ML20154R566

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Summary of 980716 Meeting with NEI in Rockville,Md Re Control Room Habitability.List of Workshop Attendees Encl
ML20154R566
Person / Time
Issue date: 10/16/1998
From: Stewart Magruder
NRC (Affiliation Not Assigned)
To: Essig T
NRC (Affiliation Not Assigned)
References
PROJECT-689 FACA, NUDOCS 9810270088
Download: ML20154R566 (97)
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{{#Wiki_filter:~ _ _. ~. _ _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _. _. _. _ _ _. a ut k y UNITED STATE 8 s j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enana anni p***** October 16r 1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Stewart L Magruder, Project Manager 4.Ayc( A 6 Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF JULY 16,1998, WORKSHOP WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING CONTROL ROOM HABITABILITY On July 16,1998, representatives of the Nuclear Energy Institute (NEI) met with . representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland.- Attachment 1 provides a list of workshop attendees. The purpose of the workshop was to discuss control room habitability and radiological dose . assessment issues. Attachment 2 provides the workshop agenda. Following the introductory remarks by representatives of the sponsors of the workshop, the NRC discussed the regulatory requirements associated with control room habitability and the manner in which these requirements are applied. Mr. Carl Terry of Nine Mile Point discussed the licensing basis for - control room habitability as applied to one facility. This was followed by the NRC detailing recent control room habitability issues. These issues included the results of tracer gas testing which demonstrated that control room envelope integrity was inconsistent with the licensing basis; plant specific remnants of TMI Action item Ill.D.3.4, Control Room Habitability; licensees and NRC inspectors identifying design, operating, or integrity flaws and/or discrepancies with the plant's licensing bases; license amendments which do not address, or inappropriately address, control room habitability; and 10 CFR 50.59 unreviewed safety questions involving control room habitability. . The NRC provided data which showed that of the eight plants which have performed tracer gas I tests, none have met their licensing basis value for inleakage. Inleakage values have ranged from 71 - 4,300 cfm, factors of approximately 1.4 - 55 times greater than the !eakage assumed fM in the licensing basis. Even though TMI Action item Ill.D.3.4 has been closed, many plants continue to carry open control room habitability issues on a plant specific basis. . The NRC has also identified deficiencies in the control room habitability analyses presented by licensee for several recen; cense amendments involving power uprates, steam generator tube alternate repair criteria and steam generator replacements. Additional weaknesses associated with the analyses themselves were discussed. A portion of the presentation dealt with control 9810270088 981016 M RE N ER M M (; W pp gg9 . 9 E V G/i&J l

f T,' Essig room atmospheric dispersion parameters including comments on the methodologies to calculate such parameters and information which should be contained in submittals supporting the values for such parameters. The NRC also discussed some of the contributors to the control room habitability problems including weaknesses associated with the technical specifications. Pete Lagus, Lagus Applied Technology, Inc. presented information on the use of tracer gas techniques on control room envelope air inleakage. A panel consisting of representatives from three operating plants, the president of the nuclear HVAC utility group (NHUG), and an attorney from Winston & Strawn . discussed control room envelope reconstitution, control room habitability issues and recovery actions, tracer gas testing at Prairie Island and control room habitability legal / licensing issues. In its last view-graph, NRC proposed to industry a possible solution to control room habitability issues. NEl indicated that the information presented at the workshop would be assessed by an j industry task force and that a meeting would be held with the NRC some time after Labor Day. l contains copies of the view-graphs which were presented at the workshop. Project No. 689 Attachments: As stated cc w/att: See next page DISTRIBUTION: See attached page ,/. OFFICE PM:PGEB PERB* SC:PERB SC:PGEB - NAME SMagruder:M JHayes REmch(( FAkstuidwicz DATE 10/l$ /98 10/14/98 10//fT98 10/ o /98 a

T. Essig roorn atmospheric dispersion parameters including comments on the met odologies to calculate such parameters and information which should be contained i submittals supporting the values for such parameters. The NRC also discussed some of the contributors to the control r om habitability problems including weaknesses associated with the technical specificatio s. Pete Lagus, Lagus Applied Technology, Inc. presented information on the use of tracer g s techniques on control room envelope air inleakage. A panel consisting of representativ s from three operating plants, the president of the nuclear HVAC utility group (NHUG), and attorney from Winston & Strawn discussed control room envelope reconstitution, control om habitability issues and recovery actions, tracer gas testing at Prairie Island and control com habitability legal / licensing issues. The NRC proposed to industry a possible solution t control room habitability issues. NEl indicated that the information presented at the wo shop would be assessed by an Industry task force and that a meeting would be held with the RC some time after Labor Day. contains copies of the view gra s which were presented at the workshop. Project No. 689 Attachments: As stated cc w/att: See next page DISTRIBUTION: See attached pa [PEpp, OFFICE PM:PGEB SC:PERB SC:PGEB SMagrudeNk JNa[7 NAME REmch FAkstulewicz DATE 10/ W /98 [ 10//(//98 10/ /98 10/ /98

