ML20207A994

Summary of 990428 Meeting with NEI in Rockville,Maryland Re Progress of NEI Task Force on Control Room Habitality.List of Meeting Attendees & Meeting Presentation Slides Encl

ML20207A994
Person / Time
Issue date:	05/25/1999
From:	Stewart Magruder NRC (Affiliation Not Assigned)
To:	Carpenter C NRC (Affiliation Not Assigned)
References
PROJECT-689 NUDOCS 9905280079
Download: ML20207A994 (16)

Text

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May 25,1999 1

L MEMORANDUM TO: Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial j

and Rulemaking Branch Division of Regulatory Improvement Programs l

Office of Nuclear Reactor Regulation l

i FROM:

Stewart L. Magruder, Project Manager " Original' Signed By" i

Generic issues, Environmental, Financial and Rulemaking Branch Division of Regulatory improvement Programs l

Office of Nuclear Reactor Regulation

SUMMARY

OF APRIL 28,1999, MEETING WITH THE NUCLEAR ENERGY INSTITUTE (NEl) REGARDING CONTROL ROOM HABITABILITY Cn April 28,1999, representatives of the Nuclear Energy Institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. provides a list of workshop attendees.

The purpose of the meeting was to discuss the progress of the NEl Task Force on control room habitability. Attachment 2 provides the meeting agenda. Following the introductory remarks by representatives of the NRC and NEl, NEl discussed their guidance document NEl 99-03, Control Room Habitability Assessment Guidance. This document is currently in a draft form undergoing utility review. Attachment 3 is the Table of Contents of the document. The NEl presentation provided an overview of the contents of each of the sections of the draft document. contains copies of the NEl view-graphs presented at the meeting. Discussions focused on control room envelope integrity and its determination, attemative ways for assessing this integrity and provisions for the establishment of sound technical bases fro such alternate approaches.

NEl indicated that they wouM be providing the NRC a copy of NEl 99-03 in mid-July. After allowing time for staff review, enother NRC/NEl meeting would be held.

Project No. 689 1

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

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l DISTRIBUTION: See attached page l

Document Name:p:\\msum0421 1

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05/4/99 05/N/99 05/h99 DATE 05/9c/99 J

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i 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 Nuclear Energy Institute Suite 400 Suite 400 1776 l Street, N'N 1776 i Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charles B. Brinkman, Director Programs Washington Operations Nuclear Energy Institute 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 Mr. Robert R. Campbell, President Engineering Nuclear HVAC Utilities Group Nuclear Energy Institute Tennessee Valley Authority Suite 400 1101 Market Street, LP4J-C 1776 l Street, NW Chattanooga, TN 37402-2801 Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Mr. Dennis Adams Licensing Nuclear HVAC Utilities Group Nuclear Energy Institute Comed Suite 400 1400 Opus Place 177S I Street, NW Downers Grove, IL 60515 Washington, DC 20006-3708 Mr. Nic' holas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 l

Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 i

1776 i Street, NW l

Washington, DC 20006-3708

O P/-8s Distribution: Mtg. Summary w/ NEl/NHUG Control Room Habitability Dated Mav ps 1909 Hard Copy PUBLIC-, a PERB R/F OGC ACRS SMagruder JHayes EMail SCollins/RZimmerman BSheron WKane GHolahan TCollins RBarrett MReinhart MBlumberg JLee MHart LBrown REmch Fdoehnert, ACRS TEssig GTracy, EDO JHayes

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MEETING ATTENDEES l

NAME ORGANIZATION i

Jack Hayes NRC/NRR Rich Barrett NRC/NRR Mark Blumberg NRC/NRR Mark REinhart NRC/NRR Jay Lee NRC/NRR Michelle Hart NRC/NRR Leta Brown NRC/NRR Rich Emch NRC/NRR Paul Boehnert NRC/ACRS Bemie Jwaszewski Vermont Yankee Steve Leonard Niagra Mohawk Sid Powell Florida Power Corp.

Nancy Chapman SERCH/Bechtel Glenn Slinson Niagra Mohawk Gopal Patel NUCORE John Cotton Entergy John Duffy PSE&G Ken Rubin Ken Rubin Enterprises Lars Ahlman Raytheon Nuclear Inc.

Robert Campbell WA Terry Sims Southern Co.

Kurt Cozens NEl Dave Modeen NEl Len Azzarello Duke Power Jim Metcalf Polestar Bill Hopkins Bechtel Karl Warkentin TU Electric Rick Kohrt AEP Ken Jha Bechtel i

f 1

r-p Meeting l

Status of NEl Activities on l

Control Room Habitability at Operating Reactors i

l April 28,1999 l

Agenda introductions J. Hayes D. Modeen NRC Reorganization R. Barrett Status of NEl CRH Task Force Activties K. Cozens Open Discussion All Future Actions All Concluding Remarks J. Hayes

I

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NEl 99-03 [ Draft A)

Nuclear Energy Institute Control Room Habitability Assessment Guidance 1

l l

l April 1999 l

1 Nuclear EnergyInstitute,17761 Street N W., Suite 400, Washington D.C. (202.739.8000)

NEI 99-03 (Draft, Rev. A)

April 1999 TABLE OF CONTENTS EXE C UTIVE S UMMARY..................................................................................... i 1

I N TR O D U C TI O N....................................................................

