230

PLANT CONDITION: PER CONDITIONS AS STATED BY OSC EMERG. COORD.

TO: Chemistry technician sampling Unit one RCS

FROM: Controller

MESSAGE: See attached data sheets

NOTE: IF LETDOWN IS NOT ESTABLISHED NO FLOW WILL BE OBTAINED

FORM THE NORMAL SAMPLE POINTS.

ACTIONS EXPECTED: Notify OSC with results.

Page 93: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

CHM-1 RCS SAMPLE (NORMAL SAMPLE POINT)

Unit I Date 08-11-92 Time 1230 - 1530

pH: 6.41

Spec Cond:

Boron: *

Chloride:

Floride:

Susp. Sol: >1000

Dissolved Oxygen: 2.OPPM

RADIOCHEMISTRY DATA

Gross Beta

Gross Gamma

Ar-41 Na-24

Kr-85m 2.12 Rb-88 3.46

Kr-87 1.12 Co-58

Kr-88 3.44 Cs-134

Xe-133 682 Cs-137 0.365

Xe-133m 706 Cs-138 1.09

Xe-135 8.91 . Mn-56

Xe-135m 64.1

1-131 4.97

1-132 5.87.

1-133 5.29

1-134 1.2

1-135 2.68

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MESSAGE NUMBER Chemistry - 3

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time After 1230

PLANT CONDITION:

TO: Chemistry technician sampling Unit 1 A & B S/Gs

FROM: Controller

MESSAGE: 1.) See attached sheets:

ACTIONS EXPECTED: Report results to OSC.

Page 95: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

UNIT 1 A SG CHEM. MESSG. NO. 3A

Unit 1 Date 08-11-92 Time After 0930

pH:

Spec Cond:

Boron: *

Chloride:

Floride:

Susp. Sol:

Dissolved Oxygen:

RADIOCHEMISTRY DATA

* Gross Beta

Gross Gamma

Ar-41 Na-24

Kr-85m Rb-88

Kr-87 Co-58 4.3 e-7

Kr-88 Cs-134

Xe-133 1.9 e-7 Cs-137 1.3 e-7

Xe-133m Cs-138

Xe-135

Xe-135m

1-131

1-132

1-133

1-134

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UNIT 1 B SG CHEM. MESSG. NO. 3B

Unit 1 Date 08-11-92 Time After 0930

pH:

Spec Cond:

Boron: *

Chloride:

Floride:

Susp. Sol:

Dissolved Oxygen:

RADIOCHEMISTRY DATA

Gross Beta

Gross Gamma

Ar-41 <MDA Na-24 <MDA

Kr-85m <MDA Rb-88 <MDA

Kr-87 <MDA Co-58 <MDA

Kr-88 <MDA Cs-134 <MDA

Xe-133 2.4 e-7 Cs-137 1.8 e-7

Xe-133m <MDA Cs-138 <MDA

Xe-135 <MDA

Xe-135m <MDA

1-131 <MDA

1-132

1-133

1-134

1-135

Page 97: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE NUMBER Chemistry - 4

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time AFTER 0930

PLANT CONDITION:

TO: Chemistry technician sampling Unit 1 hotwell.

7 .FROM: Controller

MESSAGE: 1.) Activity less than detectable.

ACTIONS EXPECTED: Report results to OSC.

Page 98: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

UNIT 1 HOTWELL CHEM. MESSG. NO. 4A

Unit 1 Date 08-11-92 Time After 0930

pH:

Spec Cond:

Boron:

Chloride:

Floride:

Susp. Sol:

Dissolved Oxygen:

RADIOCHEMISTRY DATA

Gross Beta

Gross Gamma

Ar-41 Na-24

Kr-85m Rb-88

Kr-87 Co-58

Kr-88 Cs-134

Xe-133 <MDA Cs-137

Xe-133m <MDA Cs-138

Xe-135 <MDA

Xe-135m

1-131 <MDA

1-132 <MDA

1-133 <MDA

1-134

1-135

Page 99: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE NUMBER Chemistry - 5

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time After 0930

PLANT CONDITION:

TO: Chemistry technician sampling 1&2 AND/OR 3 TBS

FROM: Controller

MESSAGE: 1.) Activity less than detectable. 2.) No oil visible. 3.) Hydrazine <.005

ACTIONS EXPECTED: Notify OSC with results.

Page 100: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

MESSAGE NUMBER Chemistry - 6

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time AFTER 1230

PLANT CONDITION:

TO: Chemistry technician sampling CTP-3.

FROM: Controller

MESSAGE: 1.) Activity less than detectable. 2.) No oil visible. 3.) Hydrazine <.005 4.) Level over weir approx. 12 inches.

ACTIONS EXPECTED: Notify OSC with results.

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FIELD MONITORING DATA

Page 102: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

SECTOR A Time: j245

5000 mr/hr

/_ 3C mr/hr

TRAINING 9 m CENTER O/hr

021 ~KEOWE {mr

.4viSITOR AI NTER 7mr/hr

SECTOR B 34 Time: IZ47-13c'7

033 0020 7oo mr/hr

METEOROLOGICAL MICROWAVE TOWE ( O mr/hr

EA TURB. G mr/hr

031 mr/hr

030 025 SECTOR C

Time: 1241- 130 f

INTERIM RADWASTE FENCE 0m26 1q50 r/hr FACILITY K

RUCTURES

50,: mr/hr

03 4 mr/hr

mr/hr

SECTOR D Time: 1250- 10

/300 mr/hr

DF 330 mr/hr

S0W mr/hr

I MILE RAOIU SSE mr/hr m1h

1(

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gp 29! D

AKSS 00

00/

ONEE RRDD.W.S OWEG- PL R XT

N(Lal n

160 A 124

KING GRvE-VAF

- D-1 U 15 RID. F

K88 HORSES

Evil Cl. MILCH

Je2 -L HA7WLLRD

J-66

Senec -,rl cp Ej ER

'40-~' m4$h~p CLEM7~zi ' V Vh~IETES

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1 4 C-1~ 291 RD. ..

VIl D1.

14

SVAN

0 D

G-3 588 et99o 46 F A t RCv FOR

Evil) 03 ILC J -2 Yll,

CHAELV

I - ARI~D.

a e,6(la..

J-5 emon4

enecaM TER. eotIER

Mile -(Cmrh cm21

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N-2 29 RIX

ffiDEF

~ii~ OEE R D, OSS Ao V

- /~60 ~ /4 H_ IKING GROVE -J F-3

K-1AOv iD.P, r el

it 4KEO E

-D2RD- OAK ~ 8i S, K- 15 0 ORSESH

N RD.W.

6-3 G- '

Fri HILL CH

EVAN! DR.

LAWRENCE

A0 E0

588 *- ~ 46 RIERCLIFF R'3

130 tWOODBINE

1-3

LWp Cal- 110VE mrhr0

mD Hi h .NES[

zo - 1(7 mr/hr cpm 210 H-5AfTR

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ODYDAL c-i- 18 CR.

183 cp -OSSA Z NRas

D-1J

AN EN

160 124CLE

KIWOED-INF-3

mr/hr POI t1/3

mr/h ROL

a~~~~~ h iN p VRr

gT0 20 G-3 m41cp 1

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4

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METEOROLOGICAL DATA

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Sheet 1 of 1

METEOROLOGY DATA WORKSHKET

**************** THIS IS A DRILL ****************

OCONEE NUCLEAR STATION

DATE: August 11, 1992

TIME: 0730

ENVIRONMENTAL SYSTEMS

DESCRIPTION************ VALUE UNITS COMP ID

AVG MC WIND SPD 60M 12 MPH P0158

AVG MC WIND DIR 60M 345 DEG P0156

AVG MC WIND SPD RV SITE 5 MPH P0159

AVG MC WIND DIR RV SITE 280 DEG P0157

AVG MC DELTA TEMP -0.50 DEGC P0160

AVG MC AMB AIR TEMP 10M 75 DEGC P0162

AVG MC WIND SPD 10M 6 MPH A0080

AVG MC WIND DIRECTION 10M 345 DEG A0081

u :DEGC 023

A 110 20

6MM angINCH Al

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Sheet 1 of 1

METEOROLOGY DATA WORKSHEET

**************** THIS IS A DRILL ****************

OCONEE NUCLEAR STATION

DATE: August 11, 1992

TIME: 1400

ENVIRONMENTAL SYSTEMS

DESCRIPTION************ VALUE UNITS COMP ID

AVG MC WIND SPD 60M 12 MPH P0158

AVG MC WIND DIR 60M 345 DEG P0156

AVG MC WIND SPD RV SITE 5 MPH P0159

AVG MC WIND DIR RV SITE 280 DEG P0157

AVG MC DELTA TEMP -0.50 DEGC P0160

AVG MC AME AIR TEMP 10M 90 DEGC P0162

AVG MC WIND SPD 10M 12 MPH A0080

AVG MC WIND DIRECTION 10M 345 DEG A0081

DEGC 1023

U1020

appquggINCH Al

Unit Vent Flow 40,000CFM

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RADIATION MONITOR DATA

Page 113: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

FIGURE H-5

DUKE POWER COMPANY OCONEE NUCLEAR SITE

RADIATION INFORMATION ALARMS (RIA)

RIA# UNIT# TYPE RANGE FUNCTION LOCATION CLASS

1 1,3 IC .1 - 1E4mr/hr Control Room Control Room Area

PBM* 1,2,3 GM .1 - lE4mr/hr Main Bridge Reactor Area Building

PBM* 1,2,3 GM .1 - 1E4mr/hr Aux. Bridge Reactor Area Building

3 1,2,3 GM, IC .1 - lE7mr/hr Refuel Canal Transfer Canal Area

4 1,2,3 GM, IC .1 - lE7mr/hr RB Entrance Personnel Hatch Area

5 1,2,3 GM .1 - lE4mr/hr Incore Tank Outside Incore Area ______ _ Fuel_ _ TK Hatch

PBMW 1,3 GM .1 - lE4mr/hr Spent Fuel SF Bridge Area

6 1,3 GH, IC .1 - lE7mr/hr Spent Fuel SF Pool Area Area Area/Pool

7 1 IC .1 - lE7mr/hr Hot Machine East Hall Area Shop

8 1 IC .1 - lE7mr/hr Hot Lab/ Hot Chem. Lab Area Chemistry

10 1,3 GM .1 - lE4mr/hr Sample Primary Sample Area I Hood/Primary hood

11 1,3 GM .1 - lE4mr/hr Corridor Unit 1/2 Change Area 796'(3rd Room, Unit 3 Level) Change Room

12 1,3 GM .1 - 1E4mr/hr Chem Unit 1/2/3 Mix Area Addition Tank

13 1,3 GM .1 - 1E4mr/hr Haste Haste disposal Area Disposal Tk

Sink

15 1,3 GM, IC .1 - 1E7mr/hr HPI HPI Rooms Area

16 1,2,3 GM .1 - 1E3mr/hr "A" Main "A" Main Steam Area Steam Line Lines

17 1,2,3 GM .1 - lE3mr/hr "B" Main "B" Main Steam Area I _ Steam Line Lines

21 3 IC .1 - lE7mr/hr Interim Interim Area Radwaste Radwaste

Evaporator Evaporator Room

22 3 IC .1 - lE7mr/hr High 9 Low Interim Area Haste Tank Racwaste

Evaporator Room

23 3 IC .1 - lE7mr/hr Evaporator Interim Area Control Radwaste

Panel

31 1,3 Nal .1 - 1E6mr/hr LPSH TB-1-M32 Effl Discharge _

H-29 Revision 92June, 1992

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DUKE POWER COMPANY OCONEE NUCLEAR SITE

Figure 11-5 (Continued)

RIA# UNIT# TYPE RANGE FUNCTION LOCATION CLASS

32 1 P.Beta .1 - lE6mr/hr Aux. Bldg. AB-1 SF Resin Area Gas Tank

32 3 P.Beta .1 - lE7mr/hr Aux. Bldg. AB-2 Elevator Area Gas Lobby

33 Hal .1 - lE6mr/hr Normal LHD Radwaste Effl Facility

35 1,2,3 Mal .1 - lE6mr/hr LPSH Disch. TB-1-M32 Effl Aux Building

36 1,2,3 Hal .1 - 1E6mr/hr RC Letdown Behind Chem Sys. Add. Pumps

37 1,3 P.Beta .1 - 1E6mr/hr Normal GHO Pen Room near Effl elevator

38 1,2 GM .1 - 1E6mr/hr High GHD Pen Room near Effl elevator

39 1,3 P.Beta .1 - lE6mr/hr CR-Gas 6th Fl. behind Area Em. Air Booster

Pumps

40 1,2,3 P.Beta .1 - 1E7mr/hr Air ejector Purge Equip. Effl off gas room

41 1,3 P.Beta .1 - lE6mr/hr SF Bldg. Gas Purge Equip. Area room

42 1,3 Nal .1 - lE6mr/hr RCH return Behind backwash Sys

43 1,2,3 P.Beta .1 - 1E7mr/hr Unit vent Purge Equip. Effl particulates room

44 1,2.3 Hal .1 - 1E7mr/hr Unit vent Purge Equip. Effl iodine room

45 1,2,3 P.Beta .1 - 1E7mr/hr Unit vent Purge Equip. Effi I_ gas normal room

46 1,2,3 CdTe .1 - lE7mr/hr Unit vent Purge Equip. Effl gas high room

47 1,2,3 P.Beta .1 - lE7mr/hr RB Purge Equip. Effl particulate room

48 1,2,3 Nal .1 - lE7mr/hr RB iodine Purge Equip. Effl room

49 1,2,3 P.Beta .1 - lE7mr/hr RB gas Purge Equip. Effl normal room

49A 1,2,3 CdTe .1 - lE7mr/hr RB gas high Purge Equip. Effl room

50 1,2,3 Nal .1 - lE6mr/hr CCH CCH pump Sys

52 1 Hal .1 - 1E6mr/hr RCH return Behind backwash Sys from Interim pumps

Bldg. _DS

53 IB Nal .1 - lE6mr/hr Interim Interim Bldg. Effl Bldg. Gas

54 1,3 al .1 - lE6mr/hr TB sump TB sump Effl

56 1,2,3 IC .1 - 1E7R/hr Vent Stack Vent Stack Effl (midway) , Imidway I

H-30 Revision 92June, 1992

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DUKE POWER COMPANY OCONEE NUCLEAR SITE

Figure H-5 (Continued)

RIA# UNIT# TYPE RANGE FUNCTION LOCATION CLASS

57 1,2,3 IC 1 - 1E8R/hr Containment Reactor Bldg. Area

High range monitor

58 1,2,3 IC .1 - 1E8R/hr Containment Reactor Bldg. Area High range

monitor

IC = Ion Chamber

PBM = Portable Bridge Monitor * Portable bridge monitors do not have assigned RIA numbers

and are local readout only.

IB = Interim Building

H-31 Revision 92June, 1992

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Sheet 1 of 1

ENCLOSURE 20

RIA DATA WORKSHEET

I************** THIS IS A DRILL ******************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 03

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UNIT-3

EL 758 RM 15 AUX CORR EL 758 MRHR 0.8 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA

RM 32 AUX BLDG AIR CPM TUU_ NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA

RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA

RM 36 RC LETDN CPM _QQS__

EL 796 RM 04 RB ENTRANCE MRHR 0.2

RM 07 MACHINE SHOP MRHR 3 NO RIA NO RIA RM 08 HOT LAB MRHR 0.2 NO RIA NO RIRM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIA

RM 10 SMPL AREA MRHR 0.5 N

RM 11 AUX CORR EL 796 MRHR 0.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a

RM 37 GWD EFF LR CPM 210 NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NC RI

EL 838 RM 02 MAIN BRIDGE MRHF. n/a

RM 03 AUX BRIDGE MRHR na

RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA

RM 39 CONTRL RM VENT CPM 40 NC RIA

RM 40 CSAE EXH CPM 1400

RM 41 SPENT FUEL BLDG AI CPM 130 NO RIA

PM 43 UNIT VENT PARTICUL CPM 500

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30

P 46 UNIT VENT GAS HR CPM 0 .

RM 47 RB PARTICULATE CPM 11300

RM 48 RB IODINE CPM 800

RM 49 RB GAS CPM 2300

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM lin NO RIA

RM 35 LPSW AUX BLDG DISC CPM 140

RM 42 RECIRC CLING WTR CPM 1140 NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RIA RM 54 T.B. SUMP CPM ( 100 NO RIA

T.B. 5 RM 16 MS HDR A MRHR 020_ RM 17 MS HDR B MRHR 0,04_

RM 33 LIQ WASTE EFF LR CPM 120 NO RIA NO RIA RM 34 LID WASTE EFF HR CPM 20 NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0-7 RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1

ENCLOSURE 20

RIA DATA WORKSHEET

<+************* THIS IS A DRILL *******************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 0940

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UNIT-3

EL 758 RM 15 AUX CORR EL 758 MRHR 0.8 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 600 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA

RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 0.2

RM 07 MACHINE SHOP MRHR 3 NO RIA NO RIA RM O8 HOT LAB MRHR 0.2 NO RIA NO RI,RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIA RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR U.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a RM 37 GWD EFF LR CPM _210_ NO RIA RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO RII. _

EL 838 RM 02 MAIN BRIDGE MRHF. n/a

RM 03 AUX BRIDGE MRHR n_a

RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA

RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1400

RM 41 SPENT FUEL BLDG AI CPM NO RIA RM 43 UNIT VENT PARTICUL CPM 500.

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30 _

P11 46 UNIT VENT GAS HR CPM 0

R11 47 RB PARTICULATE CPM 22200 .

RM 48 RB IODINE CPM 820

RM 49 RB GAS CPM 6400

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140

RM 42 RECIRC CLING WTR CPM 140 NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RIA RM 54 T.B. SUMP CPM ( 10 NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02 RM 17 MS HDR B MRHR 0.04 RM 33 LID WASTE EFF LR CPM 120 NO RIA NO RIA RM 34 LIO WASTE EFF HR CPM 20 NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.7 RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet I of 1

ENCLOSURE 20

RIA DATA WORKSHEET

<*+*++********** THIS IS A DRILL *******************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 0950

ELEV** DESCRIPTION************ UNITS UNIT-1 UNIT-2 UNIT-3

EL 758 RM 15 AUX CORR EL 758 MRHR 0.8 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 600 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA

RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 0.2

RM 07 MACHINE SHOP MRHR 3 NO RIA NO RIA RM 08 HOT LAB MRHR 0.2 NO RIA NO RIf RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIA RM 10 SMPL AREA MRHR 9 N RM 11 AUX CORR EL 796 MRHR n I NO RIA _

EL 209 RM 05 INCORE HANDLING AR MRHR n/a

RM 37 GWD EFF LR CPM 210 NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO R I

EL 838 RM 02 MAIN BRIDGE MRHF n/a

RM 03 AUX BRIDGE MRHR n/a

RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1400

RM 41 SPENT FUEL BLDG Al CPM 130 NO RIA PM 43 UNIT VENT PARTICUL CPM 500

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LF CPM 30

P 46 UNIT VENT GAS HF: CPM 0

RM 47 RB PARTICULATE CPM 18000

RM 48 RB IODINE CPM 820

RM 49 RB GAS CPM 8300

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140

RM 42 RECIRC CLING WTR CPM 140 NO RIA RM 52 INTERIM LWD EFF MRHR 120. NO RIA NO PIA RM 54 T.B. SUMP CPM ( 1nnot NO RIA

T.B. 5 RM 16 MS HDR A MRHR n-07 RM 17 MS HDR B MRHR 0,04

RM 33 LIQ WASTE EFF LR CPM 120 NO RIA NO RIA RM 34 LID WASTE EFF HR CPM 20 NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.7

RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1

ENCLOSURE 20

RIA DATA WORKSHEET

<+************* THIS IS A DRILL *****************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 1000

ELEV** DESCRIPTION************ UNITS UNIT-1 UNIT-2 UNIT-S

EL 758 RM 15 AUX CORR EL 758 MRHR n 2 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA

RM 32 AUX BLDG AIR CPM 600 NO RIA.

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA.

RM 36 RC LETDN CPM 00S

EL 796 Rtl 04 RB ENTRANCE MRHR

RM 07 MACHINE SHOP MRHR 3 NO RIA NO RIA RM 06 HOT LAB MRHR 0.2 NO RIA NO RIRM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIA RM 10 SMPL AREA MRHR 0.5 N

RM 11 AUX CORR EL 796 MRHR 0.1 NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR n/a

RM 37 GWD EFF LR CPM __1U__ NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO RIP^-.