T. Essig room atmospheric dispersion parameters including comments on the methodologies to calculate such parameters and information which should be contained in submittals supporting the values for such parameters. The NRC also discussed some of the contributors to the control room habitability problems including weaknesses associated with the technical specifications. Pete Lagus, Lagus Applied Technology, Inc, presented information on the use of tracer gas techniques on control room envelope air inteakage. A panel consisting of representatives from three operating plants, the president of the nuclear HVAC utility group (NHUG), and an attorney from Winston & Strawn discussed control room envelope reconstitution, control room habitability issues and recovery actions, tracer gas testing at Prairie Island and control room habitability legal / licensing issues. In its last view-graph, the NRC proposed to industry a possible solution to control room habitability issues. NEl indicated that the information presented at the workshop would be assessed by an Industry task force and that a meeting would be held with the NRC some time after Labor Day. contains copies of the view-graphs which were presented at the workshop. Project No. 689 Attachments: As stated cc w/att: See next page

Nuclear Energy Institute Project No. 689 i i 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, NW 1776 l StreetiNW 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 l Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Engineering Nuclear Energy Institute Suite 400 1776 i 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. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory A:tivities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 t

Distribution: Mtg. Summary w/ NEl/NHUG Control Room Habitability Dated 10/16/98 Hard Cooy PUBLIC PERB R/F OGC ACRS SMagruder JHayes EMail SCollins/FMiraglia BSheron BBoger JRoe DMatthews TEssig CMiller REmch JJang, R1 KKolaczyk, R1 MBlumberg JLyons JSegala HWalker WBurton BZaleman AKug!er PMilligan Slavie GMizuno, OGC RBellamy PTam LBrown MHart GTracy, EDO ,-g n I C '_ a

_... _ ~ -. -.. -. -. - CONTROL ROOM HABITABILITY WORKSHOP 7/16/98. List of Attendees Name Oraanization - Ray Runowski PSE&G ~ Bill Weinbecker PSE&G- ' John Butler NEl John Cotton - Entergy-ANO Bill McGallian Comed Dave Modeen NEl Jin-Shou Hseu .WCNOC Michael McGill PECO Energy. Carl Battistone Duquesne Light Co. Mike Radvansky. GPU Nuclear Frank Kennedy First Energy John Osborne BGE William Johnson Sargent & Lundy 'Dixon Yee PG&E L Nadi Moralidhara lilinois Power Bryan Ford Enter gy Dave Campbell STPtJOC j Gary Re NYPA Dennis Buschbaum TU Electric Dom Ramos . Parsons ^ William Waldrop South Carolina Electric & Gas Gerard Gryctkowski BG&E Jason Jang NRC Kurt Doten PSE&G Gopal Patel NUCORE John Duffy. PSE&G Mansour Mujibian . Sargent & Lundy Brian Thomas. PSE&G Peter Freeman NUCON Peter Dorosko CP&L ' Mark Blumberg NRC - Mark Drucker SCE Peter Lagus' LAT Dick Grot .LAT - Mark Turkal ' CP&L. David Distel GPUN AdiIrani GPUN Tim Sims ' Alliant 4 7 9 f" m-e. w w w . V

~-.. l* 1 Name Oraanization Mark Ackerman AEP Denise Wolnlak NMPC Jerry Sims Southem Nucleer Lora Polley - NSP-Prairie Island Andy Wehrenberg .Southem Co. Services Bradly McMahon l-Bernard Mierzejenski: .. Wisconsin Public Service OPPD Brad Serfas 'OPPD-Lewis Motley PSE&G Jim Little Ameren-UE i Dennis Adams NHUG/ Comed Deep Ghosh Southem Co. Robert Temple Winston & Strawn Dave Studley. Scientech-NUS Theresa Sutter - Bechtel

Ken Kolaczyk NRC Stan Devena WCNOC Pat Bennett GPUN Brad Parfit GPUN-Karl Warkentin TU Electric Sid Powell Florida Power Steve Watkins AEP

