nureg-0737,suppl 1 emergency response capability ... · operating procedure (eop) upgrade,...
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.•. 8702260257 PDR ADOCK p ;
BOREG-0737 SDPPLEllEHT 1
EMERGEHC!' RESP<IllSE CAPABILITY
Prepared for:
Public Service Electric • Gas . Salem Nuclear Generating Station
units 1 • 2
870220 ------ -----., 05000272 PDR . .
GP-R-212207
January 1987
Prepared by:
General Physics Corporation 10650 Hickory Ridge Road
Columbia r MD .21044
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TABLE OF CONTENTS
SECT I ON 1 PURPOSE .•.•••••••••••••••••••••••••••••••••••••.. • ••. • •••••••• 1-1
SECTION 2 DEFINITIONS •••••••••••••••••••••••••••••••••.••••••••••••• • 2-1
SECTION 3 REGULATORY REQUIREMENTS •••••••••• ~ ••••••• -••••••••••••••••• 3-1
SECTION 4 SALEM BACKGROUND ON ERC INTEGRATION ••••••••••••••••••••••• 4-1
SECTION 5 ERC TASK ACTIVITIES AND PSE&G RESPONSIBILITIES •••••••••••• 5-1 5.1 ERC Task Activities and PSE&G Responsibilities ••••••• 5-1 5.2 Detailed Control Room Design Review (DCRDR) •••••••••• 5-1
5.2.1 DCRDR Program Plan and Team Staffing •••••••••• 5-1 5.2.2 Develop Salem-specific Human Factors
5.2.3 5.2.4 5.2.5 5.2.6 5.2.7 5.2.8
Guidelines . .........•..•............. ." ....... 5-3 Prepare for NRC Briefing and NRC Audit •••••••• 5-4 Perform Operating Experience Review ••••••••••• 5-5 Per form Control Room Survey ••• · •••••••••••••••• 5-6 Perform DCRDR Verification •••••••••••••••••••• 5-7 Assess Human Engineering Discrepancies ••••••• ~5-8 Perform HED.Reconunendation and
Resolution ...........•.....•...... · .......... 5-9 5.2.9 Schedule Control Room Modifications •••••••••• ~-10 5.2.10 Prepare DCRDR Summary Report ••••••••••••••••• 5-11
5.3 Emergency Operating Precedure (EOP) Upgrade ••••••••• 5-12 5.3.1 Prepare and Submit EOP Procedures ·
Generation Package (PGP) ••••••••••••••••••• 5-12 5.3.2 Develop Plant Specific Technical
5. 3.'. 3 5.3.4 5.3.5 5.3.6
Guidelines (PSTG) ••••••••• _ •••• ~ •••••••••••• 5-13 Perform PSTG-Verification •••••••••••••••••••• 5-14 Develop Draft EOPs ••••••••••••••••••••••••••• 5-15 Perform EOP Verification ••••••• ~·············5-16 Perform System Functions Review and
Task Analysis . ...••....•..•..... · ......•...•. 5-1 7 5.3.7 Perform DCRDR/EOP Validation ••••••••••••••••• 5-18 5.3.8 Perform EOP Modifications •••••••••••••.••••••• 5-19 5. 3. 9 Implement EOPs ••• · ••• • ••••••••••••••••••••• , •• 5-20
5.4 Regulatory Guide (R.G.) l.97 •••••••••••••• ~·········5-20 5.4.1 Prepare R.G 1.97 (Rev 2) Compliance/
Position Report •••••••••••••••••••••••••••• 5-29 5.4.2 Perform R.G. 1.97 Control Room ·
Interface ••••••••••••••••••• ~ ••••••••••••• ~5~22 5.4.3 Prepare for R.G. 1.97 NRC
. Comment/Audit ................................ s-23 .
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TABLE OF CONTENTS (continued)
5.4.4 Prepare Design Modifications for R.G. l.97••••••••••••••••••••••••••••••••··5-24
5.4.5 Procure Equipment for Instrumentation Modification .....................••......... S-24
5.4.6 Implement R. G. 1.97 Modifications •••••••• ~ •• 5-25 5.5 Emergency Response Capability Training •••••••••••••• 5-25
5.5.1 Establish Systematic Training
5.6
Requirements ••••••••••••••••••••••••••••••• 5-25 5.5.2 Develop ERC Integrated Training Plan ••••••••• 5-27 5.5.3 Develop SPDS Simulator Hardware/
5.5.4 5.5.5 Safety 5.6.l 5.6.2 5.6.3
5.6.4
5~6.5 5.6.6
Software ...••..•..•..••••••••••••...•••.•.•.. S-28 Perform.EOP Training •••••••••• ~ •••••••••••••• 5-28 Perform SPDS Operator Training ••••••••••••••• 5-29 Parameter Display System (SPDS) •••••••••••••• 5-30 Perform SPDS Functional Analysis ••••••••••••• 5-30 Perform SPDS Parameter Set Selection ••••••••• 5-31 Perpare and Submit SPDS Safety Analysis -
. Report and Implementation Plan ••••• : ••••••• 5-32 Prepare Functional Requirement
Document ••••••••••••••••••••••••••••• • ••••• 5-34 Develop Static SPDS Displays ••••••••••••••••• 5-35_ Prepare SPDS Human Factors Program and
Per~orm Review .•..••...•....•..•........... S-3.6 5.6.7 Determine Process for Signal
5.6.8 5.6.9
Validation •••••••••••••••••••.•••••••••.••• 5-37 Develop Software Design Specification •••••••• 5-38 Determine Parameter Use and ·
Proce~sing ••••••••••••••••••••••••••••••••• 5-38 5.6.10 Develop Dypamic Display Software ••••••••••••• 5-39 5.6.11 Perform SPDS Hardware Installation ••••••••••• 5-40 5.6.12 Perform SPDS Verification/Validation
(V&V) •• -•• · •••••••••••••••••••••••••••••••• • ·.S-41 S.6.13 Perform Man/Machine Validation of
SPDS Displays ••••••••••••••••••••••••••.••• 5-42 5. 6 .14 Prepare for NRC Audit •••••••••••.••••••••••••• 5-43
SECTION 6 EMERGENCY RESPONCE CAPABILITY TASK INTEGRATION •••••••••••• 6-1 . .
6.1 Task Integration Step No 11 PSTG Development for Task Integration ••.•••••••••••••••.•••••••••••••••• 6-1
6.2 Task Integration Step No 21 ERG/PSTG Functi~nal Analysis Development .......... ·_ ........•. ~ .... ~ ..... 6-3
ii
SECTION 7.0
•
TABLE OF CONTENTS (continued)
6.3 Task Integration Ste~ No 3i SPDS Parameter Set Selectioo .......................... · .......... •. 6-4
6.4 Task Integration Step No 4i control Room ijuman Factors Guideline Development ••••• · ••••••••••••••••• 6-6
6.5 Task Integration Step No Si Performing DCRDR · · and EOP Validation ••••••••••••••••••••••••••••••••• 6-7
6.6 Task Integration Step No 6i R.G. 1.97/Control Room Interface ••••••••••••••••••••••••••••••••••••• 6-a·
6.7 Task Integration Step No 7i SPDS Verification and-Validation •.•••••••••••••••••••••••••••••• ~···6-10
6.8 - Task Integration Step No Si Salem ERC Integrated
7.1 7.2 7.3 7.4 7.5
Trainirig Plan ...............•.....•............... i-11
ERC PROJECT MANAGEMENT/ORGANIZATI~ •••••••••••••••••• 7-1
ERC Project Division of Responsibility ••••••••••••••• 7-1 ERC Project Co_ordina tor ••• · ••••••• ~ ••••••••••••••••••• 7~ 2 Project Overview/Management •••••••••••••••••••••••••• 7-3 ERC Project Documentation and Reporting •••••••••••••• 7-4 E:Rc Action Tracking ..•••...••....••••.•••••• ~········7-5
iii
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SECTION 1. INTRODUCTION
1.1 Purpose
The purpose of this plan is to establish an effective means for the
integratiai of tasks necessary to meet NRC Generic Letter 82-33 (NUREG-0737
supplement 1) and to enhance control room operations for Salem Nuclear
Generating Station (Salem) Units 1 & 2. The Emergency Response Capability
(ERC) task integration will involve the Safety Parameter Display System (SPDS)
implementation, Detailed Control Room Design Review (DCRDR), Emergency
Operating Procedure (EOP) Upgrade, Regulatory Guide 1.97 implementation for
Accident Monitoring Instrumentation, systematic operating training, and the
Emergency Response Facilities (ERFs) implementation only as they relate to the
other task activities •
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SECTION 2. DEFINITIONS
2.1 Definitions
CSF Critical Safety Function
.DCRDR Detailed Control Room Design Review
EOF Emergency Operations Facility
EbPs Emergency Operating Procedures
EPP Emergency Plan Procedures
EPRI Electric Power Research Institute
Emergency Response Capability
Emergency Response Facilities
Emergency Response Facility Information
ERC
ERFs
ERFIS
ERG Emergency Respons~ Guidelines
HED Human Engineering Discrepancy
I&C Instrumentation and Coritrol.
