table of contents · fema rac briefing at the eof news center. august i1, 1992 0730 exercise...
TRANSCRIPT
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
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
EXERCISE RULES
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.
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.
OBJECTIVES
0
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 , ,
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
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
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.
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
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
SCENARIO - SEQUENCE OF EVENTS
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.
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.
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.)
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.
* 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.
RADIOLOGICAL ASSESSMENT
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)
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
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
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.
EN:~CLOSUR1E 5
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-- 7~1!IT. 1 KCURRENT M'ET
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11D DEAY OF PPOwT0 OF E+
WELEOSE Hr. .0 ft. RELEWIT .- catainet
ENCIOSUnR 6
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[,:!..::'... 4......I CURRFENT MlET
G" L I!- Tf !. :;FEEl -- 0L~ p
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CETELINE HAL
1 5- -. 4
1. 1 2" 3,2E
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IENCLO0SUIRE 7
~::'plT .. ~TFEW .~.. TTK J L 245: 00 - 17!-FiiHT EFFLLE
CUR:RENT MET
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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
EXERCISE DATA AND MESSAGES
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.
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.
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.
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 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__
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 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
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 ___________________________________ _
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___/____
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._
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
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
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
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___
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
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.
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:
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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--
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/
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 . .
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
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/
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
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
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
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
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.
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
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.
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
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 ---
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
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
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
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
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
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
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.
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.
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.
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.
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.
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.
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.
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.
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.
* 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.
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.
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.
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.
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
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.
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
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
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.
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
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.
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.
FIELD MONITORING DATA
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(
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
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
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
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
r j- ,-~ ~
3
__________________________________________________________________________________________
4
3
I I - -
I I
-I
-
I ill I
I __
___
___
_____ ____
11.1 iii
___ -: *- _____
I:
0
____
I _____________________________________________________________
______________
6 ________
C ---- --- - .--
3
-- 4----
___ __
I ______
I ______
_____
1~~ -I. I -
-- *~L~L-:-
_____
6
I -- _____ ------ I-- ~-- - -- __ I-___
C
4- - ------f----
--
~~i**~ - -_
1ffi ________________
___ ______
----- 4----- -____
___ - ----- 4------
I - - -- - -____________
_____
I ______ I
_
'I,
__
I
I- _____________ __________ _____________________________
___________________________________
* ______________
1 ~ ' ______________ ____________
___________ _____________
_____________ II,
K - -7 ____
____ ___
*I..IIiI;II'.
____________ ___________
____________ - ____________
____________ I ____________
___________
2 ( s-cI.~s ~ III r~ ~ jt~~-I~ 1 2 3 tdl ,Ie
4
+1 -
9 1.
7
s-ti.
------------------H
7: -7 17 .______
2__
Cycle,,~ _ _ _ -tot il nh- l
METEOROLOGICAL DATA
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
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
RADIATION MONITOR DATA
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
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
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
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
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
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
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
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
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
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
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
Sheet 1 of 1
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
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.
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
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
NO AC Power Sheet 1 of ENCLOSURE 20
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
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
No AC Power Sheet I of
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
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
No AC Power Sheet I of
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
No AC Power Sheet 1 of
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
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
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_
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
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
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
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
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_
INGESTION PATHWAY DATA
Day 1 - Day of the release.
Day 1.5 - 12 hr after release
Day 2 - Day after release
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
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
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
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
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
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
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
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
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
* 0
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
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
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
* * *
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
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
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
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
* * *
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
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
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
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
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
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
Pagc 3 of4
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
Pagc 4 of 4
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
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
Pape 2 of 4
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
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
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
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
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
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
POST-ACCIDENT SAMPLING DATA
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.
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.
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
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
SIMULATOR DATA
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
CRITIQUE INFORMATION
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.
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.
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:
DRILL or EXERCISE GOOD PRACTICE
To:
Drill or Exercise Date: / / Station:
Finding:
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.
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.
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
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
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
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:
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
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
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
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
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
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
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
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