-_ Carl Terry. Niagra Mohawk Steven Osting First Energy John Lebda Duquesne Light Co. Randal Allen PG&E James Perry - Duke Energy Steven O'Riley lilinois Power Ray Crandall Florida Power Kathy Shriver - Northem States Power Everett Whitaker TVA Bruce Heida - Wisconsin Public Service ~ Dan Crowley Rochester Gas & Electric Enck Jun t OPPD Glenn Stinson Niagra Mohawk . Tim Lupold BG&E Tom Byme PECO Jim Lyons ~ NRC ' John Distefano. Duke Engineering & Services Jim Wheeler Northeast Utilities Gary Statton-lilinois Power Rich Emch NRC-Jeff Gundersen Wisconsin Electric Jack Bell N/A Linda Dewhirst NPPD John Segala. NRC Harold Walker NRC

i Name Oraanization Ken Rubin Ken Rubin Enterprises - Mark Pest - APS l William Burton. NRC Robert Campbell TVA Barry Zalcman NRC l. Jack Roe NRC l Mark Saucier SSM Industries Thomas Mogren Niagra Mohawk Jeff Kivi Northern States Power Andy Kugler NRC Francisco Rodriguez Nucienor UNESA Ralph Anderson NEl Balwant Sinigal _ Bechtel ' Patricia Milligan -NRC Jeffrey Poska Duke Engineering & Services John Pearson NCS Corp. ~ Steve LaVie NRC Dan Thomas PECO Bill Hopkins Bechtel Sreela Ferguson Stone & Webster Lopez Montero Nucienor John Russo Entergy Lars Ahlman RE&C N.R. Karipineni Bechtel Geary Mizuno NRC l George Wrobel RG&E Jim Metcalf Polestar Ron Bellamy NRC Peter Tam. NRC' Leta Brown NRC Michelle Hart NRC r l P L

lNDUSTRY MEETING ON ( CONTROL Room HABITABILITY July 16,1998 m NRC Two White Rint North Auditorium a Rockville, Maryland i AGENDA TIME TOPIC PRESENTER 7:45 Registration 8:30-Welcome C. Miller,NRC 8:35 Introductory Remarks S. Collins, NRC 'D. Adams, NHUG D. Modeen, NEI 8:50 Regulatory Requirements for Control Room Habitability NRC \\ and their Application l 9:10 Control Room Habitability Licensing Basis C. Terry, Nine Mile Point j 9:30 Current ControlRoom HabitabilityIssues NRC 10:00-BREAK ( 0:15 Accident Dose AssessmentIssues NRC 11:15 Tracer Gas Testing P. Lagus, Lagus Applied Technology, Inc. 11:45 LUNCH 1:00 Panel Discussion on Industry Experience D. Adans, NHUG B. McGallian, Dresden S. Powell, Crystal River L. Polley, Prairie Island D. L user M j, W&S[ 2:30 BREAK 2:45 Possible Solution NRC 3:00 Industry Comments All 3:30 Closing Comments on ControlRoom Habitability NRCIIndustry 4:15 Laboratory Testing of Charcoal NEC 5:15 ADJOURNMENT

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j N:.? LONG TERM CONDITIONS ~ E SYSTEM MAINTENANCE ~ ( i

l I + 9, p SUBMITTALS- ~ l 's c MORE DETAll NEEDED IN u. ' AMENDMENT REQUEST ~ t SUBMITTALS i ' METHODOLOGY, INPUTS, ASSUMPTIONS l AND THE BASES FOR SELECTION s

l 000000 l Control Room Envelope l 3'J Air Inleakage Testing Using l Tracer Gas Techniques l l Peter L. Lagus, Ph.D., CIH l July 16,1998 j Lagus Applied Technology, Inc. N San Diego, CA ae 3a ~ n. ~ 3. ....a. maamme

000000 i l What is a Tracer Gas? wa 3'J l l m Any gas that can be mixed with air and } that can be sensed making it possible to l follow air movement. Non-toxic, non-reactive, non-allergenic Easily measured at low concentrations Low or non-existent background Free of interference from normal 2l constituents of plant atmosphere B. B. IAGUS AFRED TEOfJOLOGY, INCORFORA1ED

000000 .....t i What is a Tracer Gas Test? y'J i J j A tracer gas test uses a tracer gas to follow the movement of and the changes in tracer 1 concentration so as to measure 1 l the performance characteristics of a ventilation system. } J *iJ 3Q j 3e ae 34 uaeeat 8* Ettttt LAsus AparD TECHNOLOGY. NCORPCRATED {. ~.