INPO Institute of Nuclear Power· Operations
ITP Integrated Training Program
M/M Man/Machine
NLS Nuclear Licensing and Safety
NRC Nuclear Regulatory Commission
NSAC Nuclear Safety Analysis Center
NUTAC Nuclear Utility Task Action Committee
PDA Preliminary Design Assessment
PGP Procedures Generation Package
PLS Plant Staff
. PSTGs Plant Specific Technical Guidelines * PWR Pressurized Water Reactor
Salem Salem Nuclear Generating Station
SPDS safety Parametr Display System
SRO Senior Reactor Operator
TSC Technical Support Center
V&V verification arid Validation
WOG Westinghouse Owners Group
2-1
System
* Guidelines for the EOP' s ·are WOG ERG' s with a -conrparisofi. · Record developed for Salem procedures
•
SECTION 3. REGULATORY ~QUIREMENTS
3.1 Regulatory Requirements
The specific regulatory requirements for performing the ERC tasks
including integration are contained in Generic Letter 82-33, which issued
NUREG-0737 Supplement 1 entitled, "Requirements for Emergency Response
Capability." ·All other previously issued NUREGs and Regulatory Guides are
only to be used as sources of guidance for providing acceptable means of
meeting the requirements of Generic Letter 82-33.
The requirements contained in NUREG-0737 Supplement 1 replace the
qorresponding requirements in the following sections of·NUREG-0737:
I.C. l Guidance for the Evaluation and Development of Procedures for
Transients and Accidents
I.D.l Control Room Design Reviews
I.D.2 Plant Safety Parameter Display Console
iII .A. l. 2 Meteorolbgi.cal oat.a
The requirements of NUREG-0737 Supplement 1 are referenced for each of
the Salem specific requirements discussed in Section 5 of this document. In
addition, pertinent support provided byNRCand industry guidance documents is
also referenced.
Since the integration of the ERC task activities require plant specific ·
effort coordination, task completion dates could not be dictated uniformly for
all plants. Instead, Generic Letter. 82-33 allowed for scheduie negotiations
between the NRC and the licensee based on the plant specific needs of each
utility •
3-1
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The schedule requirements for Salem Nuclear Generating Station are as
follows:
Task
SPDS Safety Analysis
SPDS Operability
EOP Procedures Generation Package
EOP Implementation
DCRDR Program Plan
DCRDR Summary Report
R.G. 1. 97 Position. Report
R.G. 1.97 Implementation
ERF Completion
3-2
Schedule
Complete (submitted 1/30/84)
6/30/87
Complete (submitted 5/20/83)
· -:No'~later·~i:h.~{i_· 6. -mopt'h!s -of NRC
··:approval of·w~i-t~r~~ -i~ide Complete (submitted 2/14/83)
Complete (submitted 12/31/S3)
Complete .;. NRC SER 6/17/85
Complete - NRC SER 6/17/85
TSC Complete 12/85
OSC Complete 12/85
EOF 12/86
••
SECTION 4. SALEM NUCLEAR GENERATING STATION BACKGROUND ON ERC INTEGRATION
4 .1 Salem Background on ERC Integration
The initial ERC task integration philosophy was reflected in t~e NRC's
SECY-82-111, developed in early 1982. Based on this NRC Commission docwnent,
Salem deferred implementati6n of several activities (including SPDS
implementation and. R.G. 1.97 position report) until the final NRC integration
plan was developed. On December 17, 1982 Generic Letter 82.;..33 was issued,
which extracted the information in SECY-82-111 to develop NUREG-0737-
Supplement 1.
Generic Letter 82-33 required that by April 15, 1983, the utility's plans
and proposed schedule be submitted to the NRC for review and schedule
negotiations. On April 15, 1983 PSE&G submitted the ERC plans and proposed·
schedule for Salem Nuclear Generating Station. In addition, a complete
discussion on the background and status of each ERC task ·effqrts and the
integration process was discussed. Subsequently, the final schedule was
negotiated with the_ NRC and documented as previously discussed in Section 3 •
4-1
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SECTION 5. ERC TASK ACTIVITIES AND PSE&G· RESPONSIBILITIES
5.1 ERC Task Activities and PSE&G Responsibilities
The primary task and PSE&G Division of Responsibility involved in
implementing the ERC project tasks are discussed below. The overall
responsibility for each of the ERC projects .are discussed in section 7.1.
The requirements for performing the ERC tasks are defined by NUREG-0737
Supplement 1 and are referenced under "Requirements" in each of the following
task acti"vities. The ERC tasks activities for the emergency response
facilities (ERF's) are not discussed in this report.
5.2 Detailed Control Room Design Review (DCRDR)
5.2.1 · DCRDR Program Plan and Team Staffing - The DCRDR Program Plan
will be prepared for NRC review on the Proposed PSE&G planning·
phase, review phase, and assessment and implementation phase for
DCRDR implementation. The program will include staffing and
qualification of th.e review team, DCRDR task analysis, operating
experience review, the verification and validatfon processes, the
_control room survey", and the methodology for assessing and
resolving human engineering discrepancies. This program plan was
submitted to the NRC on 2/14/83 for review as discribed in
Confirmatory Order dated.6/12/84 and 7/26/84.
A DCRDR Review Team will be established to work together to
perform all of the required DCRDR related activities. This team
will be used throughout the review and assessment phase of the
DCRDR program. The typical review team consists of a systems
engineer, a senior reactor operator (SRO), and I&C/Electrical
engineer and a human factors specialist.
5-1
•
•
•
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5.2.1.1 Requirements - N~G-0737 Supplement 1 Section 5.2.a
states that all licensees shall submit a program plan
within two months of the start of the control room
review that describes the CRDR process.
NUREG-0737 Supplement 1 Section 5.1.b.i requires that a
qualified multidisciplinary review team and review
program be established.
5.2.1.2 PSE&G Division of Responsibility
Primary Responsibility:
• Assure Plan development and contract of DCRDR human
factors expertise. Manage and provide the team
leapership for the DCRDR efforts •
Secondary Responsibilities:
• Aid in program scoping and development and provide a
DCRDR team member as necessary.
• Operations - Provide necessary team support (SRO's)
and review DCRDR Program Plan.
• Training - Provide DCRDR team support as necessary.
5.2.1.3 Guidance
• NUREG-0700, Guidelines for CRDR, Sept. 1981
• NUREG-0800, Section 18.1, NRC SRP on DCRDR, Sept.
1984 •
5-2
• s.2.2
•
• NUREG-0801, Evaluation Creiteria for DCRDR, Oct.
1981.
Develop Salem Specific Human Factors Guidelines - Human Factors
Criteria will be developed to document the human engineering
criteria and conventions specifically applicable to the Salem
Nuclear Generating Station Control Room. All applicable
requirements will be identified in a manner that permits easy
r.eference for convenient project use. After the DCRDR, the Human
Factors Guideline will be adapted for ongoing reviews and docu
mentation of future changes to the Salem Control Rooms. This
criteria will also be applied for SPDS development on CRT
displays as discussed in Section 6.4 of this plan.
s.2.2.1 Requirements - No NUREG-0737 Supplement 1 requirements
specified.
5.2.2.2 PSE&G Division of Responsibility
Primary Responsibility:
• Develop or assure development of Human Factors
Guidelines
Secondary Responsibility:
• None identified
5.2.2.3 Guidance
• NUREG-0700, Guidelines for CRDR, Sept. 1981
5-3
• 5.2.3
•
Prepare for NRC Briefing and NRC Audit - An NRC briefing will be ·
required by the NRC upon their review of the DCRDR Program
Plan. The briefing will respond to their specifc comments on the
Program Plan.
An NRC audit or results review will be conducted by the NRC upon
submittal of the Salem Nuclear Generating Station DCRDR Summary
Report. This audit/review will analyze the results and
documentation to assure adequate resolution of identified Human
Engineering Discrepancies (HEDs).
5.2.3.l Requirements - NUREG-0737 Supplement 1 Sections
5.1.a,c,d, and e state that the NRC review of the DCRDR
Program Plan and Summary Report will result in either an
inprogress audit, preimplementation audit, or a HED
implementation review.
5.2.3.2 PSE&G Division of Responsibility
Primary Responsibility
• Coordinate NRC audit or question responses with
plant engineering.
Secondary Responsibility
• Provide technical support for NRC audit or
responses.
5.2.3.3 Guidance
• NUREG-0700, Guidelines for CRDR, Sept. 1981 •
• NUREG-0800, Section 18.1 SRP on CRDR, Sept. 1984.
5-4
• 5.2.4
•
•
Perform Operating Experience Review
The operating experience review will identify factors or
conditions that could cause and/or have previously caused human
performance problems and could be alleviated by improved human
engineering. This review will provide information on potential
problem areas by studying documented occurrences of human
engineering related problems that have occurred at Salem and at
similar plants. This will consist of a historical review (i.e.
LERs) and operator interviews.
5.2.4.1 Requirements - Even though no requirement to perform
this review is stated in NUREG-0737 Supplement 1, the
NRC has required this review in all DCRDR program plans
per NUREG-0700 •
5.2.4.2 PSE&G Division of Responsibility
Primary Responsibility:
• Conduct or direct the operating experience review
with human factors consultant support.
Secondary Responsibility:
• Operations - To participate in the operator surveys.
5.2.4.3 Guidance
e NUREG-0800, Section 18.1, SRP on CRDR, Sept. 1984.