EL 838 RM 02 MAIN BRIDGE rRHF n/a

RM 03 AUX BRIDGE MRHR n/a RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA

RM 39 CONTRL RM VENT CPM 40 NC RIA

RM 40 CSAE EXH CPM 1900

RM 41 SPENT FUEL BLDG AI CPM 1 NO RIA

PM 43 UNIT VENT PARTICUL CPM 50U

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30

RM 46 UNIT VENT GAS HPR CPM 0

RM 47 RB PARTICULATE CPM 27720

RM 48 RB IODINE CPM _?__

RM 49 RB GAS CPM 10540

RM 51 PENT RM GAS CPM

T.S. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA

RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 140 NO RIA

RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RIA RM 54 T.B. SUMP CPM ( IUUU) NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02

RM 17 MS HDR B MRHR 0.0N RM 33 LID WASTE EFF LR CPM 1 NO RIA NO RIA RM 34 LID WASTE EFF HR CPM NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.7 RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1

ENCLOSURE 20

RIA DATA WORKSHEET

www-*+********** THIS IS A DRILL *******************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 1010

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UNIT

EL 758 RM 15 AUX CORR EL 758 MRHR 0-9 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 600 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 01 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM / 00S

EL 796 RM 04 RB ENTRANCE MRHR 5

RM 07 MACHINE SHOP MRHR 3 NO RIA NO RI RM O8 HOT LAB MRHR 0.2 NO RIA NO RI RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RI RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR _-_ NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHP n/a

RM 37 GWD EFF LR CPM 21U NO RIA

RM 38 GWV EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF n/a

RM 03 AUX BRIDGE MRHR na

RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA RM 39 CONTRL RM VENT CPM 4n NC RIA RM 40 CSAE EXH CPM 1900

RM 41 SPENT FUEL BLDG AI CPM 130 NO RIA F:M 43 UNIT VENT PARTICUL CPM Soo

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30

P 46 UNIT VENT GAS HP CPM 0

RM 47 RB PARTICULATE CPM_ 31400

RM 48 RB IODINE CPM 825

RM 49 RB GAS CPM 12100

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140

RM 42 RECIRC CLING WTR CPM 14U NO RIA

RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO PIA RM 54 T.B. SUMP CPM ( IUUU) NO RIA ( )

T.B. 5 RM 16 MS HDR A MRHR 0.02

RM 17 MS HDR B MRHR 0_. 4

RM 33 LIQ WASTE EFF LR CPM NO RIA NO RIA RM 34 LID WASTE EFF HR CPM _ U NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR Q 7

RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1 ENCLOSURE 20

RIA DATA WORKSHEET

* ************* THIS IS A DRILL ******************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 1020

ELEV** DESCRIFTION************ UNITS UNIT-1 UNIT-2 UNIT-:

EL 758 RM 15 AUX CORR EL 758 MRHR 0 8 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 600 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0,1 NO RIA

RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 7 RM 07 MACHINE SHOP MRHR 3 NO RIA NO RI RM 08 HOT LAB MRHR 0.2 NO RIA NO RIA RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIRM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR W NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR n /a

RM 37 GWD EFF LR CPM __1U_ NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA _

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF n/a

RM 03 AUX BRIDGE MRHR n/a RM 06 SPENT FUEL BRIDGE MRHP NO RIA

RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900

RM 41 SPENT FUEL BLDG AI CPM 130 NO RIA F:M 43 UNIT VENT PARTICUL CPM 500

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30

P 46 UNIT VENT GAS HR CPM 0

RM 47 RB PARTICULATE CPM_ _

RM 48 RB IODINE CPM

RM 49 RB GAS CPM

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO PIA RM 54 T.B. SUMP CPM 4 00 ) NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02

RM 17 MS HDR B MRHR 0.0_

RM 33 LIQ WASTE EFF LR CPM NO RIA NO RIA RM 34 LIO WASTE EFF HR CPM _ U NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR n_- 7 RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1 ENCLOSURE 20

RIA DATA WORKSHEET

*************** THIS IS A DRILL *****************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 1030

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UNIT

EL 758 RM 15 AUX CORR EL 758 MRHR n . NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA

RM 32 AUX BLDG AIR CPM 600 NO RIA .

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TKI MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 9 RM 07 MACHINE SHOP MRHR 3 NO RIA NO RI RM 08 HOT LAB MRHR 0.2 NO RIA NO RI RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RI RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR _.___ NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHP n/a

RM 37 GWD EFF LR CPM _7170 NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NC R I

EL 838 RM 02 MAIN BRIDGE rRHF n/a

RM 03 AUX BRIDGE MRHR n/a RM 06 SPENT FUEL BRIDGE MRHP _____ NO RIA _

RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900 RM 41 SPENT FUEL BLDG Al CPM 1u NO RIA PM 43 UNIT VENT PARTICUL CPM 500

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CFM 30 P 46 UNIT VENT GAS HR CPM 0

RM 47 RB PARTICULATE CPM 38200

RM 48 RB IODINE CPM __

RM 49 RB GAS CPM 191UU_

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140

RM 42 RECIRC CLING .WTR CPM _ _140 NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RIA RM 54 T.B. SUMP CPM ( 1000_) NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02

RM 17 MS HDR B MRHR 0.0__ RM 33 LIQ WASTE EFF LR CPM U NO RIA NO RIA RM 34 LID WASTE EFF HR CPM zu NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.7

RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet 1 of 1 ENCLOSURE 20

RIA DATA WORKSHEET

4*************** THIS IS A DRILL ****************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: J1040 _

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UNIT

EL 758 RM 15 AUX CORR EL 758 MRHR n 8 NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 6n0 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 10 RM 07 MACHINE SHOP MRHR 3 NO RIA NO RIt RM OS HOT LAB MRHR 0.2 NO RIA NO RI; RM 09 LO LVL DRUMMING MRHR 1 NO RIA NO RIi RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR _.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a

RM 37 GWD EFF LR CPM __1U NO RIA

RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO R IA

EL 838 RM 02 MAIN BRIDGE MRHF n/a

RM 03 AUX BRIDGE MRHR n/ a_

RM 06 SPENT FUEL BRIDGE MRHP 2 NO RIA RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900

RM 41 SPENT FUEL BLDG AI CPM 130 NO RIA PM 43 UNIT VENT PARTICUL CPM 500

RM 44 UNIT VENT IODINE CPM 40

RM 45 UNIT VENT GAS LR CPM 30

PM 46 UNIT VENT GAS HP CPM 0

RM 47 RB PARTICULATE CPM 41700

RM 48 RB IODINE CPM 835

RM 49 RB GAS CPM 23000

RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RIA RM 54 T.B. SUMP CPM ( 10 ) NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02

RM 17 MS HDR B MRHR 0._4

RM 33 LIQ WASTE EFF LR CPM 12U NO RIA NO RIA RM 34 LIO WASTE EFF HR CPM _ U NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.70

RM 58 CONTAINMENT MON A R/HR 0.70

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No AC Power ENCLOSURE 20

RIA DATA WORKSHEET

************** THIS IS A DRILL *************** OCONEE NUCLEAR STATION DATE: 8/11/92

RADIATION MONITOR REPORT TIME: 1050

ELEV** DESCRIFTION************* UNITS UNIT-1 UNIT-2 UNI

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO I RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA FM 43 UNIT VENT PARTICUL CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM RM1 46 UNIT VENT GAS HP CPM RM 47 RB PARTICULATE CPM RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.B. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RIA RM 54 T.B. SUMP CPM NO RIA (

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RIA RM 34 LIO WASTE EFF HR CPM NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 0.7 RM 58 CONTAINMENT MON A R/HR 0.7

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Sheet I of

No AC Power ENCLOSURE 20

RIA DATA WORKSHEET

* ****.********** THIS IS A DRILL *************** OCONEE NUCLEAR STATION DATE: 8/11/92

RADIATION MONITOR REPORT TIME: _1100

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UN:

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA

RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NC RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR

RM 37 GWD EFF LR CPM NO RIA

RM 38 GWD EFF HR! CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NO RIA

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR

RM 06 SPENT FUEL BRIDGE MRHF NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM _

RM 41 SPENT FUEL BLDG Al CPM NO RIA M 43 UNIT VENT FARTICUL. CPM --

RM 44 UNIT VENT IODINE CPM --

RM 45 UNIT VENT GAS LR CPM --

RMi 46 UNIT VENT GAS HP CPM RM 47 RB PARTICULATE CPM__

RM 48 RB IODINE CPM RM 49 RB GAS CPM

RM 51 PENT RM GAS CPM --

T.B. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM --

RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM ( ) NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RI RM 34 LIO WASTE EFF HR CPM NO RIA NO RI

0.7 ____

R. B. RM 57 CONTAINMENT MON B R/HR -

RM 58 CONTAINMENT MON A R/HR U.

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Sheet 1 of

No AC Power ENCLOSURE 20

RIA DATA WORKSHEET *************** THIS IS A DRILL *

OCONEE NUCLEAR STATION DATE: 8/11/q RADIATION MONITOR REPORT TIME: 1110

ELEV** DESCRIFTION**.******** UNITS UNIT-1 UNIT-2 Ur

EL 758 RM 15 AUX CORR EL 752 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NC RM 08 HOT LAB MRHR NO RIA NC RM 09 LD LVL DRUMMING MRHR NO RIA NC RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RIA

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR . RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICUL CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM R1 46 UNIT VENT GAS HR' CPM RM 47 RB PARTICULATE CPM__ RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.S. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM (. NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RI RM 34 LID WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 0.7 RM 58 CONTAINMENT MON A R/HR 0.7

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No AC Power Sheet 1 of ENCLOSURE 20

RIA DATA WORKSHEET

* *********** THIS IS A DRILL ************* OCONEE NUCLEAR STATION DATE: 8/11/9:

RADIATION MONITOR REPORT TIME: 1120_

ELEV** DESCRIPTION+************ UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 7S3 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NO RI.

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP ND RIO" RM 39 CONTRL RM VENT CPM NC RIRM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICUL. CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM RM 46 UNIT VENT GAS HP CPM RM 47 RB PARTICULATE CPM RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LIQ WASTE EFF LR CPM NO RIA NO RI RM.34 LID WASTE EFF HR CPM NO RIA NO RIC

R. B. RM 57 CONTAINMENT MON B R/HR 1.1 RM 58 CONTAINMENT MON A R/HR 1.1

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RIA DATA WORKSHEET

************** THIS IS A DRILL ****************4*

OCONEE NUCLEAR STATION DATE: 8/11/9 RADIATION MONITOR REPORT TIME: _J130_

ELEV** DESCRIPTION********* * UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 759 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICL' CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM

R1 46 UNIT VENT GAS HF CPM RM 47 RB PARTICULATE CPM RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM ( NO RIA (

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RI RM 34 LID WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 1.7 RM 58 CONTAINMENT MON A R/HR 1-7

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No AC Power Sheet 1 of ENCLOSURE 20

RIA DATA WORKSHEET +************* THIS IS A DRILL *************..****

OCONEE NUCLEAR STATION DATE: 8/11/9RADIATION MONITOR REPORT TIME: 1140

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UN.

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 793 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NO RIA

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHF: NO RI A RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICUL. CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM RM 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM__ RM 48 RB IODINE CPM . RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM 40 RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM 40 RIA RM 52 INTERIM LWD EFF MRHR 1J0 RIA NO RIA RM 54 T.B. SUMP CPM (. 40 RIA (

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR. RM 33 LID WASTE EFF LR CPM O RIA NO RIA RM 34 LID WASTE EFF HR CPM 4O RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR 2 RM 58 CONTAINMENT MON A R/HR 2

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ENCLOSURE 20

RIA DATA WORKSHEET

******.****** THIS IS A DRILL +++++*********** OCONEE NUCLEAR STATION DATE: 8/11/9

RADIATION MONITOR REPORT TIME: 1150

ELEV** DESCRIFTION************ UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA . MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM No RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHF NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA FM 43 UNIT VENT PARTICUL CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LP CPM RM 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI, RM 54 T.B. SUMP CPM ( NO RIA (.

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RI, RM 34 LIO WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 30 RM 58 CONTAINMENT MON A R/HR 30

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No AC Power Sheet I of ENCLOSURE 20

RIA DATA WORKSHEET

e************** THIS IS A DRILL +++****************

OCONEE NUCLEAR STATION DATE: 8/11/92 RADIATION MONITOR REPORT TIME: 1200

ELEV** DESCRIFTION*+**++++**++ UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 763 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NO RI;

EL 836 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG Al CPM NO RIA FM 43 UNIT VENT PARTICUL. CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM P11 46 UNIT VENT GAS HF CPM RM 47 RB PARTICULATE CPM__ RM 48 RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO PIA RM 54 T.B. SUMP CPM NO RIA (

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RIA RM 34 LIO WASTE EFF HR CPM NO RIA NO RIA

R. B. RM 57 CONTAINMENT MON B R/HR RM 58 CONTAINMENT MON A R/HR 85

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ENCLOSURE 20

RIA DATA WORKSHEET ****.********** THIS IS A DRILL ******* ******

OCONEE NUCLEAR STATION DATE: 8/11/9: RADIATION MONITOR REPORT TIME: _1210,

ELEV** DESCRITION************* UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RMl 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM O8 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHP RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL e22 RM 01 CONTRL ROOM MRHR NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHFP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EYH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICUL CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM RM 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM__ RM 4a RB IODINE CPM RM 49 RB GAS CPM RM 51 PENT RM GAS CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI( RM 54 T.B. SUMP CPM NO RIA L_

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR 9 MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RIi RM 34 LID WASTE EFF HR CPM NO RIA NO RI4

R. B. RM 57 CONTAINMENT MON B R/HR 125 RM 58 CONTAINMENT MON A R/HR 125

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ENCLOSURE 20

RIA DATA WORKSHEET .*.*******.* THIS IS A DRILL **************e*.

OCONEE NUCLEAR STATION DATE: 8/11/s RADIATION MONITOR REPORT TIME: 122L.

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 Ur

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NC RM 08 HOT LAB MRHR NO RIA NC RM 09 LO LVL DRUMMING MRHR NO RIA N1 RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL E09 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI.

EL 636 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHF ND RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG Al CPM NO RIA P.M 43 UNIT VENT PARTICL;. CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPfM_ RiM 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM RM 48 RB IODINE CPM RM 49 RS GAS CPM

CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO FI RM 34 LID WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 175 RM 58 CONTAINMENT MON A R/HR 175

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No AC Power Sheet 1 of

ENCLOSURE 20

RIA DATA WORKSHEET ********~****** THIS IS A DRILL *

OCONEE NUCLEAR STATION DATE: 8/11/9: RADIATION MONITOR REPORT TIME: -1230_

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 UN

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NO RM 08 HOT LAB MRHR NO RIA NO RM 09 LO LVL DRUMMING MRHR NO RIA NO RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 39 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG Al CPM NO RIA PM 43 UNIT VENT PARTICL% CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM R1 46 UNIT VENT GAS HP CPM RM 47 RB PARTICULATE CPM_ RM 48 R9 IODINE CPM RM 49 RB GAS CPM

CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RIi RM 54 T.B. SUMP CPM NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO RI RM 34 LID WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 200 RM 58 CONTAINMENT MON A R/HR 700

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No AC Power Sheet 1 of ENCLOSURE 20

RIA DATA WORKSHEET *************** THIS IS A DRILL ************ne*.**

OCONEE NUCLEAR STATION DATE: 8/11/9 RADIATION MONITOR REPORT TIME: _124

ELEV** DESCRIPTION************ UNITS UNIT-1 UNIT-2 U

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NC RM OS HOT LAB MRHR NO RIA NC RM 09 LO LVL .DRUMMING MRHR NO RIA NC RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL E09 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 39 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI.

EL 636 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHF NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VENT PARTICUL. CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM R1 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM__ RM 48 RB IODINE CPM RM 49 RB GAS CPM

CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM _

RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LIQ WASTE EFF LR CPM NO RIA NO RI RM 34 LIO WASTE EFF HR CPM NO RIA No RI

242 R. B. RM 57 CONTAINMENT MON B R/HR

RM 58 CONTAINMENT MON A R/HR 242_

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No AC Power Sheet 1 of ENCLOSURE 20

RIA DATA WORKSHEET **************** THIS IS A DRILL **************4.

OCONEE NUCLEAR STATION DATE: 8/11/ RADIATION MONITOR REPORT TIME: ..J250

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 U

EL 758 RM 15 AUX CORR EL 758 MRHR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR NO RIA RM 32 AUX BLDG AIR CPM NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA RM 36 RC LETDN CPM

EL 796 RM 04 RB ENTRANCE MRHR RM 07 MACHINE SHOP MRHR NO RIA NC RM 09 HOT LAB MRHR NO RIA NC RM 09 LO LVL DRUMMING MRHR NO RIA N1 RM 10 SMPL AREA MRHR N RM 11 AUX CORR EL 796 MRHR NO RIA

EL 809 RM 05 INCORE HANDLING AR MRHR RM 37 GWD EFF LR CPM NO RIA RM 38 GWD EFF HR CPM NO RIA

EL 822 RM 01 CONTRL ROOM MRHR NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF RM 03 AUX BRIDGE MRHR RM 06 SPENT FUEL BRIDGE MRHP NO RIA RM 39 CONTRL RM VENT CPM NC RIA RM 40 CSAE EXH CPM RM 41 SPENT FUEL BLDG AI CPM NO RIA PM 43 UNIT VEN7 PARTICL CPM RM 44 UNIT VENT IODINE CPM RM 45 UNIT VENT GAS LR CPM R1 46 UNIT VENT GAS HR CPM RM 47 RB PARTICULATE CPM_ RM 46 RB IODINE CPM RM 49 RB GAS CPM

CPM

T.E. 1 RM 31 LPSW CLR DISCH CPM NO RIA RM 35 LPSW AUX BLDG DISC CPM RM 42 RECIRC CLING WTR CPM NO RIA RM 52 INTERIM LWD EFF MRHR NO RIA NO RI RM 54 T.B. SUMP CPM NO RIA

T.B. 5 RM 16 MS HDR A MRHR RM 17 MS HDR B MRHR RM 33 LID WASTE EFF LR CPM NO RIA NO R RM 34 LID WASTE EFF HR CPM NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 257 RM 58 CONTAINMENT MON A R/HR 257

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Power restored. Sheet I o ENCLOSURE 20

RIA DATA WORKSHEET ************* THIS IS A DRILL ***********.**

RADIATION MONITOR REPORT TIME: 1300

ELEV** DESCRITION**********++* UNITS UNIT-1 UNIT-2 U

EL 758 RM 15 AUX CORR EL 758 MRHR nR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM An NO RIA

EL 793 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 4.62E6 RM 07 MACHINE SHOP MRHR 3 NO RIA N RM S HOT LAB . MRHR 0.2 NO RIA N RM 09 LO LVL DRUMMING MRHR 1 NO RIA N RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR _.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a RM 37 GWD EFF LR CPM ___1__ NO RIA RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO R I.

EL 83e RM 02 MAIN BRIDGE MRHF n/a RM 03 AUX BRIDGE MRHR n/a RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RI A RM 39 CONTFL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900 RM 41 SPENT FUEL BLDG Al CPM 130 NO RIA PM 43 UNIT VENT PARTICUL CPM 500 RM 44 UNIT VENT IODINE CPM 40 RM 45 UNIT VENT GAS LR CPM 30 PH 44 UNIT VENT GAS HP CPM 0 RM 47 RB PARTICULATE CPM offscale high RM 48 RB IODINE CPM offscale high RM 49 RB GAS CPM offscale high

RM 49A RB GAS HIGH CPM Lj,904_

T.E. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO R RM 54 T.B. SUMP CPM ( IuuU NO RIA (O.