e 000000 000000 Why a Tracer Gas Test? QEJ 'J 'J m Directly measures Air Inleakage into j CRE under actualoperating conditions. l m No assumptions about leak site j distribution or system performance j m Directly measures component leakage, i.e. dampers, ducts, shaft seals, etc. JJ e C'ften can locate actual in[or out} leakage d i l sites as an aid.in sealing the CRE. U i j f;= wees5% tttttt l / ucusmuoacauwv.rconeonmo I

CCCCCC 1 l Fundamentalideas behind the E Tracer Gas Technique i j u The movement of a parcel of air with tracer gas is the same as movement of a parcel of air withouttracer gas. u Use mathematical expressions based on j the conservation of mass to calculate consequences of actual air movement. j;j il 30 i i 3B I% 3B ,7 usuut. I matten l -muo ncaxxmuccmmao

I 000000 000000 4 l Who else uses tracer gas i Ff; measurement technology? m Environmental Compliance Community j u Semiconductor Industry i m Pharmaceutical Industry a Petrochemical Industry j u Military Nerve Gas Destruction Program a Building physics research community aau m Industrial hygiene /lAQ community l

== R. ....a. lAGUS APPLIED TECHNOLOGY. INCORPORATED

000000 Where is Tracer Gas Testing 4 l = used in the Nuclear Industry? ? l l u Plume Impact q' Chi /Q} Verification j u Critical Component Helium Leak Tests j u ANSI N510 Filter Leak Test j u Condenser Leak Testing n Ventilation System Testing n Control Room Envelope Integrity Testing gg J 'J a. I' 3. l 3 l_ _ usuua. - - - --c-.

000000 000005 Development of Tracer Gas P., Ventilation Testing i m Originally, techniques developed by researchers at NBS (now NIST} and similar agencies in other countries. s l m Interest in energy conservation and l defense applications spurred further development and wider dissemination. m Consensus measurement standard M i exists (ASTM E741-93}. $2 i 38 l 5% l f 5 55mm 7 1AGUS APPUED TEONDLOGY. INCORFORATED .[.... -..

000000 i Tracer Gas Ventilation i ee Performance Testing l is based on-i ASTM Standard E741-93 " Standard Test Methods for Determining Air Change in a 1 Single Zone by Means of a 3;g i Tracer Gas Dilution" S' 3. 34 l p teatta = usuuk. mmuowuxa.nxmne j.

~ eese jj Sulfur Hexafluoride, (SF6) Is The Most Commonly Used Tracer Gas a Non toxic, inert, colorless, odorless. m Not a normal constituent of plant atmosphere. m Detectable at very low ~ concentrations 2., ' parts per billion to parts per trillion}. jj fy 3332:: 1AGUS AMLED TECHNOLOGY. INCORPORATED

i 000000 i i Tracer Concentration Decay ] = Test i l n Works best for lower makeup rates. a Provides Total Air Inflow into CRE. 1 l m Must measure makeup to obtain Air Inleakage. l n Must measure volume of CRE. i l m For systems with no makeup, directly n l provides Air Inleakage. n Bt 3. i usuutt lAGUS AFPLED TECHNOLOGY. NCORFORATED 4

i 000000 000000 St i 34 t i CRE Decay Test 44 1 r3 rg I. AHU & Filter Duct l Duct l Inleakage\\ f OutleakaEe s 1 j 'e i i l CR l ~Inleakage l Control Room Envelope ~ ( J9 j J 'J ] 3D 38' Bt tt wuuutt T = 448448 f

  • LAGOSMMDECanOGY.FCCWCMED l

4 .--.-r,*%----- ~--..s--,,.--,,,.---.,m m...-.,---.....-w-=~',-_.-..-.----,-wmwe. ,---,-,--~,.**--.--,,ww-e-v-***,wwww._

i. i' 000000 tttttt i et et ) et et l 99 CONCENTRATION DECAY TEST 'J 'J 100.0 - i TIME CONC 0.00 26.8 Z 0.50 16.2 9 SLOPE = A F 10.0 - 's.,, 1.00 9.8 y