• NUREG-0700, Guidelines for CRDR, Oct. 1981 •
5...:5
• 5.2.5
•
Perform Control Room Survey
The purpose of the Control Room ·survey is to identify
characteristics of I&C, equipment, physical layout, and environ
mental conditions that do not conform to precepts of good human
engineering practice, regardless of the particular system or
specific task requirements. This survey is accomplished by
conducting a systematic comparison of existing Control Room
design features with documented human engineering guidelines.
5.2.S.l Requirements - NUREG-0737 Supplement 1 Section 5.1.b.iv
states that a control room survey will be conducted to
identify deviations from accepted human factors
principles.
5.2.S.2 PSE&G Division of Responsibility
Primary Responsibility:
• Assure proper conduct of control room survey along
with providing appropriate PSE&G and human factors
exper~lse~
Secondary Responsibility:
• Provide historical preliminary design assessment
input and integration coordination •.
5.2.5.3 Guidance
• NUREG-0800, Section 18.i \
• NUREG-0700, Guidelines for CRDR, Sept. 1981
5-6
5.2.6
-- -- ----------~-:------------------
Perform DCRDR Verification
The DCRDR Verification is to systematically verify that the I&C
identified in the Task Analysis as being required by the operator
are present in the Control Room and effectively designed to
support correct task performance.
5. 2. 6.1 Requirements - NUREG-0737 Supplement l Section 5. Lb. iii
states that the display and control requirements will be
compared with the inventory to identify missing displays -
and controls. Para. 5.Ld requires that selected design
improvements be verified to assure that no new HEDs are
created.
5.2.6.2 PSE&G Division of Responsibility
Primary Responsibility
• Conduct DCRDR Verification along with human factors
consultant support.
_Secondary Responsibility
• None identified.
s. 2. 6. 3, Guidance'
• NUREG-0800, Section 18.l
• NUREG-0700, Guidelines for CRDR, Sept~ 1981
5-7
s.2.1
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Assess Human Engineering Discrepancies
Upon identification of the Human Engineering Discrepancies
(HEDs), they will be assessed for their relative importance to
plant safety and operation. This assessment is accomplished by
analyzing and eval ua t;ing the problems that~ could arise from the.
failure to correct the discrepancy. Each HED must be categorized
for later consideration for resolution.
S.2.7.1 Requirements - NUREG-0737 Supplement 1 Section 5.1.c
states that assessment of HEDs based on significance
must be performed.
5.2.7.2 PSE&G Division of Responsibility
Primary Repsonsibility:
• Assure (and participate in) HED assessment with
human factors consultant support.
Secondary Responsibility:
e Training/Operations Participate in HED assessment
process.
S.2.7.3 Guidance
e NUREG-0801.
e - NUREG-0700 •
5-8
5.2.8
•
Perform HED Recommendation and Resolution
Upon final assessment of all HED~, the recoinmended resolutions,
if.any, .must be determined. Resolution or the extent of
corrective action is dependent on the level of safety
significance and overall control room modification difficulty.
In addition, the recommended HED resolutions must be evaluted to
assure that no new deviations will result from the improvement.
5.2.8.l Requirements - NURE_G-0737 Supplement 1 Section 5.1.c
states that design improvements will be selected to.
correct analyzed discrepancies, Section 5.1.d states
that recommended improvements will not create new
discrepancies on unreviewed safety questions and that
they should be coordinated with other control room
improvements (i.e. 1 R.G. 1:97 and NUREG-0737).
5.2.8.2 PSE&G Division of Responsibility
Primary Responsibility:
• Assure and participate in the HED resolution process
with support from a human factors specialist.
Secondary Responsibility:
• Training/Operations
process.
S.2.8.3 Guidance
e NUREG-0801.
e NUREG-0700.
5-9
Participate in HED resolution.
• 5.2.9 Schedule Control Room Modifications._ During.implementation
scheduling, approved modifications to resolve HEDs will be
integrated with other enhancement programs. These changes will
be scheduled consitent with PSE&G existing work scheduling
program, with consideration given the possible HED safety
consequence, plant operating status, procurement time, and plant
outages. Modifications that can be performed by simple
enhancements will be performed expeditiously.
5.2.9.l Requirements - NUREG-0737 Supplement l Section 5.1.c
states that improvements that can be accomplished with
an enhancement program should be done promptly. Section
5.1.d. states that improvements should be coordinated
with other changes resulting from other improvement
programs such as SPDS, R.G. 1.97, operator training,
etc.
5.2.9.2 PSE&G Division of Responsibility
Primary Responsibility:
• Determine initial schedule for approved HED
modification and prepare or assure preparation of
necessary design change packages.
Secondary Responsibility:
• Coordinate modification scheduling with other
improvement programs and negotiate final schedule
with the. NRC.
• Assure modification scheduling is consistent with
available manpower, budget and outages.
5-10
•
5.-2. 9. 3 Guidance
• NUREG-0700
5.2.10 Prepare DCRDR sununary Report - At the completion of the DCRDR, a
Final Summary Report will be prepared for submittal to the.NRC
for review and comment. This report will document in summary
form the processes and activities utilized in the DCRDR. Any
departures from the methodologies described in .the Program Plan
will be noted and justified.
The Final Summary Report will also describe the results of the
DCRDR Review Phase. All HEDs identified during the DCRDR will be
included, along with the determinations for correction and/or
resolution for each HED. A proposed implementation schedule will
be provided.
5.2.10.1 Requirements - NUREG-0737 Supplement l Section 5~2.b
states that all licensees shall submit a summary report
of the completed review outlining proposed control room
changes including their schedule for implementation.
Additionally, summa~y justification for HEDs with no or
only partial correction will be provided.
5.2.10.2 PSE&G Division of Responsibility
Primary Responsibility:
• Prepare Final Summary Report for submittal to the
NRC.
Secondary Responsibility:
• Licensing - Review and submit report to NRC for
review.
.5-11
5.2.10.3 Guidance
e NUREG-0700
·• NUREG-0801
5.3 Emergency Operating Procedure (EOP} Upgrade
5.3.1 Prepare and Submit EOPProcedures Generation Package (PGP) - This
document includes the Salem Nuclear Generating Station EOP plant
specific technical guidelines, writers guide, EOP validation
program and EOP trainning program description. The PGP must be
transmitted to the NRC for review.
5.3.1.1
5.3.1.2
Requirements - NUREG-0737 Supplement 1 Section 7.2.b
states that each licensee shall submit to the NRC a
Procedures Generation Package at least three months
prior to the date it plans to begin formal operator
training on the EOPs.
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare or assure preparation of the technical
content of EOP PGP.
• Assure package development and timely submittal to
the NRC.
Secondary Responsibility:
e Operations - Provide operations input and package
review as necessary.
5-12
\
5.3.1.3 Guidance
• EOP Generation Package Guideline (INPO EOPIA)
Feb. 1983.
• NUREG-0899, Guidelines for Preparation of EOPs,
August 1982.
• Review Criteria for Evaluation of PGPs (Batelle)
Nov. 1983.
5.3.2 Develop Plant Specific Technical Guidelines - The development of
the plant specific .technical guidelines (PSTGs) will consist of
converting the WOG ERGs into Salem specific guidance for develop
ment of the Salem Nuclear Generating Station EOPs in accordance
with the PGP. This will involve providing .Salem systems data
(including informational and control requirements) along with any
Salem specific non-ERG information. Any deviations from the ERGs
must be described and justified.
5.3.2.1
5.3.2.2
Requirements - NUREG-0737 Supplement 1 Section 7.2.b.i
requir.es that the method for developing plant specific
EOPs from the generic technical guidelines including
plant specific information· be developed.
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare or assure preparation of the PSTGs based on
the WOG ERGs including the calculational
methodology.
5-13
•
•
5.3.2.3
·)
Secondary Responsibility:
• Operations - Provide operations expertise arid
support as necessary. Review draft PSTGs.
Guidance
e NUREG-0899.
5.3.3 Perform PSTG Verification - The PSTG verification process will
evaluate the correctness and technical accuracy of the PSTGs.
Static aspects of the PSTGs, such as plant specific functions and
setpoints, will be confirmed to be in accordance with the WOG ERGs
and Salems PSTG Peparation Guide. The existence of adequate
documentation for the PSTG and EOP verification will be
confirmed. This will be performed by individuals not involved in
the initial PSTG preparation.
5.3.3.l
5.3.3.2
Requirements ~ NUREG-0737 Supplement 1 Section 7.2.b.iii
states that a program for EOP (PSTG~ verification must
identify operator- tasks: a_nd information and control
requirements .during emergency operations.
PSE&G Division of Responsibility
· Primary Responsibility:
• Assure proper verification of the PSTGs is
performed.
Secondary Resi;x>nsi_bili ty
• Operat_ions - Revise PSTG verification process and
results for adequacy.
5-14
5.3.3.3 Guidance
• INPO NUTAC EOP Verification (INPO 83-004).
• NUREG-0899
5.3.4 Develop Draft EOPs
After preparation of the PSTGs and their verificqtion, the draft
Saiem Nuclear Generating Station EOPs will be developed. The
draft EOPs will use the information contained in the PSTGs for
functional requirements. The EOP development process must be -
consistent with the Salem Nuclear Generatin~ Station PGP Writers
Guide.