2 CHALLENGES AND OPPORTUNITIES WITH CONTROL ROOM H AB ITABI LI TY..........................................................................

2.1 C HAL L EN G E S....................................................................................

2.1.1 Co n t rol Room I n ica ka ge................................................................................ 4 2.1.2 Design B asis Acciden t Scope Iss u e................................................................. 7 2.1.3 Completion of TMI Action Item IILD.3.4. Issue........................................... 7 2.2 O PPO RTUNITI ES......................................................................................... 9 2.2.1 Alternate Source Term and Dose Conversion Factor Insights.................... 9 2.2.2 Plant Ch ange Process (10 CFR 50.59).......................................................... 9

2.3 ASSESSMENT

OF ISSUES AND FOLLOV '-ON ACTIONS.............................. 10 2.3.1 Co n t rol Roo m I n le a k age............................................................................... 10 2.3.2 Des ig n B a s is Accid en t S cope......................................................................... 15 2.3.3 Completion of TMI Action Item III.D.3.4....................................................15 3.

PLANT DESIGN AND LICENSING BASES........................................... 16 3.1 PIANT DESIGN AND LICENSING BASES TERMINOLOGY........................ 16 3.2 HISTORICAL EVOLUTION OF DESIGN AND LICENSING REQUIREMENTS AND G UI D AN CE........................................................................................ 1 I

i r

3.3 ESTABLISHING PLANT-SPECIFIC DESIGN AND LICENSING BASES......... 20 I

3.3.1 Des i g n B as es R evi e w...................................................................................... 2 0 3.3.2 Licen s i n g B a s es Review................................................................................. 2 0 3.3.3 Co m pilation an d Ve rifica tio n....................................................................... 21 4

TYPICAL CONTROL ROOM HABITABILITY CONSERVATISMS........... 33 l

l 111 f.

i NEI 99-03 (Draft, Rev. A)

April 1999

4.1 ASSESSMENT

OF TYPICAL CONTROL ROOM HABITABILITY ANALYTICAL C ONS E RVATI SM S..................................................................................... 3 3 4.1.1 Thyroi d Dose L i m i t...................................................................................... 3 3 4.1.2 Con tain men t Sprays Ass u mption s............................................................. 3 5 4.1.3 S p r ay ed Regi o n............................................................................................ 3 5 4.1.4 Removal Margin in the Sprayed Region...................................................... 36 4.1.5 M argin in th e Un sprayed Region................................................................. 3 7 4.1.6 M argin in th e Unsp rayed Region............................................................... 3 7 4.1.7 Worst Case Meteorological Conditions for Toxic Gas (RG 1.78).............. 37 4.2 SAMPLE CALCULATIONS OF TYPICAL CONSERVATISMS....................... 55 4.2.1 Methodology And Examples Used To Estimate The Level Of Co n s e rva tis m I n Ex a mples............................................................................ 55 4.2.2 Loss of Coolant Accident Calculation of Total Conservatism................... 56 4.2.3 Main Steam Line Break Sample Calculation (Non-LOCA Example)...... 60 4.2.4 Fuel Handling Accident Example Calculation (Non-LOCA Example).... 61 4.2.5 Steam Generator Tube Rupture Example Calculation (Non-LOCA Example).........................................................................................................63 4.2.6 Toxic G as An alysis Sample Caleulation....................................................... 64 5

FO LLOw-O N A CTI O N S...................................................................... 6 5 5.1 ACCEPT THE AS FOUND CONDITION...................................................... 65 5.2 CHANGE IN PLANT CONFIGURATION WARRANTED............................... 66 5.3 ADDRESSING DISCRE PANCIES................................................................. 66 6

R E FE R E N C E S.............................................................................. 6 8 APPENDIX A - REGULATORY REQUIREMENTS AND GUIDANCE...............1 A.1 REG ULATORY REQUIREM ENTS................................................................. 1 A.1.1 Allowable D ose Co n seq u en ces........................................................................ 1 A.1.2ToxicGas..........................................................................................................1 A.1.3 S o u rc e Te r m s.................................................................................................... 1 A. 2 RE G U L AT O RY G UI D AN C E.......................................................................... 2 1V

NEI 99-03 (Draft, Rev. A)

April 1999 A.2.1 Regulatory Guides and Staodard Review Plan............................................. 2 A.2.2 S o u rc e Te r ms...................................................................................... 2 A.3 KEY CON SIDE RATI ON S.............................................................................. 2 A.3.1 A ccid e n t sc ope................................................................................................ 2 A.3.2 A tm ospb e ric Dis pe rs io n................................................................................... 5 A.3.3 Ot h e r Co n sid e ra ti o n s................................................................-..................... 5 APPENDIX B - CONTROL ROOM RADIOLOGICAL AND TOXIC GAS ANALYSES 1 B.1 B ACKG RO UND....................................................................................... 1 B.I.1 Basic Atmospheric Dispersion Analyses...........................................................1 B.1.2 Mu rphy & Campe An alysis (1974)......................................................1 B.1.3 Su mmary of c/Q S tudies from 1976 to 1994..................................................... 2 B.1.4 A RCO N Cod e Develop m e n t.............................................................................. 2 l