  • a, 1.50 6.0 F

'e z 2.00 3.6 m 4 0 j 2.50 2.2 't' z 1.0 - - 3.00 1.3 O i O %g 3.50 0.8 3 4.00 0.5 0.1 L 0.00 1.00 2.00 3.00 4.00 JJ ELAPSED TIME (HR) JQ 2 3B 30 at 4 at i 8 4WWWII 444444 = a 2 tAGUS APF1JED TECHNOLOGY, INCORPORATED 4 ,w-,, w.w.. ._,r-,,, ,..,~3..-...y,,,,-,... ,,,,,...--,-w,,,._,.r.,-% %,v,.,,,,---%w-g-

00000o o=== on o. 8* -Decay Test Calculations % 'Ii U 'd L -L L MT INLEAK y/y L,, - A e V L A*V L~ INLEAK M/U gg J 'J DG DO Bt t5 iT

====et aIIII% , s *S SE ECHNOLOGY FCmg

C00000 i o..... 3. a. 8' Test Conditions t rg Q ~ 'd J 4 i a Takes 4 to 8 hours - Lower air inleakage rates take longer Can't change ventilation lineup during test a Must ensure that tracer permeates entire CRE i Concentration must be approximately the same everywhere in CRE I e Common test errors usually result in O l higher inleakage values a; an 9%%99% l - u cus m ueo ac><<xosv. w mo ...-.--,..-,.w ---~_=--,..w.~ w- ..-._.---,---..,-.--.-..._...,w.3.-. ,.s. w+-w---....w-v,,,.--w--<a -s e.-w wr, ,w.-.,-w,w-swwi w w w m - ,=e wm-e s-sew w=,

i !~ 000000 i l ll Concentration Buildup / Steady i.. l 33 State Test l m Works best for higher makeup rates. m Provides Total Air Inflow into CRE. 1 m Must measure makeup to obtain Air j Inleakage. I m Often can simultaneously measure makeup using tracer technique. a Measured Inleakage is independent of gg CRE volume. l

== l ucusetronaenoov.remmwo

i 000000

==

== l CRE Buildup / Steady State Test ce IjIj Makeup Duct 4 i Duct f Outleakage i m Inleakage i AHU & Filter i CR j Inleakage i Control Room l Envelope ( J 'J J 'J ne i na ae aa Z_: a amamme LAGUS APPLED TECHNOLOGY. NCORPORATED

i 000000 000ttt %9 44 CONCENTRATION BUILDUP / STEADY STATE TEST 66 gra 40 - UfJ 35 - - Ceq E 30 - - E, z 25 - ^ ^ 9 t--< 20 - - m F-- 5 15 - o z o 10 - - o 5- - JJ 0 J 'J De 0 0.5 1 1.5 2 2.5 3g ELAPSED TIME (HRS) =m ....ea NNNON& LAGUS AFRED TECHNOLOGY. INCORPORATED

t I 'l 000000

==

j 08 Q% i j g* Buildup / Steady State Calculations 1, B CI 'J 'J \\ L L i L TOT INLEAK M/U 1 i 4 1 4 i S L 1 TOT i j eq i i i L L L = i INLEAK TOT M/U JJ I ~ 1 JQ i 34 + ht I Dt Bt usuuat _= i .=5 tttttt

lAGUS AFPUED TECHNOLOGY. FCORFORATED i e 9,* 9-,-, -,,, wer*=r'-*v-g -- ers -$.v-= gw--e-mv w-e w -- e v - ww--s w w -vwi =e se-e2-++wegy--===v.e,-mgg--w~+s-.w-y w -a u t w s gw w% v - +-sme-w=Mie==w-w=-w e - e - e *

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000000 ooo... at 0% 8' Test Conditions aa ,i3g i m Takes 6 to 12 hours J ] Must wait for concentration equilibrium Can't change ventilation lineup during test m Must ensure that tracer penetrates entire CRE m CRE must be well mixed j u Common test errors usually result in j;g higher inleakage values ll 3% 3% useum% i /

  • ucusmuomcmxoov.rcomuwmo l

000000 4 g: Measurement Uncertainty e. l at Can Be Quantified i a Requires detailed understanding of l measurement process m Tracer test errors can be addressed l statistically I m Other measurements may possess only j " engineering uncertainty" estimates J 'J l -Combining these errors is not a statistical jg process n. 3. =- -= IAGUS APPLED TECHNOLOGY. INCCMORATED = ,-.~...,,+-..--~~~.,-,.-~,--.m ,.----...,,,.__.,-__.m-,,.-__.,,,,._m,,,--,__.,--...,,-.--,,__.~.~-_.,-,.---,,,._,.,.+,-.,, ..,.--.wi-,--,-,,,.r.--,---..

