ML20210R110

Summary of 981214 Meeting with NEI Re Fire Protection Functional Insp Pilot Program follow-on Activities & Fire Induced Circuit Failure Analytical Assumptions Guidance Document Development.List of Attendees & Agenda Encl

ML20210R110
Person / Time
Issue date:	07/08/1999
From:	Stewart Magruder NRC (Affiliation Not Assigned)
To:	Carpenter C NRC (Affiliation Not Assigned)
References
PROJECT-689 NUDOCS 9908170032
Download: ML20210R110 (19)

Text

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July 8, 1999 MEMORANDUM TO: Cynthia A. Carpenter, Chief  ;

Generic Issues, Environmental, Financial and Rulemaking Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation a

FROM: Stewart L. Magruder, Project Manager Original Signed By:

Generic issues, Environmental, Financial

- and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation

SUMMARY

OF DECEMBER 14,1998, MEETING WITH THE j NUCLEAR ENERGY INSTITUTE (NEI) REGARDING FIRE )

PROTECTION ISSUES  ;

On December 14,1998, the staff participated in a public meeting with the Nuclear Energy Institute. The purpose of this meeting was to discuss fire protection functionalinspection pilot program follow-on activities and fire-induced circuit failure analytical assumptions guidance document development.

A list of attendees and their affiliations is provided as Attachment 1. The agenda for the meeting is provided as Attachment 2. A set of slides for an NEl presentation containing fire protection functional inspection pilot program follow-on activity proposals and a report of the status of NEl Circuit Analysis Task Force guidance development efforts is provided as Attachment 3.

The meeting consisted of the NEl presentation and discussion of the inspection proposals, and discussion of the current status of and near-term plans for the ongoing fire induced, risk-informed, circuit failure analytical assumptions guidance document development efforts of the NEl Circuit Analysis Task Force.

At the end of the meeting the NRC representatives requested that NEl provide the NRC with a letter on the docket containing detailed recommendations for fire protection functional inspection pilot program follow-on activities.

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\ .. l*,+ July 8, 1999 MEMORANDUM TO: Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation FROM: Stewart L. Magruder, Project Manager hdd-Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs f Office of Nuclear Reactor Regulation

SUMMARY

OF DECEMBER 14,1998, MEETING WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING FIRE PROTECTION ISSUES ,

I i

On December 14,1998, the staff participated in a public meeting with the Nuclear Energy l Institute. The purpose of this meeting was to discuss fire protection functionalinspection pilot program follow-on activities and fire-induced circuit failure analytical assumptions guidance J document development.

I A list of attendees and their affiliations is provided as Attachment 1. The agenda for the  ;

meeting is provided as Attachment 2. A set of slides for an NEl presentation containing fire protection functional inspection pilot program follow-on activity proposals and a report of the status of NEl Circuit Analysis Task Force guidance development efforts is provided as Attachment 3.

The meeting consisted of the NEl presentation and discussion of the inspection proposals, and discussion of the current status of and near-term plans for the ongoing fire-induced, risk-informed, circuit failure analytical assumptions guidance document development efforts of the NEl Circuit Analysis Task Force.

At the end of the meeting the NRC representatives requested that NEl provide the NRC with a letter on the docket containing detailed recommendations for fire protection functbnal  !

inspection pilot program follow-on activities.

Project No. 689 -

1 Attachments: As stated cc w/att: See next page I

u.

LIST OF ATTENDEES AT MEETING WITH THE NUCLEAR ENGERGY INSTITUTE .