5~3.4.1 Requirements - NUREG-0737 Supplement 1 Section 7.1.c
states that upgraded EOPs must be consistent with the
PSTGs and an appropriate writers guide.
5.3.4.2 PSE&G Division of Responsibility
Primary Responsibility:
• Prepare draft EOPs in accordance with Salem EOP
Writers Guide.
Secondary Responsibility:
• Operations - Review draft EOPs for acceptability.
S.3.4.3 Guidance
e NUREG-0899.
• Salem EOP Writers Guide. ·
•
•
• NUREG/CR-875, Evalµation of EOPs, April 1981.
• NUREG/CR-2005, Checklist for Evaluating EOPs, April
1983.
5.3.5 Perform EOP Verification - The EOP verification process will
evaluate the correctness, technical accuracy and proper conversion
of the Salem PSTGs for EOP d~velopment. s·~attusi aspects of the
EOPs such as plant-specific valve numbers, setpoints, footnotes,
and format will be confirmed to be in accordance with the
PSTGS and the Salem EOP Writer's Guide. Supporting procedures
that are referenced or utilized will be verified and evaluated to
ensure that the intended fllllctions referenced by an EOP can be
accomplished. In addition, the EOPs will be partially-evaluated
for usability and compatibility with the minimum number,
qualifications, training, and experience of the Salem Nuclear
Generating Statioo operating staf_f. Finally, the existence of
adequate .documentation for the EOP verification will be confirmed.
5.3.5.1 Requirements - NUREG-0737 Supplement 1 Section 7. 2. b. iii
states that a program for EOP verification must be
prepared.
5.3.5.2 · PSE&G Division of Responsibility
Primary Responsibility:
• Assure proper verification of the EOPs are
performed.
Secondary Responsibility:
• Operations - Review PSE&G verification process and
results for adequacy.
5-16
5.3.5.3 Guidance
• INPO NUTAC EOP Verification, (INPO 83-004).
• NUREG-0899.
5.3.6 Perform System Functions Review and Task Analysis - The system
functions review and task. analysis process of the DCRDR and EOP
upgrade is to determine the input and output requirements of the
Control Room crew for emergency operation and to ensure that
required systems can be efficiently and reliably operated during
emergency operations by available personnel. This will be
accomplished by performing an analysis of tasks contained in the
Salem draft EOPs.
5.3.6.l
5.3.6.2
Requirements - NUREG-0737 Supplement l Section 5.1.b.ii
states that a system function and task analysis be
conducted to identify control room op~rator tasks and
·information and control requirements during ·emergency
operations.
PSE&G Division of Responsibility
Primary Responsibility:
• Assure proper conduct of task analysis including
training needs and human factors expertise.
Secondary Reponsibility:
• Operations .... Provide operator support and input to
the task analysis.
5-17
5.3.6.3 Guidance
e NUREG-0800.
• CRDR.Task Analysis Guideline (INPO NUTAC) Dec. 1983.
• NUREG-0700, Guidelines for CRDR, Sept. 1981.
• NUREG/CR-3371, Task Analysis of Control Room Crews,
Vol .• 1 and 2, Sept. 1983.
• NRC Memorandum of May 14,_1984.
5.3.7 Perform DCRDR/EOP Validation - the DCRDR/EOP Validation is to
. determine whether the functions allocated to. the Control Room
operating crew can be accomplished effectively within (1) the
structure of the Salem EOPs and (2) .the design of the Control Room
as it exists. Ad~itionally, this step provides ari opportunity to
identify HEDs that may not have becom·e evident in the static
processes of the DCRDR, and the EOP development. The DCRDR/EOP
validation process will use predefined accident scenarios to drive
the walkthroughs or simulator exercises. This process will
require a Salem operating crew.
5.3.7.1 Requirements - NUREG-0737 Supplement 1 Section 7.2.b.iii
states that a program for validation of the EOPs be
prepared.
5.3.7.2 PSE&G Division of Responsibility
Primary Responsibility:
• Participate iri and assure proper conduct of the
DCRDR/EOP validation.
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• I
I
Secondary Responsibility:
• Operations - Provide an operating crew for
performing DCRDR/EOP Validation.
• Training - Provide simualtor time and expertise as
required.
5.3.7.3 ·Guidance
• INPO 83-006, EOP Validation Guidelines I July 1983.
e NUREG-0899.
e NUREG-0700.
5.3.8 Perform EOP Modifications - EOP discrepancies discovered during
the DCRDR/EOP Validation' phase will be evaluated and resolutions
will be incorporated into the draft EOPs. This feedback process
will better assure that the EOPs are usable. The· EOP modifica
ti6ns resulting at this time will create the human factored EOPs
required.
5.3.8.1
. 5.3.8.2
Requirements - No specific NUREG-0,737 Supplement 1
requirements identifed.
PSE&G Division of Responsibility .·
Primary Responsibility:
• Ensure EOP modifications as determined necessary are
performed.
5-19
-.
Secondary Responsibility:
• Operations - Input and review EOP modifications.
5.3.9 Implement EOPs
Upon completion of the EOPs and EOP operator training (see Section
5.5.4) the EOPs will be implemented.
5.3.9.l
5.3.9.2
5.3.9.3
Requirements - NUREG-0737 Supplement 1 Section 7.1.e
states that upgraded EOPs will be implemented.
PSE&G Division of Responsibility
Primary Responsibility:
• Operations - Implement upgraded Salem Nuclear
Generating Station EOPs.
Secondary Responsibility:
• No secondary responsibilities identified.
Guidance
• . INPO 82-013, EDP Implementation Ass~stance Program,
April 19825.
5.4 Regulatory Guide (R.G.) 1.97
5.4.1. Prepare R.G. 1.97 (Rev 2) Compliance/Position Report - This report
will consist of 1) a compliance summary on how Salem presently
meets the post accident monitoring instrumentation requirements of
R.G. 1.97 (Rev. 2) including instrument rangesi qualification,
power supply, redundancy, _etc., 2) the PSE&G position to -further
5-20
•
meet the requirements of R.G. 1.97 and justification for deviation
from the requirements, and 3) i-ts application to emergency
response facilities. This report will ~e developed using the
existing Salem instrumentation design and the EOP/EP require- .
ments. The R.G •. 1.97 Position Report was sumitted to the NRC in
accordance with.the O.L. Condition on 4/2/81.
5.4.1.1 Requirements - NUREG-0737, Supplement 1, Section 6.2
states that the licensee shall submit a report
describing how it meets the R.G. 1.97 requirements.
5.4.1.2 PSE&G Division of Responsibility
Primary Responsibility:
• Determine appropriate R.G. 1.97 instrumentation and
prepare basis for the R.G. 1.97 Position Report.
Secondary Responsibility:
• Input into R.G. 1.97 instrumentation rieeds and
develop final position report for NRC submittal.
5.4.1.3 Guidance
e R.G. 1.97 (Rev. 3).
• Recommendations for Changes to R.G. 1. 97 (INEL)
(Sept. 1982) •
5-21
•
•
5.4.2 Perform R.G. 1.97 Control Room Interface - Accident monitoring
instrumentation which are required for specific operator action
(primarily Type A/Technical Specification variables) will be
identified and given special consideration during other emergency
response capability task activities. This will include preferred
instrumentation selection on the SPDS, recognition of operator
usage during the DCRDR/EOP Validation, and the control panel
instrumentation identification for usage during an accident.
5.4.2.1
5.4.2.2
Requirements - NUREG-0737 Supplement 1 Section 5.1.d
states that .DCRDR improvements should be coordinated
with other improvement programs including R.G. 1.97.
PSE&G Divisions of Responsibility
Primary.Responsibiiity:
• Review and input into R.G. 1.97 instrumentation
identification philosophy.
Secondary Responsibility:
• Establish ERC philosophy for instrumentation
identification on the control panels.
• Review and input into instrumentation identification
philosophy and evaluate review results of DCRDR
validation.
• SPDS Project Manager - Evaluated R.G. 1.97
instrumentation list for use on SPDS displays •
5-22
•
•
5.4.2.3 Guidance
e NUREG-0700.
• R.G. 1.97 (Rev. 2) Section 1.4.6.
5.4.3. Prepare for R.G. 1.97 NRC Commen.t/Audit - The NRC will perform a
review of the Salem Nuclear Generating Station R.G •. 1.97 Position
Report and will either accept or request additional information on
each of the exceptions taken to the Regulatory Guide by PSE&G.
PSE&G will be required to prepare and submit anyadditional
information as required to support the Salem Nuclear Generating
Station positions. The NRC may also perform an audit to verify
implementation of the R.G. 1.97 instrumentation modifications.
5.4.3.1 Requirements - NUREG-0737, Supplement l Section 6.2
states that staff review will be in the form of an audit
that will include a review of the licensees method of
implementing R.G. l.97.
5. 4. 3. 2. PSE&G Di vision of Responsibility
5.4.3.3
Primary Responsibility:
• Coordinate NRC responses and/or audit.
• Provide technical support NRC responses and/9r
audit.