000000 ll Knowledge Requirements aa sa a m Physics of air movement in industrial buildings. m Detailed understanding of: Mechanical ventilation system operation -Gas analysis systems Gas sampling techniques JJ -Gas flow measurement methods jg ae 33 34 =T ttt t vcusetto maeaccy.PCCMORAED

i Q00000 o..... o l g:. Measurement System e. l tt Requirements l m All parts of measurement system must be well characterized j l -Must use recognized and appropriate j instrumental techniques j u NIST traceable," tight" calibrations for - Flow measurement system {s} i j Tracer analyzer concentration standards aa J 'J l Tracer injection gas concentrations M l

l 34 wuuuat

==

t .:= s LAGUS APPLIED TECHNOLOGY. NCC& ORATED m-wrq---- --yw-%--e i,=,g.,g-3pww,,-w,-y, yp - w, w -y,w.w-9-ww W 1= N ug '=w*w 'u'**='twe'v'%""ev t*w ' w w 1-v D FT = ' Nw w w e'+ M M e ' F T. wNw e tw e+4eN'M-w M 4 *'e w e t w e -is a w m em 1 wn'* F4 e * *1 m wN

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822222 at 8: Conclusions <II m Air Inleakage into CRE can be ~ aa measured using tracer gas techniques. m Techniques are recognized in other industries for critical applications. m Measured data is not subject to " pencil whipping". m Measurement is based on established experimental technique, hence rigorous k ~ error analysis is possible. 12

t j;

tttt t LAGUS AFPLED TECHNOLOGY INCORFORATED

i / POSSIBLE RESOLUTION .FOR ) CONTROL ROOM HABITABILITY l1.1 l DETERMINATION:i LOF; iCONTROld IROOM? lENVELOPEP i ilNTEGRITY 52h IRE-ASSESsMENTOF! APPROPRIATENESS;OFIACCIDENTs

  1. ASSUMPTIONS)

^ m ~- ~ f3HVERIFICATibN! :OF )CONTROLO RCOM 3AN DMCO l IROOM VENTILATION SYSTEMS l DESIGN AND::: OPERATION; i ! RELATIVE 3TO !THE; LIC ENSIN G:: BASISl-m@_ l l 1Ai TINCORP.ORATIONMINTOlTECHNICAL1jSPECIFICATIONS l lREQUIREMENTSf FORlPERIODIC; DEMONSTRATION EOF-l TCONTROL1 ROOM; ENVELOPE INTEGRITY 1 ^ l j -Si EQUIVALENT 10RGANiDOSEL:c= 50 REM THYROID 7 i l' 56i ~ CLOSEOUT OF TMI Ill.D.3.4 REMNANTSL j.

l l l l Nuclear HVAC. Utility Group Dennis Adams Commonwealth Edison V<NHUGd NHUG ORGANIZATION Dennis Adams-Chairman-Comed Robert Campbell-Vehairman-TVA Larry Phillips-Secretary-Consumers Pwr Ravi Aggarwal-Treasurer-Sargent & Lundy Pete Dorosko-CR HAB SubGrp-CP&L Paul Carr-Maint SubGrp-Toledo Edison Bill Sullivan-Chiller SubGrp-Enercon Jane Connelly-Dbase SubGrp-Proto-Power Lee Graser-Refrig Mgt SubGrp-TVA l @NHUGS ? 1

Control Room Habitability NHUG-Nuclear HVAC Utility Group NHUG CR HAB Subgroup Utility Positions /Conunitments Habitability Models Assumptions Technology Impact fiNHUGiil UTILITY POSITIONS Diverse Licensing Bases Design Bases Commitments 2

l \\ l NHUG Industry Excellence Through Communication and Training i No Dues-Not-for-Profit Formal Forum for Industry Discussion Independent ' Train the Trainer' Meets every 6 months Influence the way we do business-DRIVE THE INDUSTRY kNHUGsl NHUG CR HAB SUBGROUP

  • Open Forum for problem identification and resolution

+ NRC Hot Topics Industry Standardization l l LNHUGhl 3

INFLUENCES UNDERSTANDING COMMITMENTS VS REQUIREMEhTS HABITABILITY MODEL MOST LIMITING ACCIDENT CONSERVATISMS i i h l 1 i e 4