T.B. 5 RM 16 MS HDR A MRHR 0.02 RM 17 MS HDR B MRHR 0*___ RM 33 LID WASTE EFF LR CPM NO RIA NO R RM 34 LID WASTE EFF HR CPM _ U NO RIA NO R

R. B. RM 57 CONTAINMENT MON B R/HR 276 RM 58 CONTAINMENT MON A R/HR 276

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Sheet 1 o: ENCLOSURE 20

RIA DATA WORKSHEET *************** THIS IS A DRILL **************

OCONEE NUCLEAR STATION DATE: 8/11/ RADIATION MONITOR REPORT TIME: 1310

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 U

EL 758 RM 15 AUX CORR EL 756 MRHR n R NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 600 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 4.36E6 RM 07 MACHINE SHOP MRHR 3 NO RIA Ni RM O8 HOT LAB MRHR 0.2 NO RIA N RM 09 LO LVL DRUMMING MRHR 1 NO RIA N RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR U.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a RM 37 GWD EFF LR CPM 210 NO RIA RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NO R;.

EL 838 RM 02 MAIN BRIDGE MRHF n/a RM 03 AUX BRIDGE MRHR n/a RM 06 SPENT FUEL BRIDGE MRHP 2 NO RIRM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900 RM 41 SPENT FUEL BLDG Al CPM 130 NO RIA F:M 43 UNIT VENT PARTICL%. CPM 500 RM 44 UNIT VENT IODINE CPM 40 RM 45 UNIT VENT GAS LP CPM 30 RM 46 UNIT VENT GAS HR CPM 0 RM 47 RB PARTICULATE CPM OFFSCALE HIGH RM 48 RB IODINE CPM OFFSCALE HIGH RM 49 RB GAS CPM OFFSCALE HIGH

RM 49A RB GAS HIGH CPM 82,41

T.P. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 ND RIA NO R RM 54 T.B. SUMP CPM ( NO RIA (

T.B. 5 RM 16 MS HDR A MRHR 0.02 RM 17 MS HDR B MRHR 0.04 RM 33 LID WASTE EFF LR CPM U NO RIA NO R RM 34 LID WASTE EFF HR CPM LU NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 242 RM 58 CONTAINMENT MON A R/HR 242

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Sheet I c ENCLOSURE 20

RIA DATA WORKSHEET

S**.************ THIS IS A DRILL *********ss4s*. OCONEE NUCLEAR STATION DATE: 8/11.

RADIATION4 MONITOR REPORT TIME: 1320

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2

EL 758 RM 15 AUX CORR EL 758 MRHR nR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM A00 NO RIA

EL 783 RM 12 CHEM ADD AREA MRHR .1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 005

EL 796 RM 04 RB ENTRANCE MRHR 3.6E6 RM 07 MACHINE SHOP MRHR 3 NO RIA t RM 08 HOT LAB MRHR 0.2 NO RIA t. RM 09 LO LVL DRUMMING MRHR 1 NO RIA RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR 0.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a RM 37 GWD EFF LR CPM z1u NO RIA RM 38 GWD EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 Nc RIA

EL 838 RM 02 MAIN BRIDGE MRHF n/a RM 03 AUX BRIDGE - MRHR n/a

RM 06 SPENT FUEL BRIDGE MRHF: 2 NO RIA RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900 RM 41 SPENT FUEL BLDG Al CPM 130 NO RIA PM 43 UNIT VENT PARTICU CPM 500 RM 44 UNIT VENT IODINE CPM 40 RM 45 UNIT VENT GAS LR cPM 30 R1 46 UNIT VENT GAS HR CPM 0 RM 47 RB PARTICULATE CPM OFFSCAL HTGH RM 48 RB IODINE CPM OFFSCALE HIGH RM 49 RB GAS CPM OFFSCALE HIGH

RM 49A RB GAS HIGH CPM 68. 142

T.P. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO F RM 54 T.B. SUMP CPM ( lLU NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02 RM 17 MS HDR B MRHR 0.04 RM 33 LID WASTE EFF LR CPM i__U NO RIA NO F RM 34 LID WASTE EFF HR CPM ,-_U NO RIA NO F

R. B. RM 57 CONTAINMENT MON B R/HR 200 RM 58 CONTAINMENT MON A R/HR 200

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Sheet I c ENCLOSURE 20

RIA DATA WORKSHEET **************** THIS IS A DR ILL ++**************

OCONEE NUCLEAR STATION DATE: 8/11, RADIATION MONITOR REPORT TIME: 1330

ELEV** DESCRIPTION************* UNITS UNIT-1 UNIT-2 L

EL 758 RM 15 AUX CORR EL 758 MRHR nR NO RIA

EL 771 RM 13 WASTE CONTRL AREA MRHR 1.5 NO RIA RM 32 AUX BLDG AIR CPM 5fl0-- NO RIA

EL 793 RM 12 CHEM ADD AREA MRHR 0.1 NO RIA RM 19 LDY AND HOT SWR TK MRHR NO RIA NO RIA RM 36 RC LETDN CPM 00S

EL 796 RM 04 RB ENTRANCE MRHR 3.5E6 RM 07 MACHINE SHOP MRHR 3 NO RIA N RM OS HOT LAB MRHR 0.2 NO RIA N RM 09 LO LVL DRUMMING MRHR I NO RIA N RM 10 SMPL AREA MRHR 0.5 N RM 11 AUX CORR EL 796 MRHR U.1 NO RIA

EL 209 RM 05 INCORE HANDLING AR MRHR n/a RM 37 GWD EFF LR CPM LIU NO RIA RM 32 GWV EFF HR CPM 15 NO RIA

EL 822 RM 01 CONTRL ROOM MRHR 0.1 NC RI.

EL 838 RM 02 MAIN BRIDGE MRHF n/a RM 03 AUX BRIDGE MRHR nia RM 06 SPENT FUEL BRIDGE MRHP 2 NO RIA RM 39 CONTRL RM VENT CPM 40 NC RIA RM 40 CSAE EXH CPM 1900 RM 41 SPENT FUEL BLDG AI CPM 130 NO RIA RM 43 UNIT VENT PARTICL. CPM 500 RM 44 UNIT VENT IODINE CPM 40 RM 45 UNIT VENT GAS LR CPM 30 RM 46 UNIT VENT GAS HR CPM 0 RM 47 RB PARTICULATE CPM OFFSCALE HIGH RM 48 RB IODINE CPM OFFSCALE HIGH RM 49 RB GAS CPM OFFSCAT.F HTH RM 49A RB GAS HIGH CPM 65-944

T.E. 1 RM 31 LPSW CLR DISCH CPM 110 NO RIA RM 35 LPSW AUX BLDG DISC CPM 140 RM 42 RECIRC CLING WTR CPM 14U NO RIA RM 52 INTERIM LWD EFF MRHR 120 NO RIA NO RI RM 54 T.B. SUMP CPM luuu ) NO RIA

T.B. 5 RM 16 MS HDR A MRHR 0.02 RM 17 MS HDR B MRHR 004 RM 33 LIQ WASTE EFF LR CPM izU NO RIA NO RI RM 34 LID WASTE EFF HR CPM 2U NO RIA NO RI

R. B. RM 57 CONTAINMENT MON B R/HR 19____ RM 58 CONTAINMENT MON A R/HR 194_

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INGESTION PATHWAY DATA

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Day 1 - Day of the release.

Day 1.5 - 12 hr after release

Day 2 - Day after release

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SURFACE ACTIVITY (pCi/m 2)

Day I 7Anie 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 9.89E401 1.86E+02 1.42E+02 2.12E+01 7.70E+00 1.04E401

B 9.89E+(X) 1.86E+01 1.42E+01 2.12E+00 7.70E-01 1.04E+00

C 9.89E-01 1.86E+(X) 1.42E+0() 2.12E-01 7.70E-02 1.04E-01

D 4.94E-01 9.30E-01 7.08E-01 1.06E-01 3.85E-02 5.19E-02

E 9.89E-02 1.86E-01 1.42E-01 2.12E-02 7.70E-03 1.04E-02

F 4.94E-02 . 9.30E-02 7.08E-02 1.06E-02 3.85E-03 5.19E-03

G 9.89E-03 1.86E-02 1.42E-02 2.12E-03 7.70E-04 1.04E-03

Day 1.5 Zone 1 131 1133 1 135 Cs 134 CS 136 CS 137

A 924E+01 1.22E102 4.01E+01 207E+01 7.32E+00 1.01E+01

B 9.24E+001 1.22E401 4.01E+00 2.07E.() 7.322-01 1.01E+00

C 9.24E-01 1.22E+0() 4.01E-01 2.07E-01 7.32E-02 1.01E-01

D 4.62E-01 6.12E-01 2.00E01 1.03E-01 3.66E-02 5.06E-02

E 9.24E-02 1.22E-01 4.01 E-02 2.07E-02 7.32E-03 1.01E-02

F 4.62E-02 6.12E-02 2.00E02 1.03E-02 3.66E-03 5.06E-03

G 9.24E-03 1.22E-02 4.01F-03 2.07E-03 7.32E-04 1.01E-03

Day 2 ZIe I 131 I 133 I 135 (s 134 CS 136 CS 137

A 8.61Etol 8.05E+01 1.13EMol 2.02E01 6.96E400 9.88E+00

B 8.64E+X) 8.05E+(X) 1.13E f0W 2.02E+(&) 6.96E-01 9.88E-01

C 8.64E-01 8.05E-01 1.13E-01 2.02E-01 6.96E-02 9.88E-02

D 4.32E-01 4.02E-01 5.67E-02 1.01E-01 3.48E-02 4.94E-02

E 8.64E-02 8.05E-02 1.13E-02 2.02E-02 6.96E-03 9.88E-03

F 4.32E-02 4.02E-02 5.67E-03 1.012-02 3.48E-03 4.94E-03

8.64 13 9.05F (3 1.1 3E 03 2.02E1 03 6.96E-04 9.88E 04

Page I of 4

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SURFACE ACTIVITY (pCi/m2)

Day 3 Zone I 131 1 133 1135 Cs 134 CS 136 CS 137

A 7.54E+01 3.48E+01 9.08E-01 1.92E+01 6.30E+00 9.40E+00

B 7.54E+00 3.48E+00 9.08E-02 1.92E+00 6.30E-01 9.40E-01

C 7.54E-01 3.48E-01 9.08E-03 1.92E-01 6.30E-02 9.40E-02

D 3.77E-01 1.74E-01 4.54E-03 9.60E-02 3.15E-02 4.70E-02

E 7.54E-02 3.48E-02 9.08E-04 1.92E-02 6.30E-03 9.40E-03

F 3.77E-02 1.74E-02 4.54E-04 9.60E-03 3.15E-03 4.70E-03

G 7.54E-03 3.48E-03 9.08E-05 1.92E-03 6.30E-04 9.40E-04

Day 4 Zonc 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 6.58E+01 1.51E+01 7.27E-02 1.82E+01 5.70E+00 8.94E+00

B 6.58E+00 1.51E+00 7.27E-03 1.82E+00 5.70E-01 8.94E-01

C 6.58E-01 1.51E-01 7.27E-0 1.82E-01 5.70E-02 8.94E-02

D 3.29E-01 7.54E-02 3.63E-(4 9.12E02 2.85E-02 4.47E-02

E 6.58E-02 1.51E-02 7.27E-05 1.82E02 5.70E-03 8.94E-03

F 3.29E-02 7.54E-03 3.63E-05 9.12E-03 2.85E-03 4.47E-03

( 6.58E-03 1.51E-03 7.27E-06 1.82E-03 5.70E-4 8.94E-04

Day 5 7,nn 1I131 1 133 I 135 Cs 134 CS 136 CS 137

A 5.75Ti 0 6.53 E10 5.82E-03 1.74E 01 5.16E+00 8.51E+00

B 5.75E+00 6.53E-01 5.82E-04 1.74E+00 5.16E-01 8.51E-01

C 5.75E 01 6.53E-02 5.82E-05 1.74E-01 5.16E-02 8.51E-02

D 2.87E-01 3.27E-02 2.91E-05 8.68E-02 2.58E-02 4.26E-02

E 5.75E-02 6.53E-03 5.82E-06 1.74E-02 5.16E-03 8.51E-03

F 2.87E-02 3.27E-03 2.91E-06 8.68E-03 2.58E-03 4.26E-03

( 5.751 03 6.53E1-0 5.82E-07 1.74EF 03 5.16E-A 8.51E-(A

Page 2 of 4

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SURFACE ACTIVITY (pCi/m 2)

Day 6 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 5.02E+01 2.83E+00 4.66E-04 1.65E+01 4.67E+00 8.10E+00

B 5.02E+00 2.83E-01 4.66E-05 1.65E+00 4.67E-01 8.10E-01

C 5.02E-01 2.83E-02 4.66E-06 1.65E-01 4.67E-02 8.10E-02

D 2.51E-01 1.41E-02 2.33E-06 8.25E-02 2.33E-02 4.05E-02

E 5.02E-02 2.83E-03 4.66E-07 1.65E-02 4.67E-03 8.1OE-03

F 2.51E-02 1.41E-03 2.33E-07 8.25E-03 2.33E-03 4.05E-03

G 5.02E-03 2.83E-04 4.66E-08 1.65E-03 4.67E-04 8.10E-04

Day 7 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 4.38Et01 1.22E+0() 3.73E-05 1.57E+01 4.22E+00 7.71E+00

B 4.38E+(X) 1.22E-01 3.73E-06 1.57E+(X) 4.22E-01 7.71E-01

C 4.38E-01 1.22E-02 3.73E-07 1.57E-01 4.22E-02 7.71E-02

D 2.19E-01 6.12E-03 1.86E-07 7.84E-02 2.11E-02 3.85E-02

E 4.38E-02 1.22E-03 3.73E-08 1.57E-02 4.22E-03 7.71E-03

F 2.19E202 6.12E-04 1.86E-08 7.84E-03 2.11E-03 3.85E-03

G 4.38E-03 1.22E-04 3.73E-09 1.57E-03 4.22E-04 7.71E-04

Day 8 Zone I 131 I 133 1 135 Cs 134 CS 136 CS 137

A 3.83E*01 5.30E 01 2.99E 06 1.19E+01 3.82E+0) 7.34E+00

B 3.83E4 M) 5.30E-02 2.99E07 .49E+01W 3.82E-01 7.34E-01

C 3 83E-01 5.30E-03 2.99E-08 1.49E-01 3.82E-02 7.34E-02

D 1.91E 01 2.65E03 1.49E-08 7.46E-02 1.91E-02 3.67E-02

E 3.83E-02 5.30E-1 2.99E-09 1.49E-02 3.82E-03 7.34E-03

F 1.91E-02 2.65E-04 1.49E-09 7.46E-03 1.91E-03 3.67E-03

G 3.83E-03 5.30E-05 2.99E-10 1.49E-03 3.82E-04 7.34E-04

Pave 3 of 4

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SURFACE ACTIVITY (pCi/m2)

Day 9 Zone 1 131 1133 1135 Cs 134 CS 136 CS 137

A 3.34E+01 2.29E-01 2.39E-07 1.42E+01 3.46E+00 6.98E+00

B 3.34E+0() 2.29E-02 2.39E-08 1.42E+00 3.46E-01 6.98E-01

C 3.34E-01 2.29E-03 2.39E-09 1.42E-01 3.46E-02 6.98E-02

D 1.67E-01 1.15E-03 1.19E-09 7.09E-02 1.73E-02 3.49E-02

E 3.34E-02 2.29E-04 2.39E-10 1.42E-02 3.46E-03 6.98E-03

F 1.67E-02 1.15E-04 1.19E-10 7.09E-03 1.73E-03 3.49E-03

G 3.34E-03 2.29E-05 2.39E-Il 1.42E-03 3.46E-04 6.98E-04

Day 10 Zoc I 131 I 133 1135 Cs 134 CS 136 CS 137

A 2.92E+01 9.93E-02 1.91E-08 1.35E01 3.13E+00 6.64E+00

B 2.92E+X0) 9.93E-03 1.91E-09 1.35E+) 3.13E-01 6.64E-01

C 2.92E-01 9.93E-04 1.91E-10 1.35E-01 3.13E-02 6.64E-02

D 1.46E-01 4.97E-04 9.57E- I 6.74E-02 1.56E-02 3.32E-02

E 2.92E-02 9.93E-05 1.91E- I 1.35E-02 3.13E-03 6.64E-03

F 1.46E-02 4.97E-05 9.57E- 12 6.74E-03 1.56E-03 3.32E-03

G 2.92E-03 9.93E-06 1.91E-12 1.35E-03 3.13E-04 6.64E-04

Day I1I Zone I I31 1133 1 135 Cs 134 CS 136 CS 137

A 2.551001 4.301 02. 1.5(2i01 .L2810I 2.83E i00 6.32, 100

B 2.55E 100 4.30E-03 1.53- 10 1.28Ef00 2.83E-01 6.32E-01

C 2.55E-01 4.30E-04 1.53E- I 1.28E-01 2.83E-02 6.32E-02

D 1.27E-01 2.15E-04 7.66E- 2 6.41E-02 1.41E-02 3.16E-02

E 2.55E-02 4.30E-05 1.53E-12 1.28E-02 2.83E-03 6.32E-03

F 1.27E-02 2.15E-05 7.66E 13 6.41E-03 1.41E-03 3.16E-03

G 2.55F 03 4.30E-06 1.53E 13 1.28E 03 2.R3E-04 6.32E-04

Pape 4 of 4

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SOIL ACTIVITY (pCi/kg)

Day I Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 4.121E-01 7.75E-01 5.90E-01 8.85E-02 3.21E-02 4.32E-02

R 4.12E-02 7.75E 02 5.901E-02 8.85E-03 3.21E-03 4.32E-03

C 4.12E.03 7.75E-03 5.90E-03 8.85E-04 3.21 E-04 4.32E-04

D 2.06E-03 3.87E-03 2.95E-03 4.42E-04 1.60E-04 2.16E-04

E 4.12E-)4 7.75E-04 5.90E-04 8.85E-05 3.21E-05 4.32E-05

F 2.06E-04 3.87E-04 2.95E-04 4.42E-05 1.60E-05 2.16E-05

G 4.12E-05 7.75E-05 5.90E-05 8.R5E-06 3.21E-06 4.32E-06

Day 1.5 zone 1131 1 133 1 135 Cs 134 CS 136 CS 137

A 3.85E-01 5.10E-01 1.67E-01 8.62E-02 3.05E-02 4.22E-02

B 3.85E-02 5.10E-02 1.67E-02 8.62E-03 3.05E-03 4.2213-03

C 3.85E-03 5.10E-03 1.67E-03 8.62E-4 3.05E-04 4.22E-04

D 1.93E-03 2.55E-03 8.35E-04 4.311E-04 1.53E-04 2.11E-04

E 3.85E-04 5.10E)-04 1.67E-04 8.62E-05 3.05E-05 4.22E-05

F 1.93E-04 2.55E-04 . 8.35E-05 4.311E-05 1.53E-05 2.11E-05

(1 3.85E-05 5.10E-05 1.67E-05 .621-06 3.05E-06 4.22E-06

Day 2 zonc I 11 I 131 I 135 Cs 134 CS 136 CS 137

A 3.60E-01 3.35E-01 4.73E-02 8.411E-02 2.90E-02 4.12E-02

B 3.60E-02 3.35E-02 4.73E-03 8.41 E-03 2.90E-03 4.12E-03

C 3.60E-03 3.35E-03 4.73E 04 8.41E-04 2.90E-04 4.1213-04

D 1.80E-03 1.68E-03 2.3613-04 4-21E-04 1.45E-04 2.06E-04

E 3.60E-04 3.35E-04 4.73E-05 8.41 E-05 2.90E-05 4.12E-05

F 1.80E-04 1.68E-04 2.36E-05 4.211E-05 1.45E-05 2.06E-05

G 3.601:-05 3.35F- 05 4.731-06 8.4 11E-06 2.90E-06 4.12E-06

Page I of 4

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SOIL ACTIVITY (pCi/kg)