HELD IN ROCKVILLE, MARYLAND ON DECEMBER 14,1998 NAME AFFILIATION L. Marsh NRC K. West NRC P. Madden NRC L. Whitney NRC D. Modeen NEl F. Emerson NEl J. Hyslop NRC S. Wong NRC S. Kim Korea Institute of Nuclear Safety T. Sutter Bechtel )

R. Huston Licensing Support Services l D. Parker Southern Company )

D. Stellfox McGraw-Hill l i

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Attachment 1 l

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9 MEETING AGENDA NEl/NRC FIRE PROTECTION FUNCTIONAL INSPECTION PILOT PROGRAM FOLLOW-ON ACTIVITIES, AND DISCUSSION OF FIRE-lNDUCED CIRCUlT FAILURE ASSUMPTIONS FOR VARIOUS CABLE CONFIGURATIONS i DECEMBER 14,1998 ,

1 2:30- 2:45 Discussion of NEl and NRC Perceived Strengths and Weaknesses of the Pilot FPFI Inspections 2:45-3:15 Presentation of NEl Licensee Self-assessment Review Proposal e Independence of Lice nsee Assessments j e Risk-informed Characteristics of Licensee Self-assessments I e Scope and Depth of Licensee Reviews l e Conduct of Fire Protection Reviews Using Distinct " Modules" (Derived i from the NRC's FPFI Pilot Program Temporary Instruction) e Frequency and Prioritization of Module Scheduling

• Jointly Developed NRC/NEl Performance Indicators )

• Licensee Tracking of Corrective Actions J e Regularly Scheduled Self-Assessment Reviews by Regional Offices e Conduct of Major, infrequent NRC FPFI Team inspections (Based on ,

Regulatory and Safety Thresholds) )

3:15 - 3:30 Break 3:30-4:00 NRC Feedback on NEl Proposal /Open Discussion of All Possible Follow-on Options l 4:00 - 4:30 Electrical Cable Configurations and Related Fire-induced Hot Short Analytical Assumptions e No Second Failure within a Multi-conductor Cable e Failure within Fire-exposed Conduit e Other Configurations as Presented by Meeting Participants i

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ATTACHMENT 2 ;

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I Industry / NRC Meeting l Status ofIndustry Efforts to Address:

Fire Protection Assessments Fire-Induced Circuit Failures December 14,1998 White Flint

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l Overview

]

. Proposals for fire protection assessment

. Background (industry proposal at November 10 N RC workshop) l

. Current proposal

. NEl Circuit Failures issue Task Force plans

, TEI l

Fire Protection -

Assessment _

, TEI _- _. _ _. _ _ _ _

ATTACHMENT 3 1

I NEl FPFI Recommendations, 11-10-98 NRC Workshop e Advantages

. Systemanc process for assuring strong FP/SS programs

. Integrates into generic assessment process changes

. Cost efrective for plants

. Reduces NRC resource requirements

. Uses NRC guidance

. More performance-based I  :

NEl FPFI Recommendations, 11-10-98 NRC Workshop e Plants perform systematic fire protection / safe shutdown self-assessments

. Integrated into revised assessment process being developed by industry and NRC e NRC develop inspection modules from existing FPH inspection guidance

. Clear performance criteria in modules

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I NEl FPFI Recommendations, 11-10-98 NRC Workshop e Plant self-assessments on an ongoing basis

. At least one individual from another utility on assessment team

. Use all NRC modules over space of several years

. Repeat cycle when all neodules utilized

. Initially use vertical slice self assessment to establish priorities for module use

. Eventually use performance criteria for

. Pnoritirms nodule use -~ -

. Estabinhms length of assessawnt cycle gg 2

w ___

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l NEl FPFI Recommendations, _

11-10-98 NRC Workshop e NRC and industry develop seceptable s j

performance indicators for module areas by ]

December 1999 j

. NEl form new issue Task Force to work with NRC j l

= NRC discontinues FPFis '

. Current format too resource intensive

. NRC provide oversight commensurate with plant self-assessments process through hmited regional NRC assenmenu EI )

{

1 NEl FPFI Recommendations, I

] _

j 1

11-10-98 NRC_ Workshop

~ ~ ' ~ -

a Self-assessment findings reflected in existing plant corrective action programs

. Appropriate priorities assigned

. Improvements made in timely manner appropriate to pnority

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l Fire Protection Assessment: - _ _ .