Guidance
None identified •
5-23
'-
5.4."4. Prepare Design Modifications for R.G. 1.97 """ Design Change Package
(DCP) for all instrumentation modifications as determined
necessary for Salem per R.G. 1.97 must be prepared for meeting the
implementation schedule of O.L. Condition c. (7) - Unit 2_ -L:Lcens~'·
5.4.4.1 Requirements - No NUREG-0737 Supplement 1 requirements
specified.
5.4.4.2
5.4.4.3
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare design change packages for R.G. 1.97
_ instrumentation modifications.
Guidance
None identified.-
5.4.5. Procure Equipment for Instrumentation Modification - The R.G. 1.97 -
equipment-required per the approved DCPs must be procured on a
schedule to meet the implementation requirements.
-5.4.5.1 Requirements - No specific NUREG-0737 Supplement 1
requirements identified.
5.4.5.2 PSE&G Division of Responsibility
Primary Resp6nsibility:
• Procure R.G. 1.97 equipment iri timely manner for
implementation.
Secondary Responsibility:
• None identified. 5_;24
•
•
•
5.4.5.3 Guidance
None identified.
5.4.6 Implement R.G. 1.97 Modifications - In accordance with the
requirements of Operating License Condition C.(7) - Unit 2, all
R.G. 1.97 modifications as determined necessary must be imple
mented by the 1st or 2nd refueling outages.
5.4.6.l Requirements - Operating License Condition
5.4.6.2 PSE&G Division of Repsonsibility
Primary Responsibility:
• Perform modifications based on approval DCPs •
Secondary Responsibility:
• Provide technical support as determined necessary.
5.4.6.3 Guidance
None identified.
5.5 EMERGENCY RESPONSE CAPABILITY TRAINING
5.5.1 Establish Systematic Training Requirements - Salem's systematic
(performance based) training requirements will be established as
determined necessary from the INPO accreditation program criteria
along with any training related EP requirements· from the DCRDR/EOP
Validation. The performance based training criteria will include
how PSE&G proposes to 1) perform a systematic analysis to deter
mine discrete job performance requirements, 2) develop training
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•
objectives from the systematic analysis and describe the desired
trainee performance after training, 3) conduct training to meet
the specified objectives, 4) ~valuate trainees' performance during
training to demonstrate mastery of objectives, and Sf rev.ise
training program based on trainee performance on the job.
5.5.1.1 ·_Requirements_- NUREG-0737 Supplement 1 Section 3.4.c,
3.8.d, and 7.1.d and Section 306 of the Nuclear Waste
Policy Act of 1982 and the proposed lOCFRS0.57 and
50.200 (SECY-84-76) requires that a systematic (task
analysis) approach be developed to act as a basis for
performing future operator training.
5.5.1.2
5.5.1.3
PSE&G Division of Responsibility
Primary Responsibility:
• Establish systematic training requirements.
Secondary Responsibility: .
• Provide necessary input from DCRD~/EOP validation
for establishing training requirements.
Guidance
· • _,,;,Proposed lOCFRSO. 55 rulemaking on training.
• · INPO Job and Task Analysis Guides (3 Vol.) Sept.
1983 •
5-26
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•
•
•
5.5.2 Develop ERC Integrated Training Plan - This plan will provide the
systematic training process for developing operator knowledge in
order to comprehend plant conditions and cope.with potential
emergencies effectively. The scope of the training plan will
involve overall emergency response capability training including
use of the SPDS, EOPs, and use of post-accident instrumenta
tion. This plan should use criteria extracted from the Salem
systematic requirements developed from the Salem program for
complying with the INP·o Accreditation Program.
s.s.2.1
·s.5.2.2
5.5.2~3
Requirements - The requirements of an Integrated
Training Plan are not specified in NUREG-0737 Supplement
1, however, the plan was called out by the NRC in the
NUREG-0737 Supplement 1 NRC workshop tr~nscripts.
PSE&G Division of Responsibility
Primary Responsibility:
• Develop Integrated Training Plan.
Secondary Responsibility:
• Provide ·document scope and input as necessary.
Guidance
• Prop6sed 10CFR50.55 rulemakirig~
• NUREG-0737 Supplement 1. NRC Workshop Transcript .
(Feb. 24, 1983) •
5-27
•
•
5.5.3 Develop SPDS Simulator Hardware/Software - The hardware and
software for the SPDS needs to be incorporated into the Salem
Simulator. This needs to be accomplished sufficiently ahead of
SPDS implementation in order to conduct the SPDS man/machine
validation and operator training.
5.5.3.1
5.S.3.2
s.s.3.3
Requirements - No specific NUREG-0737 Supplement 1
requirements.
PSE&G Division of Responsibility
Primary Responsibility:
• Develop SPDS software and install hardware on Salem
Simulator •
Secondary Responsibility:
• Aid the hardware installation as part of the
Simulator update process.
Guidance
• Proposed R.G. 1.149, Nuclear Power Plant Simulators
for Operator Training.
5.5.4 Perform EOP Training - As part of the overall Salem training
program, EOP training will be included to establish an operating
staff that is capable and competent to respond to any off-normal
plant situation. This training will consist of classroom
instruction, simulator exercises, and/or walkthroughs, as
appropriate •
5.S.4.1 Requirements - NUREG-0737 Supplement 1 Section 7.1.d
states that the licensee will provide operator training
on the use of the upgraded EOPs prior to implementation.
5-28
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•
5.5.4.2
5.5.4.3
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare training course and conduct operator
training.
Secondary Responsibility:
• Provide background and support on EOP development.
Guidance
• IN.PO Accreditation Program.·
5.5.5 Perform SPDS Operator Training - Prior to implementing the·SPDS
the control room operators must be fully trained in the use of the
SPDS for normal and emergency conditions. Training will include
use of the SPDS as (1) an aid for following the emergency
procedures, (2) the means for estimating off-site dose levels, ( 3)
an aid to declaring emergency action levels, and (4) as a means
for providing plant status (post~accident monitoring information)
to the TSC and EOF. SPDS training for the control room will use
the SPDS added to the simulator.
5.5.5.1
5.5.5.2
Requirements - NUREG---0737 Supplement 1 Section 4.1.c
states that SPDS. training will be performed to respond
to accident conditions.
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare training course and conduct training.
5-29
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•
•
Secondary Responsibility:
• Aid or support training act{vities.
5.5.5.3 Guidance
• INPO SPDS Implementation Guideline.
5.6 SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
5.6.1 Perform SPDS Functional Analysis - This involves specification of
the function(s) the SPDS is expected to perform. The functional
analysis should identify the types of activities to be supported
by the SPDS in the control room, TSC, and EOF, and the kinds of
information required by prospective SPDS users. At a minimumn,
the analysis should define the role of the SPDS in relation to the
EOPs, the types of personnel who will be expected to use it, the
location of the SPDS units in the control room. Consideration
should also be given to design characteristics that will assure
reliability and availability goals stated in NUREG-0696.
5.6.1.l
5.6.1.2
Requirements - NUREG-0737 Supplement 1 Section 4.l~b,
4 .1. c, 4 .1. e and 4 .1. f states that the SPDS shall
continuously display information to the operators, and
shall provide sufficient information to determine plant
safety status including reactivity control, core
cooling, RCS integrity, radioactivity control, and
containment conditions.
PSE&G Division of Responsibility
Primary Responsibility
• SPDS Project Manager - Assure preparation of the
SPDS Functional Analysis for SPDS display
development basis.
5-30
•
5.6.1.3 . .
Secondary Responsibilities
• Input to and review of information to be provided by
SPDS for acceptability to operators and to assure
accurate representation to SNGS EOPs.
• Help define, or review and cordinate these
activities to assure licensing compliance .and task
. integration.
• Provide PSTG support for preparing Functional
Analysis.
Guidance
• NUREG ~ 0696, Section 5
• NUREG - 0800, Standard Review Plan Section 18.2,
Safety Parameter Display System, Rev. o, Nov. 1984
• Guidelines for an Effective SPDS Implementation
Program. INPO 83-008 (NUTAC), Jan 1983
5.6.2 Perform SPDS Parameter Set Selection - This involves the selection
of Salem specific parameters which shall be available on the SPDS
displays that must be sufficient to indicate the ERG control
functions. Thes.e parameters will be determined based on the
requirements of the Salem PSTG' s and the functional analysis
performed in 5.6.1. The parameter list must be verified by
demonstrating that the proposed parameters are sufficient to
monitor. plant status under different plant modes and meet the NRC
Critical Safety Function (CSF) requirements for continuous
moni taring.
5-31
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•
•
5.6.2.1
5.6.2.2
5.6.2.3
Requirements - NUREG-0737 Supplement 1 Section 4.1.l
states that the minimum information to· be provided shall
be sufficient to provide reactivity control, reactor
core cooling, reactor coolant system integrity,·
radioactivity control, and containment conditions.
Section 4.2.a states that the selection should be based
on a wide range of accident events including severe
accidents.
PSE&G Division of Responsibility
Primary Responsibility:
• Develop Salem specific parameter list for SPDS using
generic parameter sets and Salem specific SPDS
monitoring requirements.
Secondary Responsibility:
• Aid parameter list development and provide in Salem
SPDS safety analyses.
Guidance - No specific guidance documents identified.
5. 6. 3 J;'repare and Submit SPDS Safety Analysis Report and Implementation
Plan - This SPDS Safety Analysis is conducted to assure that the
SPDS design is sufficient to assess the safety status of each
identified safety function for a wide range Of accident events.