Day 3 Zone 1 131 I 133 1 135 Cs 134 CS 136 CS 137

A 3.14E 01 1.45E-01 3.78E-03 8.00E-02 2.62E-02 3.92E-02

B 3.14E-02 1.45E-02 3.78E-04 8.0E-03 2.62E-03 3.92E-03

C 3.14E-03 1.45E-03 3.78E-05 8.00E-04 2.62E-04 3.92E-04

D 1.57E-03 7.26E-04 1.89E-05 4.0E-04 1.31E-04 1.96E-04

E 3.14E-04 1.45E-04 3.78E-06 8.0E-05 2.62E-05 3.92E-05

F 1.57E-04 7.26E-05 1.89E-06 4.OOE-05 1.31E-05 1.96E-05

G 3.14E-05 1.45E-05 3.78E-07 8.00E-06 2.62E-06 3.92E-06

Day 4 Zone 1 131 1 133 I 135 Cs 134 CS 136 CS 137

A 2.74E-01 6.29E-02 3.03E-04 7.60E-02 2.37E-02 3.73E-02

B 2.74E-02 6.29E-03 3.03E-05 7.60E-03 2.37E-03. 3.73E-03

C 2.74E-03 6.29E-04 3.03E-06 7.60E-04 2.37E-04 3.73E-04

D 1.37E-03 3.14E-04 1.51E-06 3.80E-)4 1.19E-04 1.86E-04

E 2.74E04 6.29E 05 3.03E07 7.60E-05 2.37E-05 3.73E-05

F 1.37E-4 3.14E-05 1.51E-07 3.80E-05 1.19E-05 1.86E-05

G, 2.74E-05 6.29E-06 3.03E-08 7.60E-06 2.37E-06 3.73E-06

Day 5 Zone 1 131 1 133 I 135 Cs 134 Cs 136 CS 137

A 2.40E 01 2.72F 02 2.421: 05 1231 02 2.15E 02 3.55E-02

B 2.40E-02 2.72E-03 2.42E-06 7.23E 03 2.15E-03 3.55E-03

C 2.40E-03 2.72E-)4 2.42E 07 7.23E-04 2.15E-04 3.55E-04

D 1.20E-03 1.36E-04 1.212E-07 3.61E-04 1.07E-04 1.77E-04

E 2.40E-04 2.72E-05 2.42E-08 7.23E-05 2.15E-05 3.55E-05

F 1.20E-04 1.36E 05 1.21E-08 3.61E-05 1.07E-05 1.77E-05

G 2.40E-05 2.72E-06 242E-09 723-06 2.15E-06 3.55E-06

Pape 2 of 4

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SOIL ACTIVITY (pCi/kg)

Day 6 Zoic I 131 I 133 1135 Cs 134 CS 136 CS 137

A 2.09E-01 1.18E-02 1.94E-06 6.87E-02 1.94E-02 3.38E-02

B 2.09E-02 1.18E-03 1.94E-07 6.87E-03 1.94E-03 3.38E-03

C 2.09E-03 1.18E-04 1.94E-08 6.87E-04 1.94E-04 3.38E-04

D 1.05E-03 5.89E-05 9.70E-09 3.44E-04 .9.72E-05 1.69E-04

E 2.09E-4 1.18E-05 1.94E-09 6.87E-05 1.94E-05 3.38E-05

F 1.05E-04 5.89E-06 9.70E-10 3.44E-05 9.72E-06 1.69E-05

() 2.09E-05 1.18E-06 1.94E-10 6.87E-06 1.94E-06 3.38E-06

Day 7 Zonle 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.83E-01 5.10E-03 1.55E-07 6.54E-02 1.76E-02 3.21E-02

B 1.83E-02 5. 10E-04 1.55E-08 6.54E-03 1.76E-03 3.21E-03

C 1.831-03 5.10E 05 1.55E-09 6,54E04 1.76E-04 3.21E-04

D 9.13E04 2.55E 05 7.77E-1) 3.27E 04 8.79E 05 1.61E04

E 1.83E-04 5.10E06 1.55E-10 6.54E-05 1.76E-05 3.21E-05

F 9.13E-05 2.55E-06 7.77E-Il 3.27E-05 8.79E-06 1.61E-05

G, 1.83E-05 5.10 E-07 1.55E-1I 6.54E-06 1.76E-06 3.21E-06

Day 8 hie I 131 1 133 I 135 ( 134 CS 136 CS 137

A 1.59E 01 2.21E 03 1.24E-08 6,21 E-02 1.59E-)2 3.06E-02

B 1.59E-02 2.21E-04 1.24E-09 6.21E-03 1.59E-03 3.06E-03

C 1.59E-03 2.2 1E-05 1.24E-10 6.21E-)4 1.59E-04 3.06E-04

D 7.97E-04 1.10E-05 6.22E-11 3.11E-04 7.96E-05 1.53E-04

E 1.59E-04 2.21E-06 1.24E-11 6.21E-05 1.59E-05 3.06E-05

I 7.97F 05 1.10E 06 6.22E 12 3.11 E 05 7.96E 06 1.53E-05

I 591.,1(5 2.211307 12,11: 12 6 21 F06 1.59E-06 3.06F-06

Page 3 of 4

0 0

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SOIL ACTIVITY (pCi/kg)

Day 9 Zone 1 131 1 133 1135 Cs 134 CS 136 CS 137

A 1.39E-01 9.56E-04 9.96E-10 5.91E-02 1.44E-02 2.91E-02

B 1.39E-02 9.56E-05 9.96E-1 I 5.91E-03 1.44E-03 2.91E-03

C 1.39E-03 9.56E-06 9.96E-12 5.91E-04 1.44E-04 2.91E-04

D 6.96E-04 4.78E-06 4.98E-12 2.95E-04 7.20E-05 1.45E-04

E 1.39E-04 9.56E-07 9.96E-13 5.91E-05 1.44E-05 2.91E-05

F 6.96E-05 4.78E-07 4.98E-13 2.95E-05 7.20E-06 1.45E-05

CG 1.39E-05 9.56E-08 9.96E-14 5.91E-06 1.44E-06 2.91E-06

Day 10 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.22E-01 4.14E-04 7.97E-1 1 5.62E-02 1.30E-02 2.77E-02

B 1.22E-02 4.14E-05 7.97E-12 5.62E-03 1.30E-03 2.77E-03

C 1.22E-03 4.14E-06 7.97E-13 5.62E-04 1.30E-04 2.77E-04

D 6.08E-04 2.07E-06 3.99E-13 2.81E-04 6.51E-05 1.38E-04

E 1.22E-04 4.14E 07 7.97E-14 5.62E-05 1.30E-05 2.77E-05

F 6.08E-05 2.07E-07 3.99E-14 2.812E-05 6.51E-06 1.38E-05

G 1.22E-05 4.14E-08 7.97E-15 5,62E-06 1.30E-06 2.77E-06

Day II Zone I 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.06E-01 1.79E-04 6.38- 12 5,34E-02 1.18E-02 2.63E-02

H 1.06E 02 1.79E 05 6.38E 13 5 34E 03 1.18E-03 2.63E-03

C 1.06E-03 1.79E-06 6.38E 14 5.34E-04 1.18E-04 2.63E-04

D 5.31E-04 8.96E-07 3.19E-14 2.67E-04 5.89E-05 1.32E-04

E 1 06E 04 1.79E-07 6.38E-15 5.34E-05 1.18E-05 2.63E-05

F 5.31 E-05 8.96E-08 3.19E-15 2.67E-05 5.89E-06 1.32E-05

1.06E 05 1.79E 08 6.38E- 16 5.14E 06 1.18E-06 2.63E-06

Page 4 of 4

0

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LEAFY VEGETATION ACTIVITY (pCilkg)

Day I Zone I 131 1 133 1 135 Cs 134 CS 136 CS 137

A 2.47E+01 4.65E+01 3.54E+01 5.31E+00 1.92E+00 2.59E+00

B 2.47E+X) 4.65E+00 3.54E+00 5.31E-01 1.92E-01 2.59E-01

C 2.47E-01 4.65E-01 3.54E-01 5.31E-02 1.92E-02 2.59E-02

D 1.24E-01 2.32E-01 1.77E-01 2.65E02 9.62E-03 1.30E-02

E 2.47E-02 4.65E-02 3.54E-02 5.31E-03 1.92E-03 2.59E-03

F 1.24E-02 2.32E-02 1.77E-02 2.651-03 9.62E-04 1.30E-03

G 2.47E-03 4.65E-03 3.54E-03 5.3 1E-04 1.92E-04 2.59E-04

Day 1.5 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 2.31Ei-01 3.06E+01 1.0)E+01 5.17E+00 1.83E+00 2.53E+00

B 2.31E4(X) 3.06E+0) 1.00E+400 5.17E-01 1.83E-01 2.53E-01

C 2.31E-01 3.06E-01 1.00E-01 5.17E-02 1.83E-02 2.53E-02

D 1.16E-01 1.53E-01 5.01E-02 2.591-02 9.15E-03 1.27E-02

E 2.31 E-02 3.06E-02 1.00E-02 5.17E-03 1.83E-03 2.53E-03

F 1.16E-02 1.53E-02 5.01E-03 2.59E-03 9.15E-04 1.27E-03

G 2.31E-03 3.06E-03 1.00E-03 5.17E-04 1.83E-04 2.53E-04

Day 2 711 I I l iW 1II 'I CS 116 CS 117

A 2.16E 1Ol 2.011 i I 2.84E 100 55 5E 100 1.74E+MO 2.47000

13 2.16E+0 () 2.01 E00 2.811-l 5.05E 01 1.74E-01 2.47E-01

C 2.16E-01 2.01E-01 2.84E-02 5.05E-02 1.74E-02 2.47E-02

D 1.08E-01 1.01E-01 1.42E-02 2.52E-02 8.70E-03 1.23E-02

E 2.16E-02 201E-02 2.84E-03 5.05E-03 1.74E-03 2.47E-03

F 1.08E-02 1.012 -02 1.42E-03 2.52E-03 8.70E-04 1.23E-03

G 2.16E-03 2.01E-03 2.84-04 5.05E-04 1.74E-04 2.47E-04

Values are fr Iunwashed vegetation. If vegetation has beein washed, divide by 1(X). Pape I of 4

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LEAFY VEGETATION ACTIVITY (pCi/kg)

Day 3 Zone I 131 1133 I 135 Cs 134 CS 136 CS 137

A 1.89Eiol 8.71EOM 2.27E-01 4.80E+00M 1.57E+0() 2.35E+0)

B 1.89E+0) 8.71E-01 2.27E-02 4.80E-01 1.57E-01 2.35E-01

C 1.89E-01 8.71E-02 2.27E-03 4.80E-02 1.57E-02 2.35E-02

D 9.43E-02 4.36E-02 1.13E-03 2.40E-02 7.87E-03 1.17E-02

E 1.89E-02 8.71E-03 2.27E-04 4.80E-03 1.57E-03 2.35E-03

F 9.43E-03 4.36E-03 1.13E-04 2.40E-03 7.87E-04 1.17E-03

Gl 1.89E03 8.71E-04 2.27E-05 4.80E-04 1.57E-04 2.35E-04

Day 4 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.65E+01 3.77E+00 1.82E-02 4.56E+00 1.42E+00 2.24E400

B 1.65E+00 3.77E-01 1.82E-03 4.56E-01 1.42E-01 2.24E-01

C 1.65E-01 3.77E-02 1.82E-04 4.56E-02 1.42E-02 2.24E-02

D 8.23E-02 1.89E-02 9.08E-05 2.28E-02 7.12E-03 1.12E-02

E 1.65E-02 3.77E-03 1.82E-05 4.56E-03 1.42E-03 2.24E-03

F 8.23E-03 1.89E-03 9.08E-06 2.28E-03 7.12E-04 1.12E-03

(G 1.65E-03 3.77E-04 1.82E-06 4.56E-04 1.42E-04 2.24E-04

Day 5 7 1 1 133 I 135 Cs 134 Cs 136 Cs 137

A 1.44E311 1.63E+00 1.45E-03 4. 34E+00) 1.29E+00 2.13E+00

B 1.44E+00 1.63E-01 1.45E-(4 4.34E-01 1.29E-01 2.13E-01

C 1.44E-01 1.63E-02 1.45E-05 4.34E-02 1.29E-02 2.13E-02

D 7.19E-02 8.16E-03 7.27E-06 2.17E-02 6.45E-03 1.06E-02

E 1.44E02 1.631-03 1.45E-06 4.34E-03 1.29E-03 2.13E-03

F 7.19E-03 8.16E-04 7.27E-07 2.17E-03 6.45E-04 1.06E-03

G 1.44E-03 1.63E-04 1.45E-07 4.34E-04 1.29E-04 2.13E-04

Values are for unwashed vegetation. If vegetation has been washed, divide by 10(X. Page 2 of 4

0 0

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LEAFY VEGETATION ACTIVITY (pCilkg)

Day 6 Zone I 131 I 133 1 135 Cs 134 CS 136 CS 137

A 1.25E+01 7.07E-01 1.16E-04 4.12E+00 1.17E+00 2.03E+00 B 1.25E+(X) 7.07E-02 1.16E-05 4.12E-01 1.17E-01 2.03E-01 C 1.25E-01 7.07E-03 1.16E-06 4.12E-02 1.17E-02 2.03E-02 D 6.27E-02 3.53E-03 5.82E-07 2.06E-02 5.83E-03 1.01E-02 E 1.25E-02 7.07E-04 1.16E-07 4.12E-03 1.17E-03 2.03E-03 F 6.27E-03 3.53E-04 5.82E-08 2.06E-03 5.83E-04 1.01E-03 G, 1.25E-03 7.07E-05 1.16E-08 4.12E-04 1.17E-04 2.03E-04

Day 7 ZonIe 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.10E+01 3.06E-01 9.32E-06 3.92E+00 1.06E+00 1.93E+00 11 1. 102*00( 3.06E 02 9.32E-07 3.92E-01 1.06E-01 1.93E-01 C 1.10E-01 3.06E-03 9.32E-08 3.92E-02 1.061-02 1.93E-02 D 5.48E-02 1.53E-03 4.66E-08 1.96E-02 5.28E-03 9.64E-03 E 1.10E-02 3.063-04 9.32E-09 3.92E-03 1.06E-03 1.93E-03 F 5,48E-03 1.53E-04 4.66E-09 1.96E-03 5.28E-04 9.64E-4 G 1.10OE-03 3.06E-05 9.32E-10 3.92E-04 1.06E-4 1.93E-04

Day 8 Zone I 131 A1 133 1 135 Cs 134 CS 136 CS 137

A 9.57E100 1.32F 01 7.46F 07 1.7 iE 00 9.55E-01 1.83000 R 9.57E-01 1.32E-02 7.46E 08 3.7 -EIll 9.55E-02 1.83E-01 C 9.57E-02 1.32E-03 7.46E-09 3.73E-02 9.55E-03 1.83E-02 D 4.78E-02 6.62E-AM 3.73E-09 1.86E-02 4.77E-03 9.17E-03 E 9.57E-03 1.32E-04 7.46E-10 3.73E-03 9.55E-04 1.83E-03 F 4.78E-03 6.62E-05 3.73E-10 1.86E-03 4.77E-04 9.17E-04 G 9.57F-0 1.32E-05 7.46E-11 3.731-04 9.55E-05 1.83E-04

Vahics are for unwashed vegelation. If vegetation has been washed, divide by 1000. Page 3 of 4

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LEAFY VEGETATION ACTIVITY (pCi/kg)

Day 9 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 8.35E+00 5.74E-02 5.97E-08 3.55E+00 8.64E-01 1.75E+00

B 8.35E-01 5.74E-03 5.97E-09 3.55E-01 8.64E-02 1.75E-01

C 8.35E-02 5.74E-04 5.97E-10 3.55E-02 8.64E-03 1.75E-02

D 4.18E-02 2.87E-04 2.99E-10 1.77E-02 4.32E-03 8.73E-03

E 8.35E-03 5.74E-05 5.97E- I 3.55E-03 8.64E-04 1.75E-03

F 4.18E-03 2.87E-05 2.99E-l 1 1.77E-03 4.32E-04 8.73E-04

G 8.35E-04 5.74E-06 5.97E-12 3.55E-04 8.64E-05 1.75E-04

Day 10 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 7.30E+00 2.48E-02 4.78E-09 3.37E+00 7.81E-01 1.66E+00

R 7.30E-01 2.48E-03 4.78E- 10 3.37E-01 7.81E-02 1.66E-01

C 7.30E-02 2.48E-04 4.78E-I I 3.37E-02 7.81E-03 1.66E-02

D 3.65E-02 1.24E-04 2.39E-1 1.69E-02 3.91E-03 8.30E-03

E 7.30E-03 2.48E-05 4.78E-12 3.37E-03 7.81E-04 1.66E-03

F 3.65E-03 1.24E.05 2.39E-12 1.69E-03 3.91E-04 8.30E-04

G 7.302-(4 2.48E-06 4.78E-13 3.37E-04 7.81E-05 1.66E-04

Day 11 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 6.37E 100 1.08E-02 383E 11) 1,20(X 7.07E-01 1.58E400

B 6.37E-01 1.08E 03 3 83E II 3.201- 01 7.07E-02 1.58E-01

C 6.37E-02 1.08E-( 383E- 12 3.20E-02 7.071-03 1.58E-02

D 3.18E-02 5.38E-05 1.91E-12 1.60E-02 3.54E-03 7.90E-03

E 6.37E-03 1.08E-05 3.83E-13 3.20E-03 7.07E-04 1.58E-03

F 3.18E-03 5.38E-06 1.91E-13 1.60E-03 3.54E-04 7.90E-04

G 6.37E-04 1.08E-06 3.83E-14 3.20E-04 7.07E-05 1.58E-04

Values are for inwashed vegetation. If vegetation has been washed, divide by 1000. Page 4 of 4

* * *

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PRODUCE ACTIVITY (piCi/kg)

Day 1 7Aone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.24E+00 2.32E-fO() 1.77E+00 2.65E-01 9.62E-02 1.30E-01

B 1.24E-01 2.32E-01 1.77E-01 2.65E-02 9.62E-03 1.30E-02

C 1.24E-02 2.32E-02 1.77E-02 2.65E-03 9.62E-04 1.30E-03

D 6.18E-03 1.16E-02 8.85E-03 1.33E-03 4.8 1E-04 6.49E-04

E 1.24E-03 2-32E 03 1.77E-03 2.65E-04 9.62E-05 1.30E-(A

IF 6.18E-04 1.16E-03 8.85E-04 1.33E-04 4.8 1E-05 6.49E-05

G1 1.24E-04 2.32E-() 1.77E-04 2.65E-05 9.62E-06 1.30E-05

Day 1.5 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.16E() 1.53E+00 5.01IE-0 1 2.59E-01 9.15E-02 1.27E-01 B 1.16E-01 1.53E-01 5.01IE-02 2.59E-02 9.15E-03 1.27E-02

C 1.16E-02 1.53E-02 5.01IE-03 2.59E-03 9.15E-04 1.27E-03

D 5.78E-03 7.64E-03 2.5 1E-03 1.29E-03 4.58E-04 6.33E-04

E 1. 16E-03 1.53E-03 5.01E-04 2.59E-04 9.15E-05 1.27E-04

IF 5.78E-04 7.64E-04 2.5 1E-04 1.29E-04 4.58E-05 6.33E-05

G 1. 16E-04 1.53E-04 5.01E-05 2.59F-05 9.15E-06 1.27E-05

D~ay 2 Zone I 111 1 B 115 ('.11 ('S 136 CS 137

A 1 .08Ei)) 100 1 EIF 100 1.4 2F 01 2.5 21? (01 8.70E-02 1 .21E( 01

B) I A)EII 1.01E) 01 1.42 2-02 2.52 202 8.7013-03 1 .23E-02

C 1.08E-0)2 1.01E-02 1.4213 03 2.52E-03 8.70E-W~ 1.23E3-03

D) 5.40E3-03 5.03E3-03 7.09E4-4 1.26E3-03 4.35E-04 6.17E-04

E 1.08E-03 1.0 1E03 1,4213-(4 2.52E-0-1 8.70E-05 1.23E-04

F 5.40E-04 5.03E-04 7.09E-05 I.26E3-04 4.35E-05 6.17E-05

G IN 04E 1.0 13F1)M 1.42F3-05 2.521--05 9.70E3-06 1.23E3-05

'vale arc' i I' inwse ploSdCI )u(icc. If* J)FotIicC is \\'1sI1c(, d(lid(c \'fluhiC y 1000. Page I of 4

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PRODUCE ACTIVITY (pCi/kg)

Day 3 Z)ne 1131 1 133 1 135 Cs 134 CS 136 CS 137

A 9.43E-01 4.36E-01 1.13E-02 2.40E-01 7.87E-02 1.17E-01

B 9.43E-02 4.36E-02 1.13E-03 2.40E-02 7.87E-03 1.17E-02

C 9.43E-03 4.36E-03 1.13E-04 2.40E-03 7.87E-04 1.17E-03

D 4.71E-03 2.18E-03 5.67E-05 1.20E-03 3.94E-04 5.87E-04

E 9.43E-04 4.36E-(4 1.13E-05 2.40E-04 7.87E-05 1.17E-04

F 4.7 1E-04 2.18E-04 5.67E-06 1.20E-04 3.94E-05 5.87E-05

G 9.43E-05 4.36E-05 1.13E-06 2.40E-05 7.87E-06 1.17E-05

Day 4 Zne 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 8.23E-01 1.89E-01 9.08E-04 2.28E-01 7.12E-02 1.12E-01

B 8.23E-02 1.89E-02 9.08E-05 2.28E-02 7.12E-03 1.12E-02

C 8.23E-03 1.89E-03 9.08E-06 2.28E-03 7.12E-04 1.12E-03

D 4.11E-03 9.43E-04 4.54E-06 1.14E-03 3.56E-04 5.59E-04

E 8.23E-04 1.89E-04 9.08E-07 2.28E-04 7.12E-05 1.12E-04

F 4.11E-04 9.43E-05 4.54E-07 1.14E-04 3.56E-05 5.59E-05 G 8.23E-05 1.89E 05 9.08E208 2.28E 05 7.12E-06 1.12E-05

Day 5 Zone 1 131 1133 1135 (s 131 CS 136 CS 137

A 7.19E-01 8.16E 02 7.27E-05 2.17E 01 6.45E-02 1.06E-01

B 7.19E-02 8.16E-03 7.27E-06 2.17E02 6.45E-03 1.06E-02

C 7.19E-03 8.16E4(1 7.27E-07 2.17E-03 6.45E-04 1.06E-03

D 3.59E-03 4.08E-04 3.64E-07 1.08E-03 3.22E-04 5.32E-04

E 7.19E-04 8.16E-05 7.27E-08 2.17E-04 6.45E-05 1.06E-04

F 3.59E-04 4.08E-05 3.64E-08 I.08E-(M 3.22E-05 5.32E-05

G 7.19E 05 8.1 6F 06 7.271 09 1 7F05 6.45F 06 1.06(E 05

Values are for unwashed produce. If produce is washdI. divide values by 1000.