B.2 THE ARC O N 96 M ODE L........................................................................... 2 B.2.3 Comparison Of ARCON96 With Murphy-Campe....................................... 4 B.2.4 I mplemen tation S trategies..................................................................... 6 B. 2.5 C o n c l u s io n s..................................................................................................... 9 V

I Control Room Habitability l

Status of Industry Activities de i

i Meeting Purpose To brief NRC staff on industry activities since the l

July 1998 control room habitability (CRH) workshop

• Presentation will

- Characterize safety significance of issues identified at workshop

- Discuss tools available for licensees to address issues

- Identify and discuss future tasks and interactions with NRC staff a ?

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Summary of NEl Activities Formed NEl Control Room Habitability Task Force Prepared NEl 99-03, Control Room Hi.Ditability Assessment Guidance document

- Draft sent to industry for review

- Comments due to NEl by mid-May

- Revise document by July 1999 Will provide NRC staff a copy of the revised draft guidance document Issue final document to industry after discussion with NRC staff d.

Status ofIndustry Actions on NRC Recommendations

~-

N RCM a c e m m e n'd a lio n in d u s try d s tlo n D e te rm in a tion of C ontrol D ra ft N E l 9 9 0 3 pro vide s R oom en velop e in te Crity g uid a n c e Re assessment of Draft N El 99 03 provides a ppropria tirie s s of a ccide nt g u id a n c e a s s u m p tio n s V e rific a tion of co ntrol roo m D raf t N E i 9 9 0 3 pro vid e s a n d co n trol room ve n tilation g u id a n c e system design and ope ratio n rela tive to th e lice n sin g b a sis in c o rp o r a tio n an to te c h n ic a l Not considered necessary s p e cific a tto n s re q uire m e n ts for p eriodic d e m on stra tion o f controt room envelope in te g rHy E q uivalen t organ dose a A g re e w ith 60 re m an yroid limit 50 rem thyroid for current source term. TE D E lim it b e tra g a d d re s s e d a s p a rt o f the alternate source term rule a n d te g ula tory g uld e.

C lo s e-o u t o f T M i llLD.3.4 Affected heensees w ork witn l

re m n a n ts N R C: m ay apply alternate s o u rc e te rm in re s olu tio n d.

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l NEl 99-03 Section 1, Introduction Section 2, Challenges and Opportunities with ControlRoom Habitability

- Emergent technicalissues

- Research insights and operating experience

- Guidance to perform assessment and follow-up actions of emergent issues Section 3, Plant Design and Licensing Bases

- Key considerations relevant to defining licensing commitments and regulatory compliance 7

e NEl 99-03 (continued)

Section 4, Typical Control Room Habitability Conservatisms

- First-order estimate of conservatisms in typical CRH evaluation Operator DBA dose: LOCA, FHA, MSLB, and SGTR

• Conservatisms are estimated to be approximately 1 to 2 orders in magnituds a Toxic gas exposure

• Conservatisms are estimated to be approximately 1 order in magnitude

- Conclude that the identified issues are not near term safety concerns

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7 NEl 99-03 (continued)

Section 5, Follow on Actions

- Possible action arising from plant assessments per Section 2 Based on NEl Report 97-04, Design Bases Program Guidelines

- Possible cctions a Acceptable as is a Re-analysis to support existing plant design and licensing basis required n Warrants changes

• Physicalmodircaten

• Procedure modirobon d.

Assessment of issues and Follow-on Actions Control Room Inteakage (Radiological or Toxic Gas)

- Establish licensing basis

- Perform sensitivity study of CRE considering industry test results a No further assessment needed if unlikely to exceed licensing limits a Perform extra maintenance,if approaching licensing limits a Consider inleakage test per ASTM E 741 to establish actual inleakage if study indicates reasonable possibility to exceed licensing limits

= Pre-inleakage test maintenance recommendatons provided 5

a.

Assessment of issues and Follow-on Actions (continued)

Design Basis Accident Scope

- Confirm that changes to design basis accident (DBA) parameters have not altered limiting accident

> Examples: MSLB, FHA, SGTR

- If limiting DBA changed, correct licensing basis Completion of TMI Action item lli.D.3.4

- Review licensing basis for any open Ill.D.3.4 items

- if open items exist, evaluate considering altemate source term o Discuss appropriate action with NRC project manager M.

11 Summary Identified issues have limited safety significance Compliance issues must be resolved in a time frame consistent with safety significance NEl 99-03 provides proactive guidance to licensees on CRH issues Generic NRC request for licensee action is not warranted Future meeting warranted after NRC receives a

revised NEl 99-03

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