This report was submitted to the NRC for review by 1/30/84 and the
SPDS will be implemented by 6/87~
The Implementation Plan will describe the entire implementation
process for the SPDS system. The plan will describe the design,
development, installation,· t~aining and functional operation of
the system. This plan.will be submitted to the NRC for review
5-32
with the SPDS Safety Analysis. The detailed info!mation to be
included. in the SPDS Safety Analysis and Implementation Plan shall
contain parameter selection, signal validation, human factors
review, reliability, verification and validation, man/machine
validation, and circuit isolation.
S.6.3.1
S.6.3.2
s.6.3.3
Requirements - NUREG -0737 Supplement 1 Section 4.2
states that a written safety analysis, describing the
basis on which the selected SPDS parameters are
sufficient to assess the safety status,and an
implementation plan shall be submitted to the NRC for
review.
PSE&G Division of Responsibility
Primary Responsibilities:
• Develop SPDS Safety Analysis and Implementation
Plan.
• Develop scope and assure proper Safety Analysis
Report and Implementation Plan development for
submittal to NRC.
Secondary Responsibility:
e . Provide appropriate input for report development.
Guidance
• NUREG-0800, Section 18.2.
e· Guidelines for an Effective SPDS Implementation
Program INPO 83-003 (NUTAC), January 1983.
5-33
5.6.4 Prepare Functional Requirement Document - The Salem Functional
Requirements Document which is the design basis for the system .
will be revised with information completed/planned as a result of
this phase of the ERFCS/SPDS development. This will include the
parameter set, circuit isolation, Verification & Validation plari,
human factors, Man/Machine validation and system reliability.
This document will not be submitted to the NRC, but must be
prepared for baseline reference for future efforts.
5.6.4.1
5.6.4.2
5.6.4.3
Requirements ~ No specific NUREG-0737 Supplement 1
requirements.
PSE&G Division of Responsibility
Primary Responsibility:
• To develop or assure proper development of the
Functional Requirements Document for both software
and hardware.
Secondary Responsibilities: _
• Review and provide input to Functional Requirements
Document.
• Review design doc_ument to assure licensing
requirements are incorporated.
Guidance
• NUREG-0800, Section 18.2.
• NSAC-39, Verification and Validation for SPDS,
December 1981. _
5-34
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5.6.5 Develop Static SPDS Displays - Static displays will be designed
and built on the SPDS IDT CRl's to assure display/CR!' configura
tion acceptability. The computer display conventions will be
included at this time to assure htiman factors principles ai:e
incorporated.
5.6.5.l
5.6.5.2
5.6.5.3
Requirements - NUREG-0737 Supplement 1, Sections 4.1.a
and 4.1.b states that the SPDS should provide a concise
display of critical plant variables and continuously
display information from which plant status can be
readily and reliably assessed by control room personnel.
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare or assure preparation of SPDS static·
displays.
Secondary Repsonsibility:
e Build displays on IDT SPDS CRTs.
• Provide direct input arid evaluation on the SPDS
display development.
• Review SPDS displays to assure minimum NRC
requirements are met.
Guidance
. • EPRI-NP-3701, Vols. 1 and II, Computer Generated
Display System Guidelines, Sept. 1984~
5-35
5.6.6 Prepare SPDS Human Factors Program and Perform Review - The SPDS
displays shall be designed to incorporate accepted human factors
principles so that the displayed information can be readily
perceived and comprehended by the SPDS operator. A SPDS human
factors program will be prepared which includes readability,
parameter responsiveness to the CSFs, glare, labeling, alarms,
anthropometrics and SPDS location. A human factors review will be
performed to assure proper human factors design application.
5.6.6.1
5.6.6.2
5.6.6.3
Requirements - NUREG-0737 Supplement 1, Section 4.1.e
sta_tes that the SPDS shall be designed to incorporate
accepted human factors principles.
PSE&G Division of Responsibility
Primary Responsibility:
• Develop SPDS human factors program. Perform and
document HFE review based on survey guidance and
established HFE computer conventions.
Secondary Responsibilities:
• Aid review and help establish HFE- computer
con veri tiqn.
• Establish Salem computer conventions as part of
DCRDR.
Guidance
e NUREG-0700
• NUREG-0800, Section 18.2
5-36
5. 6. 7 Determine Process for Signal Validation - Signal validation is the
process for assuring that ·the input signals being displayed by the
SPDS are valid and that the operator is alerted if a signal is
suspect. This involves the use of algorithms for comparing
multiple signals to a processed signal in order to remove a failed
instrument channel as a signal input.
5.6.7~1
5.6.7.2
5 .• 6. 7. 3
Requirements - NUREG-0737 Supplement 1 Section 4.1.b
states that the SPDS will display information from which
plant status can be reliably assessed.by control room
personnel. NUREG-0696 states that displayed data shall
be validated where practical on a real-time basis to
ensure presentation of the most current and accurate
plant status, not compromised by faulty processing or
failed sensors.
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare or ·assure preparation of the SPDS. signal
validation algorithms
Secondary Responsibility:
• Develop software routines for algorithms.
Guidance
• EPRI NP-210, ·On-line Power Plant Signal Validation_
Technique, Nov. 1981.
5-37
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5.6.8 Develop Software Design Specification - In order to effectively
perform the SPDS Verification and Validation, a software
specification must be developed. This specification is based on
the system requirements established in the SPDS Functional
Requirements Document; and will contain the actual system design
specifications.
5.6.8.1
5.6.8.2
5.6.8.3
Requirements
No specific requirement provided in NUREG-0737
Supplement 1.
PSE&G Division of Responsibility
Primary Responsibility:
• Develop software design specification for developing
dynamic SPDS software.
Secondary Responsibility:
• Review software specification against Function
Requirements Document for _complete conversion.
Guidance
· • No specific documents identified.
5.6.9 Determine Parameter Use and Processing - The specific
instrumentation for acquiring SPDS parameter signals, including
the number of singals to be used, must be determined. These
should be selected from safety-related and normal post-accident
.monitoring instrumentation. The means of processing and averaging
(algorithms) the input data to the SPDS.must also. be determined.
5-38
•
•
5.6.9.l
5~6.9.2
5.6.9.3
Requirements - No specific NUREG-0737 Supplement 1
requirements.
PSE&G Division of Responsibility
Primary Responsibility:
• Select SPDS .·instrumentation and determine signal
processing algorithms•
Secondary Responsibility:
• Convert processing algorithms into SPDS subroutines.
• Compare instrumentation for consistency with DCRDR
identified and Regulatory Guide 1.97 instrumenta~
tion, as necessary
Guidance
• PSE&G Regulatory Guide 1.97 Position Report.
5.6.10 Develop Dynamic Display Software - Software for driving the
static displays must be developed. The software package will
also utilize the signal validation and the parameter selection
and processing results. Verification and validation will be
applied to the software package.to assure proper software.
development •.
5.6.10.1 Requirements - No specific NUREG-0737 Supplement 1.
requirements provided •
5-39
• S.6.11
•
5.6.10.2
5.6.10.3
PSE&G Division of Responsibility
Primary Responsibility
• Develop all SPDS computer software
Secondary Resp6nsibility
• Review software algorithms for proper
translation.
• Review software algorithms for proper
tr ans la ti on.
Guidance - No specific guidance documents
· identified •
Perform SPDS Hardware Installation - The SPDS hardware along
with al~ necessary cabling must be installed in the control
room, EOF and TSC. Special attention must be paid to all
interfaces between the SPDS and existing plant instrumentation
to ensure that the integrity and reliability of existing
instrumentation cannot be affected by any malfunction of the
SPDS hardware.
5.6.11.1 Requirements - NUREG-0737 Supplement 1 Section 4.1.c
states that the SPDS shall be suitably isolated from
electrical or electronic interference with equipment
and sensors that are in use for safety systems •
5-40
•
5.6.12
5.6.11.2
5. 6 .11. 3
PSE&G Division of Responsibility
Primary Responsibility
• Implement all ERFICs/SPDS hardware per approved
DCPs.
Secondary Responsibilities:
• Issue all DCPs as necessary for installation·
hardware.
• Identify all hardware installation requirements
and review instrument inputs for circuit
isolation.
Guidance - No specific guidance documents·
identified.
Perform SPDS Verification/Validation (V&V) - The verification
process will be conducted to assure that the SPDS system is
designed, tested and installed as described by the functional
requirements. The validation process assures that once the
system has been installed and is operational that it is
functionally adequate. The evaluation wil_l demonstrate that the
system actually accomplishes the role it is designed to
perform. This involves the development of a V&V test plan and
validation test procedures, conducting the actual software and
hardware V&V in accordance with those procedures, and developing
a final V&V test report. This process must be performed
independent from the engineering/computer staff.
5~6.12.1 Requirements - NUREG-0737 Supplement 1 Section 4.1.a
requires that the SPDS be developed with a high
degree of reliability.
5-41
• 5.6.12.2
5.6.12.3
PSE&G Division of Responsibility
Primary Responsibility:
• To develop (or contract for) a verification and
validatioo program including test plans and V&V
implementation.
Secondary Responsibility: ·
• Aid development of V&V program, review Validation
Test Report summarizing the V&V efforts, and make
document available for NRC review as necessary.