4 44+ b .a-...a.tas-..,. u .<2..x u...s,. ...n a, s s aa u s w.m un.us.m. o as_xe.a..a..u..s.~,..a .an,,,..-,,.-a_.,,a.a,-a,u --s. ~,. ,aas,,,,.ma._._ .-.n._ e $r 1 y.. y I A '1 r; s s o ~ O og 4 4 e e { C M C 7 u i 9 oo 't o m 4 O ~2 q DO C E O O E w" Z

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-t h .h- $.'f f 4 t n-m 4 ahkgulatory Standards wnn - - - ~ s,c.:=- se, em ~ ms--: s

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+-r 3--, y m.. s:cesm e-~<, Ybf.A! t I fj 4 m$bs; Ai!!Fau AM%dh Existing plant licensing bases vary i u e t [g"m f, depending on vintage oi plant and .i o; extent of commitments to GDC-19 and ~ a -m fi SRP a f*iene ff - GDC applicable to plants with CP applications after May 21' 1971 i

  1. 488 a%,

- SRP 6.4 applicable to OL and CP applications g after May 17,1982 e i M W W i 5 n M IVinston & Strawn I

e e e., y ^ a. l%)0{ C.F.R. l50.109 Backfitting en s p- + ~ e:). a-sme.s m:s 2 > rms. sez es;, ,nm m a fp.a-s y j$$ty g$ n Backfitting is the changes to equipment, design orprocedures forfacilities i $($=$$ as a result of new or amended Commission rules or the imposition of a regulatory staffposition interpreting the rules that is new or different from } a previously applicable staffposition. s 1 j gt si Unless the backfitting exceptions are met, a systematic and documented [g] analysisis required forbackfits. hl I e ? a Unless the backfitting exceptions are met, the Commission shallrequire i the backfitting only when it determines, based on the backfitting analysis, } that: Q there is a substantialincrease in the protection of the public health and safety or the common defense and security, and f that the direct and indirect costs ofimplementation for that facility are m& justified in view of this increased protection. l t j Winston & Strawn l g (

l 'e -l .+? "i _ ?! ~+n y s.:: nl LGanclusions Recommendations i m;e wu y p :. ya:....:. 7,;=;.;;;n g.) h k.:., i,;{ e{ l i fliM-4ww w?'..:.: 'cd/s/F / ,%pMrs NRC should be sensitive to differences l ll *p- ] in plant design bases ~~a c ,3 Impacts could be great on olderplants g m%f NRC should foHowproperprocesses to i s opm establish new regulatorf positions = f( Backfitting analysis under 10 CFR 50.109 um [$l l Rulemaking process forany new regulatoryrequirements g i ag i Winston & Strawn l b i

3 hk3 Commonwealth Edison Company Ji@ Dresden Station L. -. $Ndl [l1 CONTROL ROOM ENVELOPE RECONSTITUTION d System Manager: Billy L. McGallian a fi 16 July,1998 b r- $ll BACKGROUND <. w b n Fallof1996 h-k Control Room pressure was identified to be ' ' X; negative, relative to adjacent area Work Execution Center (WEC). x Entered a 14 Day Administrative Technical .il Requirement LCO to restore operable status or .:? within the following 36 hours be in a condition ~~ where secondary containment was not required. a A Specla! ControlRoom Envelope Team was developed. GI i' I

ENEVELOPE DEFINITION / INITIAL 4 lH TESTING RfM 7.

ris
q -Q n ControlRoom Envelope was defined.

& 0 m Smoke testingInitiated. .s, " n Sealing activities were Initiated. a A SpecialProcedure, DOS 5750 07, was developed. a ControlRoom Enveloce unfiltered air inleakage was verified > 4000 scfm ( UFSAR requires < 263 scfm). ( D fi 7 ..r, .. n Q-TESTING / SEALING - r-Ak n In fourteen days the unfiltered airIntenkago on g; Safety Related train was verified at ~ 440 scfm. y a Sealing activities continued on a 24 hour basis, a New ControlRoom Emergency Zone radiological calculations were performed. k n ControlRoom Envelope Bubble Tightisolation j Damper Tracer Gas testing performed. i a ControlRoom HVAC System air flow balancing was performed for both trains. t.i 1 2

\\ 1 1 ..,y y] "tE TESTING / SEALING kn r c._ a January 24,1997 unfilteredinleakage: G, 1. A Train Sub-system was 162 scfm +/- 91

  • ?6 scfm.