Page 2 of 4

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PRODUCE ACTIVITY (pCi/kg)

Day 6 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 6.27E-01 3.53E-02 5.82E-06 2.06E-01 5.83E-02 1.01E-01 B 6.27E-02 3.53E-03 5.82E-07 2.06E-02 5.83E-03 1.01E-02 C 6.27E-03 3.53E-04 5.82E-08 2.06E-03 5.83E-04 1.01E-03 D 3.14E-03 1.77E-04 2.91E-08 1.03E-03 2.92E-04 5.06E-04 E 6.27E-04 3.53E-05 5.82E-09 2.06E-04 5.83E-05 1.01E-04 F 3.14E-04 1.77E-05 2.911E-09 1.03E-04 2.92E-05 5.06E-05 G 6.27E-05 3.53E-06 5.82E-10 2.06E-05 5.83E-06 1.01E-05

Day 7 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 5.48E-01 1.53E-02 4.66E-07 1.96E-01 5.28E-02 9.64E-02

B 5.48E-02 1.53E-03 4.66E-08 1.96E-02 5.28E-03 9.64E-03 C 5.48E-03 1.53E-04 4.66E-09 1.96E-03 5.28E-04 9.64E-04

D 2.74E-03 7.65E-05 2.33E-09 9.80E-04 2.64E-04 4.82E-04

E 5.48E-04 1.53E-05 4.66E-10 1.96E-04 5.28E-05 9.64E-05 F 2.74E-04 7.65E-06 2.33E-10 9.80E-05 2.64E-05 4.82E-05 G 5.48E-05 1.53E-06 4.66E-11 1.96E-05 5.28E-06 9.64E-06

Day 8 Zone 1 131 1133 I 135 (s 13-1 CS 136 CS 137

A 4.78E-01 6.62E 03 3.73F-08 1 .86 01 4.77E-02 9.17E-02

H 4.78E-02 6.62E-04 3.73E-09 1.86E-02 4.77E-03 9.17E-03

C 4.78E-03 6.62E-05 3.73E-10 1.86E-03 4.77E-4 9.17E41

D 2.39E-03 3.311E-05 1.87E-10 9.32E-(M 2.39E-04 4.58E-04

E 4.78E-04 6.62E-06 3.73E-1I 1.86E-04 4.77E-05 9.17E-05

F 2.39E-04 3.31E-06 1.87E-11 9.32E-05 2.39E-05 4.58E-05

(1 4.78F-05 6.62E-07 3.73E-12 1.861105 4.77F-06 9.17E-06

Values are for unwashed produce.. if prodxuce is washed, divide values by 1000. Page 3 of 4

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PRODUCE ACTIVITY (pCi/kg)

Day 9 7Anc 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 4.18E-01 2.87E-03 2.99E-09 1.77E-01 4.32E-02 8.73E-02

B 4.18E-02 2.87E-04 2.99E-10 1.77E-02 4.32E-03 8.73E-03

C 4.18E-03 2.87E-05 2.99E- Il 1.77E-03 4.32E-04 8.73E-04

D 2.09E-03 1.43E-05 1.49E-11 8.86E-04 2.16E-04 4.36E-04

E 4.18E-04 2.87E-06 2.99E-12 1.77E-04 4.32E-05 8.73E-05

F 2.09E-04 1.43E-06 1.49E-12 8.86E-05 2.16E-05 4.36E-05

G 4.18E-05 2.87E-07 2.99E-13 1.77E-05 4.32E-06 8.73E-06

Day 10 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 3.65E-01 1.24E-03 2.39E-10 1.69E-01 3.91E-02 8.30E-02

B 3.65E-02 1.24E-04 2.39E-ll 1.69E-02 3.91E-03 8.30E-03

C 3.65E-03 1.24E-05 2.39E-12 1.69E-03 3.91E-04 8.30E-04

D 1.82E-03 6.21E-06 1.20E-12 8.43E-04 1.95E-04 4.15E-04

E 3.65E-04 1.24E-06 2.39E-13 1.69E-04 3.91E-05 8.30E-05

F 1.82E-04 6.21E-07 1.20E-13 8.43E-05 1.95E-05 4.15E-05

G 3.65E-05 1.24E-07 2.39E-14 1.69E-05 3.91E-06 8.30E-06

Day 11 Zoic 1 131 1 133 1 135 1s 134 CS 136 CS 137

A 3.18E-01 5.38E-04 1.91E-1 I 1.60E-01 3.54E-02 7.90E-02

B 3.18E-02 5.38E-05 1.91E-12 1.60E-02 3.54E-03 7.90E-03

C 3.18E-03 5.38E-06 1.91E-13 1.60E-03 3.54E-04 7.90E-04

D 1.59E-03 2.69E-06 9.57E-14 8.01E-04 1.77E-04 3.95E-04

E 3.18E-04 5.38E-07 1.91E-14 1.60E-04 3.54E-05 7.90E-05

F 1.59E-04 2.69E-07 9.57E-15 8.01E-05 1.77E-05 3.95E-05

G, 3.18F-05 5.38E-08 1.91E-15 1,60F-05 3.54E-06 7.90E-06

Values are for unwashed produce. If prod(uce is washed, divide values by 1000. Page 4 of 4

* * *

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MILK ACTIVITY (pCi/I)

Day 1.5 Zone 1131 1133 1135 Cs134 Csl37

A 5.OOE+OO 7.18E+00 4.23E+00 4.68E-01 2.28E-0OI B 5.OOE-O1I 7.18E-01 4.23E-0OI 4.68E-02 2.28E-02

C 5.OOE-02 7.18E-02 4.23E-02 4.68E-03 2.28E-03

D 2.50E-02 3.59E-02 2.11 E-02 2.34E-03 1. 14E-03

E 5.OOE-03 7.18E-03 4.23E-03 4.68E-04 2.28E-04

F 2.50E-03 3.59E-03 2.1IE-03 2.34E-04 1.14E-04

G 5.OOE-04 -1.18E-04 4.23E-04 4.68E-05 2.28E-05

Day Zone 1131 1133 1135 Cs134 Cs137

A 8.OOE+OO 8.21E+00 2.88E+00 8.50E-01 4.15E-01 B 8.OOE-O1 8.21 E-0OI 2.88E-01 8.50E-02 4.15E-02

C 8.OOE-02 8.21E-02 2.88E-02 8.50E-03 4.15E-03 D 4.OOE-02 4.1 OE-02 1 .44E-02 4.25E-03 2.08E-03

E S.OOE-03 N.2 IE-03 2.88E-03 8.50E-04 4.15E-04

F 4.OOE-03 4. 1OE-03 1.44E-03 4.25E-04 2.08E-04

G 8.OOE-04 8.2 1E-04 2.88E-04 8.50E-05 4.15E-05

Day Zone 1131 1133 1135 Cs134 Csl37

A 1 .20E+01 5.75E+00 7.69E-01 1.28E+00 6.23E-01

B 1.20E+00 5.75E-01 7.69E-02 1.28E-01 6.23E-02

C 1 .20E-01 5.75E-02 7.69E-03 1.28E-02 6.23E-03 D 6.OOE-02 2.87E-02 3.84E-03 6.38E-03 3.11 E-03

E 1 .20E-02 5.75E-03 7.69E-04 1.28E-03 6.23E-04 F 6.OOE-03 2.87E-03 3.84E-04 6.38E-04 3.1 IE-04

G 1.20E-03 5.75E-04 7.69E-05 1.28E-04 6.23E-05

Day

Zone 1131 1133 1135 Cs134 Cs137

A 1.30E+01 3.08E+01 1.15E-01 1.49E-+00 7.27E-01

B 1.30E+00 3.08E+00 1. 15E-02 1 .49E-01 7.27E-02 C 1.30E-01 3.08E-01 1. 15E-03 1.49E-02 7.27E-03 D 6.50E-02 1 .54E-01 5.77E-04 7.44E-03 3.63E-03 E 1 .30E-02 3.08E-02 1.15E-04 1.49E-03 7.27E-04 F 6.50E-03 1 .54E-02 5.77E-05 7.44E-04 3.63E-04 G 1.30E-03 3.08E-03 1.15E-05 1.49E-04 7.27E-05

Page 1 of 3

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MILK ACTIVITY (pCill)

Day Zone 1131 1133 1135 Cs134 Csl37

A 1.20E+01 1.27E+00 2.50E-02 1.59E+00 7.78E-01

B 1.20E+00 1.27E-01 2.50E-03 1.59E-01 7.78E-02

C 1.20E-01 1.27E-02 2.50E-04 1.59E-02 7.78E-03

D 6.OOE-02 6.36E-03 1.25E-04 7.97E-03 3.89E-03

E 1.20E-02 1.27E-03 2.50E-05 1.59E-03 7.78E-04 F 6.OOE-03 6.36E-04 1.25E-05 7.97E-04 3.89E-04

G 1.20E-03 1.27E-04 2.50E-06 1.59E-04 7.78E-05

Day 6 Zone 1131 1133 1135 Cs134 Cs137

A 1.00E+01 6.16E+00 1.66E+00 8.1OE-01

B 1.00E+00 6.16E-01 1.66E-01 8.1OE-02 C 1.00E-01 6.16E-02 1.66E-02 8.10E-03 D 5.OOE-02 3.08E-02 8.29E-03 4.05E-03 E 1.OOE-02 o.I6E-03 1.66E-03 8.10E-04

F 5.OOE-03 ()8E-03 8.29E-04 4.05E-04

G .OOE-03 0.16E-04 1.66E-04 8.1OE-05

Day Zone 1131 1133 1135 Cs134 Cs137

A 9.OOE+00 2.67E-01 1.68E+00 8.20E-01 B 9.00E-O1 2.67E-02 1.68E-01 8.20E-02 C 9.OOE-02 2.67E-03 1.68E-02 8.20E-03 D 4.50E-02 1.33E-03 8.39E-03 4.1OE-03 E 9.OOE-03 2.67E-04 1.68E-03 8.20E-04 F 4.50E-03 1.33E-04 8.39E-04 4.10E-04

G 9.OOE-04 2.67E-05 1.68E-04 8.20E-05

Day Zone 1131 1133 1135 Cs134 Cs137

A 8.OOE+00 1.23E-01 1.70E+00 8.30E-01 B 8.OOE-01 1.23E-02 1.70E-01 8.30E-02 C 8.OOE-02 1.23E-03 1.70E-02 8.30E-03 D 4.OOE-02 6.16E-04 8.50E-03 4.15E-03 E 8.OOE-03 1.23E-04 1.70E-03 8.30E-04 F 4.OOE-03 6.16E-05 8.50E-04 4.15E-04

G 8.00E-04 1.23E-05 1.70E-04 8.30E-05

Page 2 of 3

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MILK ACTIVITY (pGi/I)

Day 9 Zone 1131 1133 1135 Cs134 Cs137

A 7.OOE+OO 5.34E-02 1.68E+00 8.20E-01 B 7.OOE-O1I 5.34E-03 1.68E-01 8.20E-02 C 7.OOE-02 5.34E-04 1.68E-02 8.20E-03 D 3.50E-02 '-.67E-04 8.39E-03 4.10E-03

E 7.OOE-03 5.34E-05 1.68E-03 8.20E-04

F 3.50E-03 2.67E-05 8.39E-04 4.10OE-04 G 7.OOE-04 5.4E-06 1.68E-04 8.20E-05

Day 10 Zone 1131 1133 1135 Cs134 Cs137

A 6.OOE+OO 2.67E-02 1.66E+00 8.1OE-O1 B 6.OOE-O1 I 2.67E-03 1.66E-0O1 8. 1OE-02 C 6.OOE-02 2.67E-04 1.66E-02 8. 1OE-03 D 3.OOE-02 1 .33E-04 8.29E-03 4.05E-03 E 6.00E-03 -'67E-05 1.66E-03 8.10OE-04 F 3.00E-03 1.33E-05 8.29E-04 4.05E-04

G 6.OOE-04 '-.67E-06 1.66E-04 8.10E-05

Day 1 Zone 1131 1133 1135 Cs134 Cs137

A 5.50E+00 1.64E+00O 7.99E-01 B 5.50E-01 1 .64E-01 7.99E-02 C 5.50E-02 1 .64E-02 7.99E-03 D 2.75E-02 8.18E-03 4.OOE-03 E 5.50E-03 1.64E-03 7.99E-04 F 2.75E-03 8.18E-04 4.OOE-04 G 5.50E-04 1.64E-04 7.99E-05

Notes

I Values are for animals which were not placed on stored feed during day 1.

2. If animals were placed on stored feed during day 1, divide values by 103

Page 3 of 3

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FORAGE ACTIVITY (pCi/kg)

Day I Ane I 131 I 133 I 135 Cs 134 CS 136 CS 137

A 2.63E+00 4.65E+01 3.54E+01 7.08E+01 1.92E+00 5.62E+01

B 2.63E-01 4.65E+00 3.54E+00 7.08E+00 1.92E-01 5.62E+00 C 2.63E-02 4.65E-01 3.54E-01 7.08E-01 1.92E-02 5.62E-01 D 1.32E-02 2.32E-01 1.77E-01 3.54E-01 9.62E-03 2.81E-01 E 2.63E-03 4.65E-02 3.54E-02 7.08E-02 1.92E-03 5.62E-02 F 1.32E-03 2.32E-02 1.77E-02 3.54E-02 9.62E-04 2.81E-02

G 2.63E-04 4.65E-03 3.54E-03 7.08E-03 1.92E-04 5.62E-03

Day 1.5 Zone 1131 1 133 1 135 Cs 134 CS 136 CS 137

A 2.46E+00 3.06E+01 1.00E+01 6.90E+01 1.83E+00 5.48E+01

B 2.46E-01 3.06E+00 1.00E+00 6.90E+00 1.83E-01 5.48E400

C 2.46E-02 3.06E-01 1.00E-01 6.90E-01 1.83E-02 5.48E-01

D 1.23E-02 1.53E-01 5.01E-02 3.45E-01 9.15E-03 2.74E-01

E 2.46E-03 3.06E-02 1.00E-02 6.90E-02 1.83E-03 5.48E-02

F 1.23E-03 1.53E-02 5.01E-03 3.45E-02 9.15E-04 2.74E-02

G 2.46E-04 3.06E-03 1.00E-03 6.90E-03 1.83E-04 5.48E-03

Day 2 Zone 1 131 1 133 1 135 Cs 13 CS 136 CS 137

A 2.30E 00 2.01E101 2.84Ei00 6.73E10l 1.7-10 10) 5.35E 01

B 2.30E-01 2.01E100 2.84E -01 6.73.000 1.74E-01 5.35E 00

C 2.30E-02 2.01E-01 . 2.84E-02 6.73E-0I 1.74E-02 5.35E-01

D 1.15E-02 1.01E-01 1.42E-02 3.36E-01 8.70E-03 2.68E-01

E 2.30E-03 2.01E-02 2.84E-03 6.73E-02 1.74E-03 5.35E-02

F. 1.15E 03 1.01E-02 1.42E-03 3.36E 02 8.70E-04 2.68E 02

C 2.30E-01 2.01E-03 2.84E1I 6,73F 03 1.74E(0 5.35E 01

Pr - I of 4

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FORAGE ACTIVITY (pCi/kg)

Day 3 7,01c 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 2.01 E+00 8.7 1E+00 2.27E-01 6.40E+01 1.57E+00 5.09E+01

B 2.01E-01 8.71E-01 2.27E-02 6.40E+00 1.57E-01 5.09E+00 C 2.01 E-02 8.7 1E-02 2.27E-03 6.40E-01 1.57E-02 5.09E-01

D 1.00E-02 4.36E-02 1.I13E-03 3.20E-01 7.87E-03 2.55E-01

E 2.012E-03 8.7 1E-03 2.27E-04 6.40E-02 1.57E-03 5.09E-02

F L.00E-03 4.36E-03 1. 13E-04 3.20E-02 7.87E-04 2.55E-02

G 2.01 E-04 8.7 1E-04 2.27E-05 6.40E-03 1.57E-04 5.09E-03

Day 4 7,onc 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.75E+00 3.77E+00 1.82E-02 6.08E+01 1.42E-*00 4.85E+i01

B3 1.75E-01 3.77E-01 1.82E-03 6.08E±00 1.42E-01 4.85E±00

C 1.75E-02 3.77E-02 1.82E-04 6.08E-01 1.42E-02 4.85E-01

D 8.76E-03 1.89E-02 9.08E-05 3.04E-01 7.12E-03 2.42E-01

E 1.75E203 3.77E-03 1.82E-05 6.08E202 1.42E-03 4.85E-02

F 8.76E-04 1.89E-03 9.08E-06 3.)4E-02 7.122-04 2.42E-02

6 1.75E-04 3.77E-04 1.82E-06 6.)8E-03 1.42E-04 4.85E-03

Day 5 Z.one I 131 I13 13.113 (\ 13 CS 136 CS 137

A 1.5313 00) 1,613 i00 1.41'F 05 5.7E 10 1 1.29E 100 4.61 E 0 1

11 1.531 1 I .6312 01 1 .451: 0-1 S,.Nil 00 1.29F 01 4.61 E 00

C 1.5313-02 1.63E-02 1.45E 05 5.78E 01 1.29E-02 4.61 E-01I

D 7.64E-03 8.16E-03 7.27E-06 2,892-01 6.45E-03 2.312E-01I

E 1.53E 03 1.63E-03 1.45E-06 5.78E-02 1.29E-0)3 4.612E-02

F 7.64E-04 8.162-04 7,27E-0)7 2.9E-02 6.45E204 2.312E-02

G 1.532-IN 1.61E-(" 1.452-07 5.7821-- 03 1 .29E-04 4.612E-03

0 0

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FORAGE ACTIVITY (pCi/kg)

Day 6 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.34E+00 7.07E-01 1.16E-04 5.50E+01 1.17E+00 4.39E+01 B 1.34E-01 7.07E-02 1.16E-05 5.50E+00 1.17E-01 4.39E+00