Guidance
• NSAC-39, Verification and Validation for SPDS,
December 1981.
• Component verification and System Validation
(INPO NUTAC) October 1983.
5.6.13 Perform Man/Machine Validation of SPDS Displays - During the
DCRDR Validation of Control Room Functions, the SPDS 'displays ' should be evaluated for their relationship to other control room
·'
_instrwnents and their ability to aid to the operators in use of
the EOPs.
5.6~13.l Requirements - NUREG-0737 Supplement l Section 4.1.b
states that the SPDS will provide plant status which
can be readily and reliably assessed by control room
personnel.
5-42
•
5.6.14
•
5.6.13.2
5.6.13.3
PSE&G Division of Responsibility
Primary Responsibility:
• Prepare Man/Machine Validation program and
arrange for appropriate personnel to be available
during validation. ·
Secondary Responsibility:
• Support Man/Machine Validation with simulator and
validation crew support.
• Provide SPDS operating crew for validation •
• Provide scenario input and valida.tion experience
to SPDS validation.
Guidance
• NUREG-0700.
• DCRDR Validation Results (to be conducted).
• NSAL-39 Verification and·Validation for Safety
Parameter Display Systems, December 1981.
Prepare for NRC Audit - The NRC will either perform a second
"Preimplementation Audit" or a "Validation (post-implementation)
Audit", but likely not both. The preimplementation audit will
involve a review on how the NRC requirements are met. prior to
SPDS implementation. The validation audit will look more
heavily at the SPDS man/machine validatioo, operability and
training aspects.
5-43
• 5.6.14.1
5.6.14.2
5.6.14.3
•
Requirements - No NUREG-0737 Supplement 1
requirements specified.
PSE&G Division of Responsibility
Primary Responsibility:
• Coordinate NRC audit at SNGS.
• Provide the technical support and documentation
for NRC audit.
• Support NRC audit as required.
Guidance
• NUREG-0800, Section 18.2 •
5-44
•
SECTION 6. EMERGENCY RESPONSE CAPABILITY TASK INTEGRATION
Section 3, "Coordination and Integration of (ERC) Initiatives" of
NUREG-0737 Supplement 1 discusses the NRC's philosophy and suggested approach
to the ERC task integration. The NRC does not dictate how ERC task
integration will be accomplished, since every plant has different needs and
various stages of task completion, but provides suggested methodologies to be
considered. In addition, an: INPO NUTAC developed document "Guidance for an
Integrated Implementation Plan for Emergency Response Capabilities" (INPO 83-
048) also provides various methodologies for accomplishing this integration.
The following discussions elaborate on the methodology:
· 6.1 Task Integration Step No. l; PSTG Development for Task Integration
WOG
Technical
Guidelines
'(ERG's, Rev. 1)
' I PSTGs /
l l I ! !
SPDS R.G. 1.97 DCRDR EOP
Parameter Compliance Information Development
Set and Control .
Requirements
6.1.l Prerequisites -
a) PWR Technical Guidelines, WOG ERG's (Rev. 1)
b) WOG ERG Calculational Procedures
6-1
•• 6.1.2
•
c) Salem Nuclear Generating Station EOP Procedures Generation
Package (PGP)
d) Plant Specific design details
Integration Activities - The Plant Specific Technical Guidelines
(PSTGs), are the base document for almost all ERC task develop
ment activities. As discussed in Section S.3.2, the PSTGs will
be derived from the WOG ERGs using Salem Nuclear Generating
Station specific design and system requirements and the action
set-points. This document will be the basis for determining the
DCRDR information and control requirements, the EOP upgrade
development, the SPDS parameter set selection, and the R.G. 1.97
instrumentation requirements.
The EOP development process will use the PSTGs to acquire the
basic plant specific information necessary for converting the
function type statements of the ERGs to the task related actions
of the EOPs. At this point in the EOP development process, the
EOPs are rough draft and will require further human factoring
and step refinement from information received during the task
analysis and EOP Validation. The PSTGs can either be used
directly in the DCRDR task analysis or can be enhanced by
providing the EOP writers guide format and EOP design input. In
either case, the Salem Nuclear Generating Station plant specific
technical data will be in use, but no plant specific technical
data will be included in order to prevent predetermining the
adequacy of the existing control room instrumentation.
The DCRDR process will use the PSTGs/Draf t EOPs as a basis for
identifying the information and control requirements to be
determined during the DCRDR System Function Review and Task
Analyses.· These information and control requirements will be
compared against the Control Room Inventory to determine
instrument deficiencies in the control room.
6-2
•
•
The SPDS parameter set selection will be based on the PSTGs for
determining the EOP entry conditions and the EOP monitoring and
control requirements. This activity is further discussed in
Task Integration Step No. 2.
The R.G. 1.97 post-accident monitoring instrumentation require
ments are also based on the PSTGs. Type A variables are based
on the PSTG entry conditions and the monitoring and control
requirements. Other R.G. 1.97 variable positions are based on
their specific use and need as determined by the PSTGs.
6.2 Task Integration Step No. 2; ERG/PSTG Functional Analysis Development
WOG
ERGs
.CONTROL ROOM
INFORMATION
CONTROL REQ •
ERG
.FUNCTIONAL ANALYSIS
SALEM PSTG
FUNCTIONAL
ANALYSIS
SALEM SPDS
PARAMETER
SET
6.2.1 Prerequisites -
SALEM
EOPs
a) WOG Technical Guidelines, WOG ERGs (Rev. 1).
b) Salem PSTGs •
6-3
\.
• 6.2.2 The WOG ERGs and the Salem PSTGs are "function" based docurnen ts
whe.re a function represents a higher order activity by which the
EOP developer translates the objectives of the ERGS into the
PSTGs.
6. 3 TASK INTEGRATION STEP NO. 3 ~ SPDS Parameter· Set Selection
Salem
PSTGS
Salem
Functional
Analysis
SPDS
Parameter
Set
·e..3.1 Prerequisites -
a. PWR Technical Guidelines, WOG ERG's (Revision 1 or later)
b. Plant Specific Techrifoal Guidelines
c. Salem SPDS Function Analysis
6-4
• 6. 3 .• 2
•
Integration Activities - Since the SPDS will be structured
around the use of the Salem EOPs, the SPDS parameter set must be
integrated closely with informational requirements of the EOP
Upgrade process. The Salem PSTGs establish the basis for the
informational needs of the EOPs and will therefore be used as
the basis for selection of the SPDS parameters.
The Salem SPDS parameter set can then be determined by applying
the PSTG entry condition and the monitor and control functions
of the PSTGs.
This process requires close integration of the two programs and
any major revisions to the PSTGs will need to be reviewed to
assure that the SPDS Parameter Set and PSTGs are consistent •
6-5
•
•
')
6.4 TASK INTEGRATION STEP NO. 4; CONTROL ROOM HUMAN FACTORS GUIDELINE
DEVELOPMENT
NU REG
-0700
I>CRDR Human
Factor~ Guideline
Salem
Control Room
I&C
I
Control Room SPDS R.G. 1. 97
Conventions Conventions Instrument
Design
6 •. 4 .1
6.4.2
Prerequisites -
None.
Integration Activities - The control room human factors
guideline being developed as discussed in section S.2.2 will be
beneficial to several ERC task activities. It will primarily be
used to establish specific Salem control room conventions that
can be used to justify exception to the human factors
engineering checklist requirements. Secondly, it will document
. the standard human engineering design characteristics of the
existing computer systems in the control room. This will allow
the SPDS display designers the ability to use the same or
similar convention.s when. developing the SPDS displays. The
human factors conventions can also be used to develop the R.G •
1.97 instrumentation modifications in the control room.
6-6
•
•
6.5 TASK INTEGRATION STEP NO. 5: PERFORMING DCRDR AND EOP VALIDATION
CONTROL DRAFT SALEM
ROOM EOPs SIMULATOR
I&C SCENARIOS
NEEDS
I I l ' DCRDR/EOP SPDS
VALIDATION SCENARIOS
I I ' • DCRDR EDP SPDS
VERIFICATION TRAINING VALIDATION
6.5.l
6.5.2
Prerequisites -
a. Draft Salem EOPs
b. Selected Accident Scenarios
c. Control Room Task Analysis
d. Control Room Inventory
Integration Activities - The DCRDR/EOP Validation primarily
serves to determine whether the control room operating crew can
effectively perform system functions within the structure of the·
EOPs and within the existing design of the Salem control room.
Accident scenarios will be selected that will exercise the Salem
system functions and most of the EOP steps. This process assure
that ·under accident conditions the man/machine interface in the
control room is more effective.
6-7
• Additionally, ·the methodology for validation of the EOPs and the
scenario used in the validation will benefit a similar
validation to be performed on the SPDS. This will further.
assure that the operators use of the EOPs are effective.
The DCRDR/EOP validation, through the videotaping of the
scenarios, can benefit Salem EOP Operator training.
6.6 TASK INTEGRATION STEP NO. 6: R.G. 1.97/CONTROL RoOM INTERFACE
DCRDR/EOP
VALIDATION WOG ERGS
R.G. 1.97
.--~~~~~~~--4 TYPE A
R.G. 1. 97
INSTR.