Current Industry Proposal e Industryrole e NRC role w4- -w

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-l A New Assessenent Process

= Regulatory oversight recofnmendations integrate licensee audits /self-assesstnents into regulatory 1 oversight l

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= NEl approach for regulatory oversight

. Thresholds for NRC acuon

. Routine level of eversight focused te perforuunce

. Acgulatory threshnid for increased NRC inspectue before safety tnreshold reached

. Safety threshoki for overt regutmory action to assure pubhc heakh A saft. -

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I Industry Proposal: .

Supporting Considerations

. Industry guidance should be co.',si, vent with, and integrated into, developing changes a NRC ov. rsight and assessment

. Use performance indicators to morror and a-e :s' '.e .

proiccison and safe shuidown progra,

. Use regulatorv and safety thre^ < .o, ' tea ame regulatory activity  ;

1.icer'i sees have primary role in monitoring and assessing  !

programs; regulatory activity increases below regulsiory threshold EI l

_ Industry Proposal: Supporting Considerations

-~

. Industry assessment guidance should offer plants a way to monitor and impreve performance through self-assessment

. Plants with strong fire protection and assessment prograres should not be subjected to increased mspection

. Ali phnts should have the opportunity foi .ff. ,

assessment and improvement before being subject to increased regulatory oversight ---

EI -

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1 J l FP Assessment: NRC Role

. Short term (CY 1999) .

. Complete module development from inspcetion guidance i

. Dewlop appropriate perfomunes cracru with input from industry

. Differentate regulatory requeenrat modules from those involvmg good practices or other suessowns goals --

. Plan role of FPfis

! . Linut FPFh ncept where safety thresho J reached (yellow band)

., Y' _ _ _ _ . _ _ . , . . _ _ _ . _ . _ _ _ . . _ _ . _ _ -

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I FP Assessment: Industry Role

. Short term (CY 1999)(generic)

. Industrj mput to NRC mapection manual revisions:

. use NRC nodules addreuing tegulatwy requurments

. Perfwm a self-assessnwns of a module area mbw de perfonnance irdicator(s) reach the regulatory threshold (whim band)

. Allow approprinte credit for other assessnwnts(tiennial audas, etc.)

. Fud auessmets resuhn into plant corrective acten programs EI I

FP Assessment: Industry Role - --

= Short term (CY 1999)(generic)

. Form new NEl issue Task Force to propose appropnate performance critena and inputs to fire protection  !

rensions to inspection manual

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I i FP Assessment: Industry Role

. Short term (CY 1999)(plant-specifici

. Plants pnontue initial use of NRC modules on

. Resuka of recent audits or asseurnents, or

. Detailed knowledge of plant conditems, or

. Vertical slict self.assenmenits

. Plants contmue other required audits / assessments

. Plants provide plans and schedules to NEl for miormation - -

' EI 1.s 2

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I FP Assessment: NRC Role e Long term

. Conduct fire protecuon inspection activity consistent with nsk informed bascime inspection program

. Conduct FPfis only when plant indicators reach safety threshold

,, TEI I

FP Assessment: Industry Role e Long term

. Plants conduct self-assessments consistent with revised assessment and oversight role

,, %EI I

1 Fire-Induced Circuit Failure _

Resolution

,w ew -eNe * '&+-

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i Circuit Analysis Guidance Products a nree organizations addressing this issue; different products, consistent guidance

. NElITF. propose safety significance determination method for discussion with NRC carly 1999

. DWROG guidance for BWR memters; LTR submittal .

for SER

. NFPA to be addressed in Standard 805; to be issued in 2000 QEI i

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Circuit Failures ITF

= Risk informed soproach to addressing potential y Y

circuit failures includes

. Cable failure n. ode:

. Types of cable fa hres o be considered

. Risk information

. Frequency /probabdity of.mndamns leadmg to danugmsr us

. Recovery

. Systren redundancy

. Regulatory Guide 1.174 elements El

. Tradamnal deurminisuc consideratens a ,

i Proposed Tools a First, apply generic method for addressing potential multiple failures involving cable to cable (C/C) and other interactions e Which ones can be screened out

. Which ones should be considered further e in parallel, consuler irnpact on defense-in-depth, safrty margins, etc. [AW genenc industry guidance

. Result: Some potential failures screened out

. V' _

4 4

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' Proposed Tools -

. Second, apply plant-specific risk methods - - - - -

. Determine frequency of damaging Gres or probabihty of conditions supporting damaging Srcs

. Determine probability of recovery of equipment e Detennine availability of redundant equipment

. Calculate PSA impact and compare with e.tablished criteria for risk sigmficance

. In parallel, consider impact on defense-in-depth, safety margins, etc, IA W generic industry guidance

. Result: Further potential failures gg screened out ,,

I Proposed Tools

= Bird, analyze remaining potential failures through traditional deterministic analysis methods

= Fourth, take appropriate action to address any remaining potential failures deemed safety significant

. Fifth, document analysis

,, Y' I

I Cable Failure Modes: )

Generic Analysis  !

e Primarygoal

. Determine genenc likelihood of multiple circuit failures involving C/C interactions for a broad range of cabies .

and conditions

. If low. can climmate large fraction of potentia' multiple circuit failures .

. Secondary goal

. Determine generic hkelihood of multiple circuit failures ~^~

~ ~ ~ ~ ~ ^

in single multi <onductor cables EI

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I Plant-Specific Risk Analysis -

e Frequency ordamaging fires or probability of conditions supporting damaging fires

. Fire initiation frequency

. Fire exposure

. Location

. Growth (T,-l19 ewve)

. Size and cornbustibles ,

. Daniers

. Detection and mar.ual suppression

. Automatic suppression gg l

Plant-Specific Risk Methods e Probability of recovery of equipment

. Automatic recovery

. Operator action

. Availability of redundant equipment

. Random failure

-~

. Loss due to fire s, 't"'

i Committee Actions

. Generic circuit failure rnodes analysis

.1-3199 Dran matrix of failure combinations

. 2 28 99: Dran program plan for achieving goals

. Addresswainsneeds

. Address saalysis requirements

. Censuler RES research actmies. NRR vues ,

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' Committee Actions

. Plant-specific risk analysis methods

.1 15-99 Detailed outline for methods and their use 2 28 99 Methods drafted a Deterministic rnethods .

. 2 28-99: NEl draft for application of methods /

considerauons

. Tradammal determinhuic methods

. Considersion of defense in depth, sarcty nwges, etc.

. T"'

r )

I I 1 Committee Actions a Proof of concept / pilot 3-1 to 4 30 99: Method applied on a trial basis at one or more plants e Progress reports to NRC and NRC feedback on a continuing basis

,. %EI l

Requested NRC Feedback e Specific cir:uit configurations to be considered i e Comments on proposed method for addressing potential circuit failures

. Recommended areas for additional work to make )

methods acceptabic

~ ~ ~ ~ ~ ~~

. Response to NEl recommendations "

for QEI EGM 98-002 ..- . .---.-.- -

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Nuclear. Energy institute Project No. 689 cc: Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute Nucsar Energy Institute Suite 400 Suite 400 1776 l Street, NW 1776 l Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charlas B. Brinkman, Director Programs Washington Operations Nuclear Energy lastitute ABB-Combustion Engineering, Inc.

Suite 400 12300 Twinbrook Parkway, Suite 330 1776 i Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Engineering Nuclear Energy Institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Jim Davis, Director Operations l Nuclear Energy Institute Suite 400 1776 i Street, NW 1Nashington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation

' P.O. Box 355 Pittsburgh, Pennsylvania 15230 l 1

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-Distribution: Mig.' Summary w/ NEl re Fire Protection Dated 3,,1 v 9 1000

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