C 1.34E-02 7.07E-03 1.16E-06 5.50E-01 1.17E-02 4.39E-01

D 6.68E-03 3.53E-03 5.82E-07 2.75E-01 5.83E-03 2.19E-01 E 1.34E-03 7.07E-04 1.16E-07 5.50E-02 1.17E-03 4.39E-02 F 6.68E-04 3.53E-04 5.82E-08 2.75E-02 5.83E-04 2.19E-02 G 1.34E-04 7.07E-05 1.16E-08 5.50E-03 1.17E-04 4.39E-03

Day 7 7onc 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 1.17E+00 3.06E-01 9.32E-06 5.23E+01 1.06E+00 4.18E+01

B 1.17E-01 3.06E-02 9.32E-07 5.23E+00 1.06E-01 4.18E+00

C 1.17E-02 3.06E-03 9.32E-08 5.23E-01 1.06E-02 4.18E-01

D 5.83E-03 1.53E-03 4.66E-08 2.61E-01 5.28E-03 2.09E-01

E 1.17E-03 3.06E-04 9.32E-09 5.23E-02 1.06E-03 4.18E-02

F 5.83E-04 1.53E-04 4.66E-09 2.61E-02 5.28E-04 2.09E-02

G 1.17E-04 3.06E-05 9.32E-10 5.23E-03 1.06E-04 4.18E-03

Day 8 Il H II'S I-v k'O (I7

A L.0213100 1.32E 01 7.46E 07 1.971oil 9.55E 01 3.97EMI0

B 1.02E-01 1.32E 02 7.46E-08 1.97E 00 9.55E-02 3.97E t00

C 1.02E 02 1.32E-03 7.46E-09 .197E-01 9.55E-03 3.97E-01

D 5.09E-03 6.62E-0M 3.73E-09 2.49E-01 4.77E-03 1.99E-01

E 1.02E03 1.32E-04 7.46E 10 4.97E 02 9.552-04 3.97E-02

F 5.09E-04 6.62E-05 3.73E-10 2.49E-02 4.77E-04 1.99E-02

G W.210 1.321 O(s 71647 FI 1 9(71", 0 9.5W 105 3.971 F 0

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FORAGE ACTIVITY (pCi/kg)

Day 9 7Ane 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 8.89E-01 5.74E-02 5.97E-08 4.73E+01 8.64E-01 3.78E+01 B 8.89E-02 5.74E-03 5.97E-09 4.73E+00 8.64E-02 3.78E+00 C 8.89E-03 5.74E-04 5.97E-10 4.73E-01 8.64E-03 3.78E-01 D 4.44E-03 2.87E-04 2.99E-10 2.36E-01 4.32E-03 1.89E-01 E 8.89E-04 5.74E-05 5.97E- 11 4.73E-02 8.64E-04 3.78E-02 F 4.44E-04 2.87E-05 2.99E-ll 2.36E-02 4.32E-04 1.89E-02 G 8.89E-05 5.74E-06 5.97E-12 4.73E-03 8.64E-05 3.78E-03

Day 10 ZA)nc 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 7.76E-01 2.48E-02 4.78E-09 4.49E+01 7.81E-01 3.60E+01 B 7.76E-02 2.48E-03 4.78E-10 4.49E4-00 7.81E-02 3.60E+00 C 7.76E-03 2.48E-04 4.78E-Il 4.49E-01 7.8 1E-03 3.60E-01 D 3.88E-03 1.24E-04 2.39E-11 2.25E-01 3.91E-03 1.80E-01 E 7.76E-04 2.48E-05 4.78E-12 4.49E-02 7.81E-04 3.60E-02 F 3.88E-04 1.24E-05 2.39E-12 2.25E-02 3.91E-04 1.80E-02 G 7.76E-05 2.48E-06 4.78E-13 4.49E-03 7.81E-05 3.60E-03

Day II Zone 1 131 1133 1135 ( 131 CS 136 CS 137

A 6.78E-01 1.08E-02 3.83E 10 .127Eftol 7.07E-01 3.42E+1I II 6.78E-02 1.08E-03 3.83E- II 427E0O 7.07E-02 3.42E+00 C 6.78E-03 1.08E 04 3.83E 12 4.27E-01 7.07E-03 3.42E-01 D 3.39E-03 5.38E-05 1.91E 12 2.14HE-01 3.54E-03 1.71E-01 E 6.78E-04 1.08E-05 3.83E- 13 4.27E-02 7.07E-04 3.42E-02 F - 3.39E-04 5.38E-06 1.91E 13 2. 1IE-02 3.54E-04 1.71E-02 S 6.78E-05 1.08E-06 3.83E- 1.4 .1.27E-03. 7.07E 05 3.42E-03

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WATER ACTIVITY (pCi/)

Day I Ae 1 131 1133 1 135 Cs 134 CS 136 CS 137

A 6.84E-03 1.46E-02 1.19E-02 1.33E-02 7.24E-04 9.51E-03

B 6.84E-04 1.46E-03 1.19E-03 1.33E-03 7.24E-05 9.51E-04

C 6.84E-05 1.46E-04 1.19E-04 1.33E-04 7.24E-06 9.51E-05

D 3.42E-05 7.29E-05 5.94E-05 6.63E-05 3.62E-06 4.76E-05

E 6.84E-06 1.46E-05 1.19E-05 1.33E-05 7.24E-07 9.51E-06

F 3.42E-06 7.29E-06 5.94E-06 6.63E-06 3.62E-07 4.76E-06

G 6.84E-07 1.46E-06 1.19E-06 1.33E-06 7.24E-08 9.51E-07

Day 1.5 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 6.39E-03 9.59E-03 3.36E-03 1.29E-02 6.89E-04 9.28E-03

B 6.39E-04 9.59E-04 3.36E-04 1.29E-03 6.89E-05 9.28E-04

C 6.39E-05 9.59E-05 3.36E-05 1.29E-04 6.89E-06 9.28E-05

D 3.20E-05 4.79E-05 1.68E-05 6.47E-05 3.44E-06 4.64E-05

E 6.39E-06 9.59E-06 3.36E-06 1.29E-05 6.89E-07 9.28E-06

F 3.20E-06 4.79E-06 1.68E06 6.47E-06 3.44E-07 4.64E-06

G 6.39E-07 9.59E-07 3.36E-07 1.29E-06 6.89E-08 9.28E-07

Day 2 Zoie 1 131 I 133 1 135 Us 134 CS 136 CS 137

A 5.97E03 6.31E 03 9.52E 04 1.26E 02 6.55E-04 9.05E-03

B 5.97E-04 6.31E-04 9.52E-05 1.26E-03 6.55E-05 9.05E-04

C 5.97E-05 6.31E-05 9.52E-06 1.26E-04 6.55E-06 9.05E-05

D 2.99E-05 3.15E-05 4.76E-06 6.31E-05 3.28E-06 4.53E-05

E 5.97E-06 6.31E-06 9.52E-07 1.26E-05 6.55E-07 9.05E-06

F 2.99E-06 3.15E-06 4.76E-07 6.31E-06 3.28E-07 4.53E-06

G 5.97E-07 6.31E-07 9.52E-08 1.26E-06 6.55E-08 9.05E-07

Page 1 of 4

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WATER ACTIVITY (pCi/)

Day 3 Zon I1131 1 133 I 135 Cs 134 CS 136 CS 137

A 5.2 1E-03 2.73E-03 7.62E-05 1.20E-02 5.93E-04 8.62E-03

B 5.2 1E-04 2.73E-04 7.62E-06 1.20E-03 5.93E-05 8.62E-04

C 5.21E-05 2.73E-05 7.62E-07 1.20E-04 5.93E-06 8.62E-05

D 2.61E-05 1.37E-05 3.81E-07 6.00E-05 2.96E-06 4.31E-05

E 5.21E-06 2.73E-06 7.62E-08 1.20E-05 5.93E-07 8.62E-06

F 2.61E-06 1.37E-06 3.81E-08 6.OOE-06 2.96E-07 4.31E-06

G 5.21E-07 2.73E-07 7.62E-09 1.20E-06 5.93E-08 8.62E-07

Day 4 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 4.55E-03 1.182-03 6.10E-06 1.14E-02 5.36E-04 8.20E-03

B 4-552304 1.18E-04 6.10E-07 1.14E-03 5.36E-05 8.20E-04

C 4.55E-05 1.18E-05 6.10E-08 1.14E-04 5.36E-06 8.20E-05

D 2.28E-05 5.91E-06 3.05E-08 5.70E-05 2.68E-06 4.10E-05

E 4.55E06 1.18E-06 6.10E09 1.14E-05 5.36E-07 8.20E-06

F 2.28E-06 5.91E-07 3.05E-09 5.70E206 2.68E-07 4.10E-06

G 4.55E-07 1.18E-07 6.10E-10 1.14E-06 5.36E-08 8.20E-07

Day 5 zone I 131 1 133 I 135 Cs 134 CS 136 CS 137

A 3.98E303 5.12E-04 4.88E07 1 08E-02 4.85E-04 7.80E-03

B 3.98E-04 5.12E-05 4.88108 1.08E-03 4.85E-05 7.80E-04

C 3.98E-05 5.12E-06 4.88E-09 1.08E-04 4.85E-06 7.80E-05

D 1.99E-05 2.56E-06 2.44E-09 5.42E-05 2.43E-06 3.90E-05

E 3.98E-06 5.12E-07 4.88E-)10 1.08E-05 4.85E-07 7.80E-06

F 1.99E306 2.561-07 2.44E 10 5.42E-06 2.43E-07 3.90E-06

G 3.98E-07 5.12E-08 4.88E-I1 1.08E-06 4.85E-08 7.80E-07

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WATER ACTIVITY (pCi/)

Day 6 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 3.47E-03 2.22E-04 3.91E-08 1.03E-02 4.39E-04 7.43E-03 B 3.47E-04 2.22E-05 3.91 E-09 1.03E-03 4.39E-05 7.43E-04

C 3.47E-05 2.22E-06 3.91E-10 1.03E-04 4.39E-06 7.43E-05

D 1.74E-05 1.11E-06 1.95E-10 5.16E-05 2.20E-06 3.71E-05

E 3.47E-06 2.22E-07 3.91E-11 1.03E-05 4.39E-07 7.43E-06

F 1.74E-06 1.11E-07 1.95E-11 5.16E-06 2.20E-07 3.71E-06

G 3.47E-07 2.22E-08 3.91E-12 1.03E-06 4.39E-08 7.43E-07

Day 7 Zone 1 131 1 133 1135 Cs 134 CS 136 CS 137

A 3.03E-03 9.59E-05 3.13E-09 9.80E-03 3.97E-04 7.07E-03

B - 3.03E-04 9.59E-06 3.13E-10 9.80E-04 3.97E-05 7.07E-04

C 3.03E-05 9.59E-07 3.13E-I I 9.80E-05 3.97E-06 7.07E-05

D 1.52E-05 4.80E-07 1.56E-11 4.90E-05 1.99E-06 3.53E-05

E 3.03E-06 9.59E-08 3.13E-12 9.80E-06 3.97E-07 7.07E-06

F 1.52E-06 4.80E-08 1.56E-12 4.90E-06 1.99E-07 3.53E-06

G 3.03E-07 9.59E-09 3.13E-13 9.80E-07 3.97E-08 7.07E-07

Day 8 zone 1 131 I 133 I 135 Cs 134 CS 136 CS 137

A 2.65E-03 4.15E-05 2.51E-10 9.32E-03 3.59E-04 6.72E-03

B 2.65E-04 4.15E-06 2.51E-11 9.32E-04 3.59E-05 6.72E-04

C 2.65E-05 4.15E-07 2.51E-12 9.32E-05 3.59E-06 6.72E-05

D 1.32E-05 2.08E-07 1.25E-12 4.66E-05 1.80E-06 3.36E-05

E 2.65E-06 4.15E-08 2.51E-13 9.32E-06 3.59E-07 6.72E-06

F 1.32E-06 2.08E-08 1.25E-13 4.66E-06 1.80E-07 3.36E-06

2.651 07 4.15F 09 2.5 1F 14 9.32E-07 3.59E-08 6.72F-07

Page 3 of 4

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WATER ACTIVITY (pCi/I)

Day 9 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 2.31E-03 1.80E-05 2.01E-1I 8.86E-03 3.25E-04 6.40E-03 ll 2.31E 04 1.80E)06 2.01E-12 8.86E204 3.25E-05 6.40E-04 C 2.31E-05 1.80E-07 2.01E-13 8.86E-05 3.25E-06 6.40E-05 D 1.16E-05 8.99E-08 1.00E-13 4.43E-05 1.63E-06 3.20E-05 E 2.31E-06 1.80E-08 2.01E-14 8.86E-06 3.25E-07 6.40E-06 F 1.16E-06 8.99E-09 1.00E-14 4.43E-06 1.63E-07 3.20E-06 G 2.31E-07 1.80E-09 2.01E-15 8.86E-07 3.25E-08 6.40E-07

Day 10 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 2.02E-03 7.78E-06 1.61E-12 8.43E-03 2.94E-04 6.09E-03

B 2.02E-04 7.78E-07 1.61E-13 8.43E-04 2.94E-05 6.09E-04 C 2.02E-05 7.78E-08 1.61E-14 8.43E-05 2.94E-06 6.09E-05 D 1.01E-05 3.89E-08 8.03E-15 4.21E-05 1.47E-06 3.04E-05

E 2.02E-06 7.78E-09 1.61E-15 8.43E-06 2.94E-07 6.09E-06

F 1.01E-06 3.89E-09 8.03E-16 4.21E-06 1.47E-07 3.04E-06

G 2.02E-07 7.78E- 10 1.61E-16 8.43E-07 2.94E-08 6.09E-07

Day 11 Zone I 131 I 133 1 135 Cs 134 CS 136 CS 137

A 1.76E-03 3.37E-06 1.29E-13 8.01E-03 2.66E-04 5.80E-03

B 1.76E-04 3.37E-07 1.29E-14 8.01E-04 2.66E-05 5.80E-04

C 1.76E-05 3.37E-08 1.29E-15 8.01E-05 2.66E-06 5.80E-05

D 8.81E-06 1.69E-08 6.43E-16 4.01E-05 1.33E-06 2.90E-05

E 1.76E-06 3.37E-09 1.29E-16 8.01E-06 2.66E-07 5.80E-06

F 8.81E-07 1.69E-09 6.43E-17 4.01E-06 1.33E-07 2.90E-06

G 1.76E-07 3.37E-10 1.29E-17 8.01E-07 2.66E-08 5.80E-07

Page 4 of 4

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DOSE RATE @ 1 METER (mremn/hr)

Day 11.5 2 3 4 5

Zone A 3.08E+00 1.59E+00 1.06E+00 7.15E-01 5.83E-01 5.07E-01

B 3.08E-0OI 1.59E-01 1.06E-01 7.15E-02 5.83E-02 5.07E-02

C 3.08E-02 1.59E-02 BKGD BKGD BKGD BKGD

D 1.54E-02 BKGD BKGD, BKGD BKGD BKGD

E BKGD BKGD BKGD BKGD BKGD BKGD

F BKGD BKGD BKGD, BKGD BKGD BKGD

G BKGD BKGD BKGD BKGD, BKGD BKGD

Day 6 7 8 9 10 11

Zone A 4.53E-01 4.11 E-0OI 2.64E-01 3.46E-01 3.19E-01 2.94E-01

B 4.53E-02 4.11 E-02 2.64E-02 3.46E-02 3.19E-02 2.94E-02

C BKGD BKGD BKGD BKGD BKGD BKGD

D BKGD BKGD BKGD, BKGD BKGD BKGD

E BKGD BKGD BKGD BKGD, BKGD BKGD

F BKGD BKGD BKGD BKGD BKGD BKGD

G BKGD BKGD BKGD BKGD BKGD BKGD

Page 1 of 1

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AQUATIC FOODS ACTIVITY (pCi/kg)

Day 3 Zone 1 131 1133 1 135 Cs 134 CS 136 CS 137

A 7.82E-02 4.1OE-02 1.14E-03 2.40E+01 1.19E+00 1.72E+01

B 7.82E-03 4.10E-03 1.14E-04 2.40E+00 1.19E-01 1.72E+00

C 7.82E-04 4.1OE-04 1.14E-05 2.40E-01 1.19E-02 1.72E-01

D 3.91E-04 2.05E-04 5.71E-06 1.20E-01 5.93E-03 8.62E-02

E 7.82E-05 4.10E-05 1.14E-06 2.40E-02 1.19E-03 1.72E-02

F 3.91E-05 2.05E-05 5.71E-07 1.20E-02 5.93E-04 8.62E-03

G 7.82E-06 4.10E-06 1.14E-07 2.40E-03 1.19E-04 1.72E-03

Day 4 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 6.83E-02 1.77E-02 9.15E-05 2.28E+01 1.07E+00 1.64E+01

B 6.83E-03 1.77E-03 9.15E-06 2.28E400 1.07E-01 1.64E+00

C 6.83E-04 1.77E-04 9.15E-07 2.28E-01 1.07E-02 1.64E-01

D 3.41E-04 8.87E-05 4.57E-07 1.14E-01 5.36E-03 8.20E-02

E 6.83E-05 1.77E-05 9.15E-08 2.28E-02 1.07E-03 1.64E-02

F 3.41E-05 8.87E-06 4.57E-08 1.14E-02 5.36E-04 8.20E-03

G 6.83E-06 1.77E-06 9.15E-09 2.28E-03 1.07E-04 1.64E-03

Day 5 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 5.96E-02 7.68E-03 7.32E-06 2.17E+01 9.71E-01 1.56Ef01

B 5.96E-03 7.68E-04 7.32E-07 2.17E+00 9.71E-02 1.56E+00

C 5.96E-04 7.68E-05 7.32E-08 2.17E-01 9.71E-03 1.56E-01

D 2.98E-04 3.84E-05 3.66E-08 1.08E-01 4.85E-03 7.80E-02

E 5.96E 05 7.68E 06 7.32E-09 2.17E-02 9.71E-04 1.56E-02

F 2.98E-05 3.84E-06 3.66E-09 1.08E-02 4.85E-04 7.80E-03

( 5.96E 06 7.68E-07 7.32E- 10 2.17E -0 9.71E-05 1.56E-03

Page I of 3

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AQUATIC FOODS ACTIVITY (pCi/kg)

Day 6 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 5.21E-02 3.32E-03 5.86E-07 2.06E+01 8.78E-01 1.49E+01

B 5.21E-03 3.32E-04 5.86E-08 2.06E+00 8.78E-02 1.49E+00

C 5.21E-04 3.32E-05 5.86E-09 2.06E-01 8.78E-03 1.49E-01

D 2.60E-04 1.66E-05 2.93E-09 1.03E-01 4.39E-03 7.43E-02

E 5.2 1E-05 3.32E-06 5.86E-10 2.06E-02 8.78E-04 1.49E-02

F 2.60E-05 1.66E-06 2.93E-10 1.03E-02 4.39E-04 7.43E-03

G 5.21E-06 3.32E-07 5.86E-1I 2.06E-03 8.78E-05 1.49E-03

Day 7 Zone 1 131 1 133 1 135 Cs 134 CS 136 CS 137

A 4.55E-02 1.44E-03 4.69E-08 1.96E+01 7.95E-01 1.41E+01

B 4.55E-03 1.44E-04 4.69E-09 1.96E+00 7.95E-02 1.41E+00

C 4.55E-04 1.44E-05 4.69E-)10 1.96E-01 7.95E-03 1.41E-01

D 2.27E-04 7.20E-06 2.35E-10 9.80E-02 3.97E-03 7.07E-02

E 4.55E-05 1.44E-06 4.69E-I1 1.96E-02 7.95E-04 1.41E-02

F 2.27E-05 7.20E-07 2.35E-11 9.80E-03 3.97E-04 7.07E-03

G 4.55E-06 1.44E-07 4.69E-12 1.96E-03 7.95E-05 1.41E-03

Day 8 Zone I 131 I 133 I 135 Cs 134 CS 136 CS 137

A 3.97E-02 6.23E-04 3.76E-09 1.86E+01 7.19E-01 1.34E+01

B 3.97E-03 6.23E-05 3.76E-10 1.86E+00( 7.19E-02 1.34E+00

C 3.97E-04 6.23E-06 3.76E 11 1.86E-01 7.19E-03 1.34E-01

D 1.98E-4 3.12E-06 1.88E-11 9.32E-02 3.59E-03 6.72E-02

E 3.97E-05 6.23E-07 3.76E-12 1.86E-02 7.19E-04 1.34E-02

F 1.98E-05 3.12E-07 1.88E-12 9.32E-03 3.59E-04 6.72E-03

(G 3.97E-06 6.23E-08 3.76E-13 1.86E-03 7.19E-05 1.34E-03

* of 3

0 0

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AQUATIC FOODS ACTIVITY (pCi/kg)