. I.D. in CR
6.6.1 Prerequisites -
VARIABLES
SALEM
TECH.
SPECS
. a. R.G. 1.97. Position Report.
b. DCRDR/EOP validation.
6-8
SPDS
SIGNAL
LIST
• I
I I
6.6.2 Integration Activities - As discussed in Section 5.4.1, the
Salem R.G. 1.97 Position Report was submitted to the NRC ·on
4/2/81. In this report, the Salem Type A variables (parameters)
must be determined. Type A variables are those that provide
primary information to the control room operators in order to
take manually controlled action for which there is no.automatic
control. Even though there are Type A, B, c, D and E variables
required by R.G. 1.97, only those of Type A will be given
special conSiderations for ERC integration, sinc·e these are the
required Category l instruments.
The R.G. 1.97 Type A variables will then be input into: 1) the
Salem Technical Specifications, 2) the SPDS signal list, and 3)
will be given special identification in the. control room.
Section 3.3 of the Salem Technical Specifications will be
modified to reflect the Type A accident monitoring instrumenta
tion. This will be in accordance with the October 12, 1983 NRC
interval memorandum from Mattson to Eisenhut entitled,
"Technical Specifications for Post-accident Monit~ring
Instrumentation".
The SPDS signal list for use in the SPDS entry conditions will,
·to the greatest extent, use the instrumentation specified as
_R.G. 1.97 Type A variable. This is due to their higher
reliability and redundant'instrumentation.
The Type A variable instruments will also be specially marked to
denote them as post-accident monitoring instruments for use with
the EOPs •. The identification methodology will be consistent
with the results of the DCRDR/EOP Validation and Control Room
survey.
6-9
•
6.7 TASK INTEGRATION STEP NO. 7: SPDS VERIFICATION AND VALIDATION
HUMAN FACTORS PSTG/EOP R.G. 1.97
GUIDELINE DEVELOPMENT INTERFACE
I I ~ . ~
DCRDR/EOP SPDS
HEDs DEVELOPMENT I I
I __. ' I ... - - - -• •
FUTURE SPDS SPDS
MODS
6.7.1
6.7.2
TRAINING
Prerequisites -
a. Salem PSTGs/EOPs
b. Salem R.G •. 1.97 Position Report
c. SPDS V&V Program Plan/Procedures
Integration Activities - The Salem SPDS verification and
Validation (V&V) program is being expanded beyond the NSAC - 39
requirement·s to include other ERC integration activities. The
SPDS development process is-dependent on other ERC activities
including the EOP Upgrade,-R.G. 1.97 instrumentation, and the
DCRDR (NUREG-0700) human factors conventions. In addition,
resulting products of the SPDS development process include SPDS
training, and potential future modification that may be
necessary from the HEDs identified during the DCRDR/EOP
Valida ti on process.·
6-10
The SPDS V&V program will review the input documentation and
results of the SPDS development process to additionally ensure
that all ERC integration activities involving the SPDS are
documented properly.
6.8 TASK INTEGRATION STEP NO. 8: SALEM ERC INTEGRATED TRAINING PLAN
INPO
ACCREDITATION
PROGRAM
SALEM
JOB/TASK
ANALYSIS
RESULTS
EOP
TRAINING
PLANS
INTEGRATED
TRAINING
PLAN
6.8.l Prerequisites -
a. INPO Accreditation Program
DCRDR
TASK ANALYSIS
VALIDATION
RESULTS
SPDS
TRAINING
PLANS
b. DCRDR/EOP,Task Analysis and Validation results
c. Salem Training JOB/TASK Analysis Results
6-11
•
•
• L
6.8.2 , Integration Activities - Ai; discussed in Section 5.5.2 the Salem
ERC Integrated Training Program will be the basis for emergency
resp0nse training including training on the EOPs, SPDS, and use
of the control room instrumentation (i.e., R.G. 1.97 instrumen
tation). This program should be developed in conjunction with
the INPO Accreditation Program as made Salem plant specific.
As part of the DCRDR/EOP Validation task, videotapes of operator
actions during accident scenarios were recorded. These along
with the INPO job/task analysis results· conducted for Salem can
be used to support the performance based requirement of the ERC
Integrated Training Program •
6-12
•
•
SECTION 7. ERC PROJECT MANAGEMENT/ORGANIZATION
An Emergency Response Capability Project Management Organizat,ion will be
established to assure that: l) specific ERC task activities are accomplished
by defining PSE&G divisions of responsibility, 2) proper task integration is
be~ng performed, 3) the ERC tasks are being performed on a schedule consistent
with our Operating License Conditions, and 4) proper reporting and
documentation is being accomplished. This will.be accomplished through an
established PSE&G division of responsibility for each project, and ERC
Coordinator, and an ERC management reporting process.
7.1 ERC PROJECT DIVISICJt1 OF RESPONSIBILITY
The PSE&G responsibility for performing each of the overall projects
required by NUREG-0737 Supplement l are as follows:
• Detailed Control Room Design Review - General Manager Eng.ineering &
· Plant Betterment
• Emergency Operating Procedured Upgrade - General ~anager Salem
Operations
• Sa~ety Parameter Display System Development - General Manager
Engineering & Plant Betterment
• Regulatory Guide l. 97 Implementation - General Manager Engineering &
Plant Betterment
• ERC Training General Manager Nuclear Services
• Emergency Response Facility Implementation - General Manager Nuclear
.services
The PSE&G primary (lead) and secondary (support) responsibli ties for· each
of the specific tasks activities are provided in Section 5 of this plan•,
7-1
• Each of the lead projects organizations for performing the ERC tasks will
be responsible for:
• Assuring.that their overall project (i.e., SPDS, DCRDR) is developed
and implemented on a schedule consistent with Confirmatory Orders
Dated 6/12/84 and 7/26/84.
• Assuring that each of their task activities required by NUREG-0737
Supplement 1 and as specified in Section 5 of this project plan are
performed.
• Maintaining adequate documentation of their entire project ~evelopment
and implementation to support NRC review and audit.
• Providing input on a regular basis to the ERC Coordinator for monthly
, reporting to PSE&G management. (See Section 7.2).
• Providing support and input, _as determined necessary, to other ERC
project activities.
The ERC project will be coordinated from a single source within PSE&G
which will enable a unified coordination and integration of ERC task
activities.
ERC Project Coordinator Responsibilities - The ERC Project Coordinator
will perform specific· res.ponsibili ties to assure proper integration and
schedule coordination of activities. This will include the following
activities:
e Coordinate all ERC task activities between the reponsible pSE&G
organizations to assure proper integration of ERC activities.
7-2
•
• Define and obtain proper guidance in order that the ERC integration is
both licensable and beneficial to the project results. This may
involve modifications to the previously established ERC project
integration if individual task results or schedules are changed.
• Develop and maintain the overall ERC task integration schedule in
order to coordinate individual task activities for timely input into
task efforts.
• Provide proper NRC liaison on ERC status and activities.
• Provide review and maintain documentation of all ERC task activity
reports.
7. 3 PROJECT OVERVIEW/MANAGEMENT
The overall progress and coordination of the ERC projects will ·be·
directed by Vice President Nuclear. His responsibilities will be to:
• Assure that all projects are being conducted on a schedule consistent
with Confirmatory Order Dated 6/12/84 and 7/26/84.
• Resolve any "Management Attention" concern that are identified in the
ERC monthly reports.
• Resolve any interdepartmental concerns and disagreements.
• Review overall ERC activities to assure proper project direction.
• Interface with either PSE&G or NRC upper management regarding ERC
projects •
7-3
I
L
7. 4 ERC PROJECT DOCUMENTATION AND REP.ORTING
Proper reporting and documentation is necessary for review of project
progress, concern identification, and retrieval of documentation of task
activity accomplishments.
7.4.l
7.4.2
Project Reporting ~ Monthly ERC project reports will be
developed by the ERC Project Coordinator for PSE&G management
and departmental review. The ERC monthly report will discuss
the "Activities Completed" during the report month, the
. "Activities Planned" for the. upcoming month (s}, and any areqs of
"Management Attention" that have been identified during the
report month or that may occur .in. the forthcoming month (s) ~
Each of the ERC task activity lead engineers will be responsible
for providing monthly input to the ERC Project Coordinator on a
routine basis and no later than the first working day of the
following month.
Activities or concerns on a more urgent basis will be brought to
the immediate attention of the ERC Project Coordinator and to
PSE&G Management, as necessary.
Documentation - All ERC related correspondence and reports will
be filed in accordance with existing Salem project procedures.
Correspondence that is requesting action from other ERC or Salem
disciplines should be documented in a central file and be given
proper correspondence designators. All other ERC related
correspondence should be determined by the originator as to
whether it should be placed in the Salem file.
Correspondence distribution should consider both the direct and
indirect involvement of Salem ERC disciplines.
7-4
•
•
7.5 ERC ACTION TRACKING
The specific activities or input requirements for completing the ERC task
activities will be tracked and provided to each of the project lead or
responsible organizations for actioning. The ERC action may consist of a
NRC requirement, NRC commitment or an internal integration input for task
completion. However, the ERC action tracking system will not be used to
track all task commitments, but only those actions that require
interdepartmental input or responsibility, such as a R.G. 1.97 commitment
that requires a SPDS action •
7-5
top related