Day 9 Zone 1 131 1133 1135 Cs 134 CS 136 CS 137

A 3.47E-02 2.70E-04 3.OIE-10 1.77E+01 6.50E-01 1.28E+01 B 3.47E-03 2.70E-05 3.01E-I1 1.77E+00 6.50E-02 1.28E+00 C 3.47E-04 2.70E-06 3.01E-12 1.77E-01 6.50E-03 1.28E-01 D 1.73E-04 1.35E-06 1.50E-12 8.86E-02 3.25E-03 6.40E-02

E 3.47E-05 2.70E-07 3.01E-13 1.77E-02 6.50E-04 1.28E-02 F 1.73E-05 1.35E-07 1.50E-13 8.86E-03 3.25E-04 6.40E-03

G 3.47E-06 2.70E-08 3.01E-14 1.77E-03 6.50E-05 1.28E-03

Day 10 Zone 1131 1133 1135 Cs 134 CS 136 CS 137

A 3.03E-02 1.17E-04 2.41E-11 1.69E+01 5.88E-01 1.22E+01

B 3.03E-03 1.17E-05 2.41E-12 1.69E+00 5.88E-02 1.22E+00

C 3.03E-04 1.17E-06 2.41E-13 1.69E-01 5.88E-03 1.22E-01

D 1.51E-04 5.84E-07 1.20E-13 8.43E-02 2.94E-03 6.09E-02

E 3.03E-05 1.17E-07 2.41E-14 1.69E-02 5.88E-04 1.22E-02

F 1.51E-05 5.84E-08 1.20E-14 8.43E-03 2.94E-04 6.09E-03

G 3.03E-06 1.17E-08 2.41E-15 1.69E-03 5.88E-05 1.22E-03

Day 11 Zone 1 131 1 133 1135 Cs 134 CS 136 CS 137

A 2.64E-02 5.06E-05 1.93E-12 1.60E+01 5.32E-01 1.16E+01

B 2.64E-03 5.06E-06 1.93E-13 1.60E+00 5.32E-02 1.16E+00

C 2.64E-04 5.06E-07 1.93E-14 1.60E-01 5.32E-03 1.16E-01

D 1.32E-04 2.53E-07 9.64E-15 8.01E-02 2.66E-03 5.80E-02

E 2.64E-05 5.06E-08 1.93E-15 1.60E-02 5.32E-04 1.16E-02

F 1.32E-05 2.53E-08 9.64E-16 8.01E-03 2.66E-04 5.80E-03

C 2.64E-06 5.06E 09 1.93F 16 1.60-03 5.32E-05 1.16E-03

Note

I. Aquatic foods include fish, shellfish, etc.

Pae' 3of 3

0 0

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POST-ACCIDENT SAMPLING DATA

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POST-ACCIDENT CONTAINMENT AIR SAMPLING

ONS EMERGENCY DRILL 92-04

Following successful operation of the Post- Accident Containment Air Sampling System, sample analysis will indicate the following containment air concentrations.

1-131 equivalent 8.79 E-03 vCi/cc

1-131 8.47 E-03 pCi/cc

1-133 1.62 E-04 pCi/cc

1-135 5.11 E-04 pCi/cc

Cs-134 1.76 E-03 pCi/cc

Cs-134 8.79 E-04 VCi/cc

Xe-133 equivalent 102 pCi/cc

NOTE: The various isotopes of xenon are not listed individually because

analytical results are given in 133 equivalence.

Assumptions: 1) 95% of the original airborne iodine is placed into solution by building spray - [0.05 x 3.38 pCi/cc = 0.169 pCi/cc]. Deposition factor for iodine and particulates is 19.23

NOTE: The deposition correction must be applied by the technician to correct analysis results.

2) Containment airborne concentration of noblegases is 102 pCi/cc Xe-133 equivalent.

3) Airborne Cs-137 concentration is 10%of the airborne iodines' iodine 131 equivalent. Cs-134 concentration is twice that of Cs-137.

Dose rates on samples were determined to be relatively insignificant. A nominal value of 5 mr/hr will be use as the dose rate from the each of the samples.

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MESSAGE NUMBER Chemistry - 2

DUKE POWER COMPANY

OCONEE NUCLEAR STATION

Drill 92-04

Date 08-11-92 Time *

PLANT CONDITION:

TO: Chemistry technician sampling RCS via PALSS.

FROM: Controller

MESSAGE: See attached sheets for data. SHEET #2A - 1230/1530 SHEET 2B - 1530/END OF DRILL

* Data is valid after 1230. Boron concentration should be determined by

Controller based on volumnes pumped by Operations.

** Omly data requested by TSC/OSC should be reported to technician from attached

sheet

ACTIONS EXPECTED: Notify OSC with results.

Page 177: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

CHM-2B

Unit 1 Date 08-11-92 Time After 1530

pH: * * IF CAUSTIC IS ADDED VALUE MUST BE CALCULTED

Spec Cond:

Boron: * * CONTACT SIMULATOR FOR CONCENTRATION

Chloride:

Floride:

Susp. Sol:

Dissolved Oxygen:

RADIOCHEMISTRY DATA

Gross Beta

Gross Gamma 5.95 E3

Ar-41 Na-24

Kr-85m 8.47 Rb-88 13.84

Kr-87 4.63 Co-58

Kr-88 12.72 Cs-134

Xe-133 2.72 E3 Cs-137 1.46

Xe-133m 2.82 E3 Cs-138 4.36

Xe-135 35.6

Xe-135m 2.56 E2

1-131 19.88

1-132 22.3

1-133 21.1

1-134. 4.8

1-135 8.9

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CHM-2B

Unit 1 Date 08-11-92 Time After 1530

pH: * * IF CAUSTIC IS ADDED VALUE MUST BE CALCULTED

Spec Cond:

Boron: * * CONTACT SIMULATOR FOR CONCENTRATION

Chloride:

Floride:

Susp. Sol:

Dissolved Oxygen:

RADIOCHEMISTRY DATA

Gross Beta

Gross Gamma 5.95 E3

Ar-41 Na-24

Kr-85m 8.47 Rb-88 13.84

Kr-87 4.63 Co-58

Kr-88 12.72 Cs-134

Xe-133 2.72 E3 Cs-137 1.46

Xe-133m 2.82 E3 Cs-138 4.36

Xe-135 35.6

Xe-135m 2.56 E2

1-131 19.88

1-132 22.3

1-133 21.1

1-134 4.8

1-135 8.9

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SIMULATOR DATA

Page 180: TABLE OF CONTENTS · FEMA RAC briefing at the EOF News Center. August I1, 1992 0730 Exercise begins. 1330 Day I of excrcise is terminated. 1430 Day 3 of exercise begins. 1700 Day

04-06-92 18:50:04

OCONEE NUCLEAR STATION, UNIT ONE

7 PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF ON

A2 REACTOR COOLANT PUMP, ON/OFF ON

Bl REACTOR COOLANT PUMP, ON/OFF ON

B2 REACTOR COOLANT PUMP, ON/OFF ON

A REACTOR COOLANT LOOP, HOT LEG TEMP 601.99 DEG F OK

B REACTOR COOLANT LOOP, HOT LEG TEMP 601.99 DEG F OK

Al REACTOR COOLANT LOOP, COLD LEG TEMP 555.96 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 555.96 DEG F OK

B1 REACTOR COOLANT LOOP, COLD LEG TEMP 555.88 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 555.88 DEG F OK

ACTOR COOLANT LOOP,SAT TEMP MARGIN 25.70 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 25.70 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 2157.24 PSIG OK

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 0.0 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 46.501 uAMPS

POWER RANGE NEUTRON FLUX 99.42 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 608.37 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 616.33 DEG F OK

INCORE THERMOCOUPLE M9, TEMPERATURE 608.17 DEG F OK

INCORE THERMOCOUPLE F13, TEMPERATURE 617.36 DEG F OK

O RE THERMOCOUPLE B7, TEMPERATURE 609.68 DEG F OK

INCORE THERMOCOUPLE C6, TEMPERATURE 617.33 DEG F OK

REACTOR BUILDING LEVEL (WATER) 0.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

EACTOR COOLANT LOOP, HOT LEG LEVEL 597.00 INCHES OK

,TOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 18:50:08

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 261.19 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 257.31 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 907.92 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 907.96 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 5307414.50 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 5322691.50 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

C HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

LETDOWN FLOW RATE 63.58 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

TED WATER STORAGE TANK LEVEL 48.64 FEET OK

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I

Name:Date: / /_

Arc- of review: Recovery

(Chcek One) Exercise objective to be reviewed: Adequate Inadequate*

IIb. Demonstrate the ability to take post-accident liqnid samples under accident conditions.

Ie. Demonstrate the ability to take post-accident gascons samples under accident conditions.

Note: These objectives will he tested on Day 2 of the [xcrcise.

*Note: Expand on any item(s) marked "InadeqIate."

Evaluator signature

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04-06-92 18:50:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 122.81 DEG F OK

REACTOR BUILDING DOME AREA, TEMPERATURE 126.58 DEG F OK

REACTOR BUILDING NORMAL SUMP LEVEL 12.48 INCHES OK

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.00 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

*** The following ERRORS were found ****

Error accessing Node-OC4201 Tag-SSA1906 Field-ACV Error accessing Node-OC4201 Tag-A1902 Field-A CUALM

ror accessing Node-OC4201 Tag-SSA1907 Field-ACV r accessing Node-OC4201 Tag-A1903 Field-A CUALM

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04-06-92 19:00:04

OCONEE NUCLEAR STATION, UNIT ONE

PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF ON

B1 REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF ON

A REACTOR COOLANT LOOP, HOT LEG TEMP 622.03 DEG F HIHI

B REACTOR COOLANT LOOP, HOT LEG TEMP 622.01 DEG F HIHI

Al REACTOR COOLANT LOOP, COLD LEG TEMP 556.46 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 565.30 DEG F OK

Bl REACTOR COOLANT LOOP, COLD LEG TEMP 557.16 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 565.37 DEG F OK

CTOR COOLANT LOOP,SAT TEMP MARGIN 19.19 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 19.21 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 2370.11 PSIG HIHI

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 0.0 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 29.913 uAMPS

POWER RANGE NEUTRON FLUX 64.19 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 628.28 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 634.68 DEG F HIHI

INCORE THERMOCOUPLE M9, TEMPERATURE 628.09 DEG F HIHI

INCORE THERMOCOUPLE F13, TEMPERATURE 635.68 DEG F HIHI

E THERMOCOUPLE B7, TEMPERATURE 629.27 DEG F HIHI

INCORE THERMOCOUPLE C6, TEMPERATURE 635.69 DEG F HIHI

REACTOR BUILDING LEVEL (WATER) 0.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

*TEACTOR COOLANT LOOP, HOT LEG LEVEL 597.00 INCHES OK

R TOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 19:00:09

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 203.70 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 195.92 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 1082.34 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 1082.42 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 4312515.00 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 4289495.00 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

W RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

C HIGH PRESSURE INJECTION PUMP, ON/OFF ON

LETDOWN FLOW RATE 66.68 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 208.22 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 218.75 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

-B RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

TED WATER STORAGE TANK LEVEL 48.64 FEET OK

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04-06-92 19:00:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 125.38 DEG F OK

REACTOR BUILDING DOME AREA, TEMPERATURE 128.91 DEG F OK

REACTOR BUILDING NORMAL SUMP LEVEL 12.48 INCHES OK

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.00 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

*** The following ERRORS were found ****

Error accessing Node-OC4201 Tag-SSA1906 Field-ACV Error accessing Node-OC4201 Tag-A1902 Field-A CUALM

r accessing Node-OC4201 Tag-SSA1907 Field-ACV 7 accessing Node-OC4201 Tag-A1903 Field-A CUALM

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04-06-92 19:10:04

OCONEE NUCLEAR STATION, UNIT ONE

PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF ON

B1 REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF ON

A REACTOR COOLANT LOOP, HOT LEG TEMP 555.23 DEG F OK

B REACTOR COOLANT LOOP, HOT LEG TEMP 555.23 DEG F OK

Al REACTOR COOLANT LOOP, COLD LEG TEMP 553.11 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 553.30 DEG F OK

B1 REACTOR COOLANT LOOP, COLD LEG TEMP 553.05 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 553.24 DEG F OK . ACTOR COOLANT LOOP,SAT TEMP MARGIN 47.71 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 47.72 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 1802.81 PSIG OK

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 338204.0 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 0.000 uAMPS

POWER RANGE NEUTRON FLUX 0.00 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 555.30 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 553.98 DEG F OK

INCORE THERMOCOUPLE M9, TEMPERATURE 554.25 DEG F OK

INCORE THERMOCOUPLE F13, TEMPERATURE 556.14 DEG F OK

RE THERMOCOUPLE B7, TEMPERATURE 555.34 DEG F OK

INCORE THERMOCOUPLE C6, TEMPERATURE 556.93 DEG F OK

REACTOR BUILDING LEVEL (WATER) 0.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

'CTOR COOLANT LOOP, HOT LEG LEVEL 597.00 INCHES OK

Rn.cTOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 19:10:09

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 62.90 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 62.58 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 1010.43 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 1010.13 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 3218.37 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 3218.37 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

C HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

LETDOWN FLOW RATE 87.57 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

\TED WATER STORAGE TANK LEVEL 48.64 FEET OK

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04-06-92 19:10:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 128.79 DEG F OK

REACTOR BUILDING DOME AREA, TEMPERATURE 132.49 DEG F HIHI

REACTOR BUILDING NORMAL SUMP LEVEL 12.49 INCHES OK

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.00 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

**** The following ERRORS were found **** Error accessing Node-OC4201 Tag-SSA1906 Field-ACV

Error accessing Node-OC4201 Tag-A1902 Field-ACUALM

ror accessing Node-OC4201 Tag-SSA1907 Field-ACV

r accessing Node-OC4201 Tag-A1903 Field-ACUALM

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04-06-92 19:20:03

OCONEE NUCLEAR STATION, UNIT ONE

PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF OFF

B1 REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF OFF

A REACTOR COOLANT LOOP, HOT LEG TEMP 561.39 DEG F OK

B REACTOR COOLANT LOOP, HOT LEG TEMP 561.05 DEG F OK

Al REACTOR COOLANT LOOP, COLD LEG TEMP 553.41 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 552.58 DEG F OK

Bl REACTOR COOLANT LOOP, COLD LEG TEMP 553.25 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 552.24 DEG F OK . ICTOR COOLANT LOOP,SAT TEMP MARGIN 51.10 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 51.42 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 1928.18 PSIG OK

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 244.4 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 0.000 uAMPS

POWER RANGE NEUTRON FLUX 0.00 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 564.11 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 563.16 DEG F OK

INCORE THERMOCOUPLE M9, TEMPERATURE 563.38 DEG F OK

INCORE THERMOCOUPLE F13, TEMPERATURE 565.04 DEG F OK

RE THERMOCOUPLE B7, TEMPERATURE 564.25 DEG F OK

INCORE THERMOCOUPLE C6, TEMPERATURE 565.70 DEG F OK

REACTOR BUILDING LEVEL (WATER) 0.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK . EACTOR COOLANT LOOP, HOT LEG LEVEL 597.00 INCHES OK

.'TOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 19:20:08

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 33.83 INCHES OK

B STEAM GENERATOR LEVEL,.FULL RANGE 29.01 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 1005.66 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 1002.49 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 0.00 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 0.00 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

W * RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF ON

C HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

LETDOWN FLOW RATE 0.00 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

LTED WATER STORAGE TANK LEVEL 48.64 FEET OK

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04-06-92 19:20:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 134.21 DEG F OK

REACTOR BUILDING DOME AREA, TEMPERATURE 137.85 DEG F HIHI

REACTOR BUILDING NORMAL SUMP LEVEL 12.50 INCHES OK

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.00 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

**** The following ERRORS were found **** Error accessing Node-OC4201 Tag-SSA1906 Field-ACV Error accessing Node-OC4201 Tag-A1902 Field-ACUALM

-nr accessing Node-OC4201 Tag-SSA1907 Field-A_CV r accessing Node-OC4201 Tag-A1903 Field-ACUALM

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04-06-92 1 00

OCONEE NUCLEAR STATION, UNIT ONE

PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF OFF

Bl REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF OFF

A REACTOR COOLANT LOOP, HOT LEG TEMP 592.70 DEG F OK

B REACTOR COOLANT LOOP, HOT LEG TEMP 587.75 DEG F OK

Al REACTOR COOLANT LOOP, COLD LEG TEMP 565.84 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 565.85 DEG F OK

B1 REACTOR COOLANT LOOP, COLD LEG TEMP 563.05 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 563.05 DEG F OK

* CTOR COOLANT LOOP,SAT TEMP MARGIN 0.00 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 0.00 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 1443.21 PSIG LOLO

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 72.2 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 0.000 uAMPS

POWER RANGE NEUTRON FLUX 0.00 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 590.91 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 589.90 DEG F OK

INCORE THERMOCOUPLE M9, TEMPERATURE 590.10 DEG F OK

INCORE THERMOCOUPLE F13, TEMPERATURE 591.63 DEG F OK

RE THERMOCOUPLE B7, TEMPERATURE 590.84 DEG F OK

INCORE THERMOCOUPLE C6, TEMPERATURE 592.22 DEG F OK

REACTOR BUILDING LEVEL (WATER) 0.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

* FACTOR COOLANT LOOP, HOT LEG LEVEL 589.29 INCHES OK

K ;rOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 19:30:09

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 31.58 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 27.46 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 1033.35 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 1018.14 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 0.00 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 0.00 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

W RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF ON

C HIGH PRESSURE INJECTION PUMP, ON/OFF ON

LETDOWN FLOW RATE 0.00 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW -0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW -0.00 GPM LOLO

TED WATER STORAGE TANK LEVEL 48.64 FEET OK

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04-06-92 19:30:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 212.40 DEG F HIHI

REACTOR BUILDING DOME AREA, TEMPERATURE 215.43 DEG F HIHI

REACTOR BUILDING NORMAL SUMP LEVEL 24.00 INCHES HIHI

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.00 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

**** The following ERRORS were found **** Error accessing Node-OC4201 Tag-SSA1906 Field-A_CV Error accessing Node-OC4201 Tag-A1902 Field-ACUALM

* r accessing Node-OC4201 Tag-SSA1907 Field-A CV 7 accessing Node-OC4201 Tag-A1903 Field-ACUALM

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04-06-92 19:40:04

OCONEE NUCLEAR STATION, UNIT ONE

PIRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF OFF

B1 REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF OFF

A REACTOR COOLANT LOOP, HOT LEG TEMP 580.33 DEG F OK

B REACTOR COOLANT LOOP, HOT LEG TEMP 580.12 DEG F OK

Al REACTOR COOLANT LOOP, COLD LEG TEMP 540.96 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 540.96 DEG F OK

BI REACTOR COOLANT LOOP, COLD LEG TEMP 540.96 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 540.96 DEG F OK

ACTOR COOLANT LOOP,SAT TEMP MARGIN 0.00 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN 0.00 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 952.05 PSIG LOLO

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 438.5 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 0.000 uAMPS

POWER RANGE NEUTRON FLUX 0.00 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 569.16 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 550.15 DEG F OK

INCORE THERMOCOUPLE M9, TEMPERATURE 550.14 DEG F OK

INCORE THERMOCOUPLE F13, TEMPERATURE 550.77 DEG F OK

RE THERMOCOUPLE B7, TEMPERATURE 550.03 DEG F OK

INCORE THERMOCOUPLE C6, TEMPERATURE 550.87 DEG F OK

REACTOR BUILDING LEVEL (WATER) 3.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

- ACTOR COOLANT LOOP, HOT LEG LEVEL

0.51 INCHES OK

q-.2TOR VESSEL HEAD LEVEL. 0.00 INCHES OK

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04-06-92 19:40:09

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 25.67 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 22.98 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 1043.82 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 933.73 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 0.44 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 0.44 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

B HIGH PRESSURE INJECTION PUMP, ON/OFF ON

C HIGH PRESSURE INJECTION PUMP, ON/OFF OFF

LETDOWN FLOW RATE 0.00 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 0.00 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW -0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW -0.00 GPM LOLO

TED WATER STORAGE TANK LEVEL 48.64 FEET OK

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04-06-92 19:40:11

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 283.18 DEG F HIHI

REACTOR BUILDING DOME AREA, TEMPERATURE 285.44 DEG F HIHI

REACTOR BUILDING NORMAL SUMP LEVEL 24.00 INCHES HIHI

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.25 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 3.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 % OK

*** The following ERRORS were found ****

Error accessing Node-OC4201 Tag-SSA1906 Field-ACV

Error accessing Node-OC4201 Tag-A1902 Field-ACUALM -r accessing Node-OC4201 Tag-SSA1907 Field-A CV

r accessing Node-OC4201 Tag-A1903 Field-ACUALM

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04-06-92 19:50:03

OCONEE NUCLEAR STATION, UNIT ONE

PRIMARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

Al REACTOR COOLANT PUMP, ON/OFF OFF

A2 REACTOR COOLANT PUMP, ON/OFF OFF

B1 REACTOR COOLANT PUMP, ON/OFF OFF

B2 REACTOR COOLANT PUMP, ON/OFF OFF

A REACTOR COOLANT LOOP, HOT LEG TEMP 726.53 DEG F HIHI

B REACTOR COOLANT LOOP, HOT LEG TEMP 773.31 DEG F HIHI

Al REACTOR COOLANT LOOP, COLD LEG TEMP 533.19 DEG F OK

A2 REACTOR COOLANT LOOP, COLD LEG TEMP 555.08 DEG F OK

B1 REACTOR COOLANT LOOP, COLD LEG TEMP 745.16 DEG F OK

B2 REACTOR COOLANT LOOP, COLD LEG TEMP 476.57 DEG F OK . -ACTOR COOLANT LOOP,SAT TEMP MARGIN -196.36 DEG F OK

B REACTOR COOLANT LOOP,SAT TEMP MARGIN -243.15 DEG F OK

A REACTOR COOLANT LOOP, SYSTEM PRESS 558.51 PSIG LOLO

PRESSURIZER LEVEL 0.00 INCHES LOLO

STARTUP RANGE NEUTRON FLUX 506.1 CT/SEC

INTERMEDIATE RANGE NEUTRON FLUX 0.000 uAMPS

POWER RANGE NEUTRON FLUX 0.00 % FP

A REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

B REACTOR COOLANT LOOP, FLOW ??????????????xE3 LBM/HR ?????

AVERAGE CORE TEMPERATURE 889.59 DEG F OK

INCORE THERMOCOUPLE H9, TEMPERATURE 889.29 DEG F HIHI

INCORE THERMOCOUPLE M9, TEMPERATURE 889.29 DEG F HIHI

INCORE THERMOCOUPLE F13, TEMPERATURE 889.94 DEG F HIHI

IRE THERMOCOUPLE B7, TEMPERATURE 889.21 DEG F HIHI

INCORE THERMOCOUPLE C6, TEMPERATURE 890.05 DEG F HIHI

REACTOR BUILDING LEVEL (WATER) 3.00 FEET OK

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A REACTOR COOLANT LOOP, HOT LEG LEVEL 0.00 INCHES OK

0 ACTOR COOLANT LOOP, HOT LEG LEVEL

0.60 INCHES OK

W2TOR VESSEL HEAD LEVEL 0.00 INCHES OK

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04-06-92 19:50:09

OCONEE NUCLEAR STATION, UNIT ONE

SECONDARY COOLANT SYSTEM, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

A STEAM GENERATOR LEVEL, FULL RANGE 55.62 INCHES OK

B STEAM GENERATOR LEVEL, FULL RANGE 43.09 INCHES OK

A STEAM GENERATOR OUTLET PRESSURE 774.30 PSIG OK

B STEAM GENERATOR OUTLET PRESSURE 722.47 PSIG OK

A STEAM GENERATOR FEEDWATER FLOW 0.43 xE3 LBM/HR OK

B STEAM GENERATOR FEEDWATER FLOW 0.43 xE3 LBM/HR OK

A STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

B STEAM GENERATOR EMER FEEDWATER FLOW 0.00 GPM OK

SAFETY INJECTION SYSTEMS, SIMULATED

RIPTION VALUE ENGRNG VALUE UNITS QUALITY

A LOW PRESSURE INJECTION PUMP, ON/OFF OFF

B LOW PRESSURE INJECTION PUMP, ON/OFF OFF

C LOW PRESSURE INJECTION PUMP, ON/OFF OFF

A HIGH PRESSURE INJECTION PUMP, ON/OFF ON

B HIGH PRESSURE INJECTION PUMP, ON/OFF ON

C HIGH PRESSURE INJECTION PUMP, ON/OFF ON

LETDOWN FLOW RATE 0.00 GPM OK

A RC LOOP, HIGH PRESSURE INJ FLOW 672.19 GPM OK

B RC LOOP, HIGH PRESSURE INJ FLOW 459.10 GPM OK

A RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

B RC LOOP, LOW PRESSURE INJ FLOW 0.00 GPM LOLO

TED WATER STORAGE TANK LEVEL 47.20 FEET OK

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04-06-92 19:50:10

OCONEE NUCLEAR STATION, UNIT ONE

CONTAINMENT SYSTEMS, SIMULATED

DESCRIPTION VALUE ENGRNG VALUE UNITS QUALITY

REACTOR BUILDING PRESSURE 0.00 PSIG OK

CONTROL ROD DRIVE AREA, TEMPERATURE 245.38 DEG F HIHI

REACTOR BUILDING DOME AREA, TEMPERATURE 247.54 DEG F HIHI

REACTOR BUILDING NORMAL SUMP LEVEL 24.00 INCHES HIHI

REACTOR BUILDING EMERGENCY SUMP LEVEL 0.25 FEET OK

A REACTOR BUILDING CAVITY WATER LEVEL 3.00 FEET OK

B REACTOR BUILDING CAVITY WATER LEVEL 0.00 FEET OK

REACTOR BUILDING HYDROGEN CONCENTRATION 0.00 OK

**** The following ERRORS were found **** Error accessing Node-OC4201 Tag-SSA1906 Field-A CV

Error accessing Node-OC4201 Tag-A1902 Field-A CUALM

-nr accessing Node-OC4201 Tag-SSA1907 Field-ACV accessing Node-UC4201 Tag-A1903 Field-ACUALM

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CRITIQUE INFORMATION

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CRITIQUE

Critiques should serve as a feedback mechanism to identify and correct Faults discovered during the exercise. The discussions held by key players and controller/cvaluators during the critiques are an opportunity for integrating all comments and developing an accurate overall picture of performance during an exercise. The written logs and comments of each

controller/evaluator Will provide valuable information for later evaluation. However, each individual is capable of viewing only a small portion of an entire exercise and, in some

cases, views only a small portion of a particular task. The critiques serve to clear up viewpoints, and help participants put all of the comments in perspective.

Process

Following the exercise, the lead controller/evaluntor from each section/group will meet with their exercise participants. Attending also will be the additional evaluators from the

section and the Superintendent/Section Manager for that group. The group then will review their participation in the exercise with feedback from playcrs and evaluators. The

lead controller should then work with group iembers to determine if the exercise

objectives were adequately met, and to ensure action items are written for objectives that were not met. Additional action items may also be generated for areas where

improvement is needed. The lead controller should compile all evaluation sheets and action items/good practices for the group making sure that no misunderstandings or misconceptions have taken place.

Controller Critique

The Exercise Director will lead the meeting. The Lead Controller from each group will be the spokesperson for that group. The lead controller should discuss any objectives in

his/her area that were not met and why. Then, each action item should be discussed.

(Good practices may be discussed if time permits). Each item presented will be open for discussion. Any controller aware of any information that could change or nullify an item should present the information to the group. At the end of the critique, the Exercise

Director may ask that certain controllers attend the NRC critique, particularly if significant problems were identified in their area of evaluation.

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NRC Critique

Players Response:

The Superintendent/Section Manager will be the spokesperson at the players critique for their section. The critique should be concise, orderly and represented by all factions of the Emergency Response Organization.

Controller Response:

The Exercise Director will be the spokesperson highlighting problems identified during the exercise. If the problem was identified by the Pliaycr spokesperson, then that. item will not be discussed in dctail by the Excrcisc Director.

NRC Response:

NRC Team Leader would provide evaluation of the response of the Emergency Response Organization.

After the NRC critique, the Exercise Director will combine the critique comments into a critique summary and will develop an action item list. Response to any action item will require a root cause analysis to be developed to determine that the solution will indeed correct the problem. The Manager, Emergency Planning will be responsible for follow-up to ensure implementation of corrective measures.

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COMMITMENT FOR CORRECTIVE ACTION FORM

* **** * ***** ************************ ***** ******* *** ** *********************,

DATE

1D NUMBER - COMPLIANCE CONTACT

ASSIGNED TO - RESPONSIBILITY NUMBER

DOCUMENT ID - PIR SERIAL NO.

COMMITMENT MADE TO - DATE DUE

DESCRIPTION

***********************************************

SECTION II

If a date the commitment should be completed by was not provided in

the date due above, please enter a target date here and initial.

Compliance

Target Date Initial Posted/Date:

RETURN TO COMPLIANCE WITHIN 10 WORKING DAYS OF RECEIPT SETTING THE

TARGET DATE

SECTION III

When corrective action has been completed, provide a short

description of the action taken: (Approved by Section Head)

Date Completed

NOTE: If the commitment will not be completed by the date set, provide a

letter stating why the commitment will not be met, as well as a

new date the commitment is to be completed by. This letter must be

approved by the group superintendent.

SIGNED: __________________ DATE:

APPROVED: DATE: ** RETURN TO COMPLIANCE AFTER COMPLETING SECTION III

POSTED: DATE:

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DRILL or EXERCISE GOOD PRACTICE

To:

Drill or Exercise Date: / / Station:

Finding:

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PLAYERS

The success of the drill is largclV dependent on player reaction and knowledge of the emergency plan and procedures. Some information and situations affecting player reaction will exist at the time the drill begins (initial conditions). Most of the information will be introduced by controllers/evaluators throughout the course of the drill. Players are responsible for initiating actions according to the procedures, responsibilitics. and tasks outlined for their particular function in the emergency plan and implementing procedures.

Players should react to scenario information as it is presented to them. Players shall not critique and comment on the scenario data or information during the drill. However, this does not mean that questions related to data clarification cannot be asked if nceded.

Players are identified by badges or armbands indentifying their positions.

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CONTROLLERS/EVALUATORS

Controllers/Evaluators are assigned to specific locations and/or groups. Responsibilities for Controllers/Evaluators include:

1. Maintaining action according to the scenario 2. Providing input messages and data 3. Observing players as they work in their specialized functions 4. Compiling observations and judgcments onto the evaluation forms

5. Generating 'good practices' and/or 'actions items' as appropriate

Controllers/Evaluators will provide simulated plant parameters and information in the form of drill messages to appropriate players throughout the drill. They will observe player responses to the messages and (ata sheets. Each Controller/Evaluator should gencrate a chronology of events observed throughout the drill. Following the drill. evaluation sheets should be completed and action

items/good practices devcloped.

CONTROLLER/EVALUATOR ASSIGNMENTS

Exercise Director Simulator Control Room 2 TSC Overall I TSC Offsite Communications I TSC Dose Assessment I TSC Reactor Engineering I OSC Overall I OSC Rad. Protection 5 OSC Operations 5 OSC Chemistry 2 OSC Maintenance 2 l&E 3 Field Monitoring Teams 5 EOF Overall I Radiological Assessment I Offsite Communications I Security I Fire Protection I

Note: Other controller/cvaluators may be added, as needed.

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Name: Date: / /

Area of review: Simulator Control Room

(Check One)

Exercise objective to be reviewed: Adequate Inadequate*

Aa. Demonstrate the ability to alert, notify, and staff the TSC, OSC and EOF after declaring an Alert or higher emergency classification.

Ac. Demonstrate precise and clear transfer of responsibility from the Shift Supervisor in the Control Room to the Emergency Coordinator in the TSC.

Ac. Demonstrate the ability to assess the incident and provide mitigation strategies.

Ba. Demonstrate the ability to declare emergency classification in accordance with procedures.

Bb. Demonstrate the ability to notify the State and the countics within 15 minutes after declaring an emergency or after changing the emergency classification.

Be. Demonstrate proper use of the notification form and authentication methodology for messages transmitted to States and Counties.

Ca. Test communications equipment among on-site emergency facilities including plant extensions, intercoms, and on-site radio systems.

Test primary off-site communications equipment to the County and State warning points, and to NRC including the Selective Signaling System and the NRC Emergency Notification System.

Co. Demonstrate the ability to notify NRC not later than I hour after declaring one of the emergency classes.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature

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Name:Date: / /

Area of review: TSC Overall (Check One)

Exercise objective to be reviewed: Adequate Inadcquatc*

Aa. Demonstrate the ability to alert, notify, and staff the TSC, OSC and EOF after deelaring an Alert or higher emergency classification.

Ac. Demonstrate precise and clear transfer of responsibility from the Shift Supervisor in the

Control Room to the Emergency Coordinator in the TSC.

Ac. Demonstrate the ability to assess the incident and provide mitigation strategies.

Ba. Demonstrate the ability to declare emcrgency classification in accordance with procedures.

Bh. Demonstrate the ability to notify the State and the countics within 15 minutes after declaring an cmergency or after changing the emergency classification.

Ca. Test communications equipment among oi-site emergency facilities including plant extensions, intercons, and on-site radio systems.

Cc. Test adequncy and operability of emergency equipment/ supplies.

Ch. Demonstrate the ability to communicate with al appropriate locations, organizations, and field personnel.

Cd. Demonstrate the ability to provide current plant data to appropriate locations, organizations, and field personnel.

Da. Demonstrate assembly of station personnel within 30 minutes in a simulated emergency and provide accountability for any not present at the assembly locations.

Dc. Demonstrate the ability to effect an orderly evacuation of non-essential personnel.

* Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature

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Name:_ate: / /

Area of review: Off-site Conunnications (Incildes TSC Ind EOF)

(Check One)

Exercise objective to be reviewed: Adequate Inadcquate*

Bb. Demonstrate the ability to notify the State and the countics within 15 minutes after declaring an emergency or after changing the emergency

classification.

Bc. Demonstrate proper use of the notification form and anthentication methodology for messages transmitted

to States and Counties.

Cb. Demonstrate the ability to communicate with all appropriate

locations, organizations, and Field personnel.

Ce. Evaluate the adequacy and operability of emergency

equipment and supplies.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature

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Name: Date: / /

Arca of review: TSC Reactor Engineering

(Check One)

Excrcise objective to be reviewed: Adequate Inadequate*

Ac. Demonstrate the ability to assess the incident and determine

mitigation strategies.

Cd. Demonstrate the ability to provide enrrent plant data

to appropriate locations. organizations, and field

personiel.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature:

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Name:Date: / /

Area of review: OSC Overall

(Check One)

Excrcisc obicctive to be reviewed: Adequate Inadcquate'

An. Demonstrate the ability to staff the OSC facility

after declaring ain Alert or higher emergey class.

Ac. Demonstrate the ability to assess the incident and provide

mitigation strategies.

Ca. Test communications equiipment among on-site eiergency

facilities including plant extensions and intercoms.

Cb. Demonstrate the ability to comintinicate with all appropriate

locations, organizations, and field personnel.

Ce. Test adequacy and operability of emergency cqIipment/

supplies.

D). Demonstrate the ability to locate unaccounted personnel

determined by the site assembly. (This accountability will

be tested only if personnel are determined to le unaccouited

inside the protected area.)

Fa. Demonstrate the ability to monitor and control emergency

worker exposure.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature.

0

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Name: Date: / /

Arca of review: On-site Radiation Monitoring

(Check One)

Exercise objective to be reviewed: Adequate Inadequate*

Ce. Test adequacy and operability of emergency c(uipment/ supplies.

Ea. Demonstrate appropriate equipment and procedures for determining ambient radiation levels.

Demonstrate appropriate equipment and procedures for measurement of airborne radioiodine concentrations.

Demonstrate the ability to monitor and control worker

exposure.

*Note: Expand on any item(s) marked "Inadequiate."

Evaluator Signature

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Name: Date: / /

Area of rcvicw: ()SC Maintenance and OSC I&E (form to be ised by hoth groups)

(Check One)

Excrcise obicctive to be reviewed: Adequate Inadequatc*

Ae. Demonstrate the ability to assess the incident and provide

mitigation strategies.

Cb. Demonstrate the ability to conununicate with all appropriate locations, organizations, and Field personnel.

Ea. Demonstrate the ability to monitor and control worker exposure.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature

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Name: Date: / /

Area of review: Ficld Mvlonitoring Teamns

(Check One)

Exercise objective to be reviewed: Adequate Inadequate*

Ea. Demonstrate the ability to monitor and control worker exposure.

Eb. Demonstrate the ability to mobilize teams in the 10-mile

EPZ to locate and track the plume for nobie gases and radiolodinc concentrations in a timely manner.

Demonstrate appropriate eq(uipment amid procedure for

collection, transport, and analysis of samples of soil.

vegetation, and water.

(Note: Since this exercise is anl ingestion pathway,

controllers will request no simulation for samples).

Demonstrate the ability to transmit field measurement data

to the EOF.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator signature

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Name:________________________Date: / /___

Area of review: Joint Information Confer

(Check One)

Exercise obIjective to be reviewed: Adequate Inadequate*

Ga. Demonstrate the ability to brief the media in a clear.

accurate, and timely manner.

Gb. Demonstrate the ability to provide advance coordination

of information released.

Gc. Demonstrate the ability to establish and operate rumor

control in a coordinated fashion.

*Note: Expand on any itcm(s) marked "Inadequate."

Evainator signature

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Name:__fe: / /

Area of review: Security

(Check One)

Exercise objective to be reviewed: Adequate Inadequate*

Cb. Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel.

Da. Demonstrate assembly of station personnel within 30 minutes in a simulated emergency and provide accountability for any not present at the assembly locations.

Db. Demonstrate the ability to locate unaccounted personnel determined by site assembly. (Note: This objective will

be tested only if personnel are actually reported as unaccounted during the exercise. No personnel will be staged as unaccounted.)

Dc. Demonstrate the ability to effect an ordery evacuation of non-essential personnel.

Dd. Demonstrate access control measures to the plant site and EOF.

*Note: Expand on any item(s) marked "Inadequate."

r Evaluator Signature

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Name: Date: / /

Area of review: EOF Overall

(Check One) Exercise objective to be reviewed: Adequate Inadequate*

Aa. Demonstrate the ability to alert, notify, and staff the EOF after declaring an Alert or higher emergency classification.

Ad. Demonstrate precise and clear transfer of responsibility from the Emergency Coordinator in the TSC to the EOF Director in the [OF.

Ba. Demonstrate the ability to declare emergency classification in accordance with procedures.

Bb. Demonstrate the ability to notify the Stateand the countics within 15 minutes after declaring an emergency or after changing the emergency classification.

Bc. Demonstrate proper use of the notification form and authentication methodology for messages transmitted to States and Counties.

Ca. Test primary off-site communications equipment to the County and State Emergency Operations Center.

Cd. Demonstrate the ability to provide current plant data to appropriate locations, organizations, and field personnel.

Ce. 'rest adequacy and operability of emergency eqnipment/ supplies.

Ec. Demonstrate the ability to provide timely and appropriate protective action recommendations in accordance with site procedures.

Fa. Demonstrate the ability to identify need for, request and obtain Federal assistance.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature

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Nanic:Date / /

Area of rcvicw: EOF Radiological Asscssment

(Check One) Exercise objective to be reviewed: Adequate Inadequatc*

Cb. Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel.

Ce. Test adequacy and operability of emergency equipment/supplies.

Ea. Demonstrate the ability to project offsite dose projections in accordance with site procedures.

Ec. Demonstrate the ability to project dosage to the public via ingestion pathway exposures.

Demonstrate the ability to project damage to the public based on plant and field data for public via ingestion pathway exposure.

Demonstrate the ability to provide timely and appropriate protective action recomunendations in accordance with site procedures.

*Note: Expand on any item(s) marked "Inadequate."

Evaluator Signature