2. B Train Sub-system was 156 scfm +/- 86 scfm. l 3. UFSAR Requirements.s 263 scfm. 4 v" l 0 TESTING / SEALING , ysa ..,. 17 - T ; W28 ' a The low values of unfiltered airinleakage were achieved after substantial sealing efforts l throughout the physical walls of the Control d Room Envelope as wells as the ductwork of the ventilation system. 9!! + 3

t 1 'j).g OPERABILITY 5 ECl 3.-- ? m January 24,1997-Operable but degraded (5$ h 1. ControlRoom HVAC System B Train 7 *th Emergency Zone Safety-Related Sub. j _; system was declared operable. ~ 1 2. Sub system was properly balanced. l 3. Sub-system A Train Sub-system required l _ additional repair prior to final air balance. n August 20,1997 - Fully Operable ControlRoom HVAC System A Train declared M operable. a 4 .i ' a w: CONCLUSIONS

j$YN1 n..7 a Totalelapsed time to resolve ControlRoom g).L g

Emergency Zone deficiencies was 11 months. e

" a The rapid and efficient response by the i

Dresden ControlRoom HVAC Project Team to i resolve identified deficiencies allowed Dresden l Station to continue production of electricity J-with Unit 2 and and after a forced outage Unit 3 to restart. l 1

\\ .1 I

r..;,_

ADDITIONAL SAVINGS jQ{.3 CONTRIBUTIONS 7 &@, a Lessonslearnedaboutfostering Contro

~t deficiencies, and implementing resolutions have been shared with the nuclearindustry

= l and Comed facilities. l n 1. Differential Pressure Surveillance Procedures ~ Equipment for monitoring Control 2. Room differentialpressures to adjacent areas. 3. Air flow balancing procedures Li 4. Sulfur hexaflouride Tracer Gas Testing contacts. y [..:. ADDITIONAL SAVINGS CONTRIBUTIONS ..s u a Sharedlessonslearned: i& 5. Sealing design details and Lcg specifications. 6. Control Room HVAC WIN Team developed. -i emnab 4

4 I @ g,we 2,wem>* 2dwam # l -_m 3 E 1 Crystal River Unit 3 j 4 1 l Control Room Habitability j i l Issues and Recovery Actions 3 i [ sid Powell O Principal Nuclear Licensing Engineer l i l i M i, . - o n. _f_ ao p---.-- -,,;=_,e su g,u. a e.% l 1 Kr aywwnwMF--vwwh 9mnwn- - -..y r l Habitability Envelope i 1 i j j i f i I

  • 5 Levels of the Control Complex h
  • Control Room

[ s i j j

  • Ventilation Equipment Room j

l l

  • ES Distribution Equipment Rooms j

i i i

  • Unpressurized l
  • Isolation and recirculation i

4 E e i 2

  • Ventilation System Enclosed in HE

? l siu, ,,,_ m - m.- e.1 w w'. - am m_ is=mm mar.ma spurmaam me - - ~ h w _ e -a;nOsr i s 9 l i l I,

i F i 31-e. T F irT '1-ww e re r 2EN - % +n~ % .*'!" BU-YFN '.~- - '1' 4 Ab Issues i o I i ) 1 4 l h{

  • Isolation dampers vulnerable to single j

l failure l d

  • Assumed leakage not verified j

l ?,

  • Non-conservative assumptions m j

} leakage calculations e a l I ii I'I l C 4 4 i l .-wa _ in~n. -n - m :y l M__ A_. E e Recovery Plan j i ?. u 4 1

  • Inspect & seal the habitability envelope j

j i i.

  • Upgrade isolation dampers j

1 i

  • Perform leak test 4

s 9

  • Revise dose calculations i

i n 2, w _a- .. ueo - - - - -c. s e. 4,u,;c.y i 2 2

d 'k,' 7 * ' 5 ' ' # 5.~dEd' YL5_h"[ j J 'f _5.* ' A_ Leak Test Results u f

  • Leakage greater than asenmed in dose cales j
  • Revise treatment'ofleakage in dose j

i cales i e i 5

  • Submit License Amendment Request i,

2 a for USQ l

  • Revise Tech Specs 1

W/AT,,LTY~&rf"L *?l$I'ae% DW TMWM1W $ '_~K _T. A_. i Approval for Restart i I f

  • NRC dose calc for letdown line rupture l

l

  • Used SRP assumptions

{

  • Commitment for new SGTR dose cale i

s f l

  • Using SRP assumptions

]

  • Commitment for KI administration to Control Room Operators j
  • GL 91-18, Rev.1 JCO l

e w~ ..-,_----n...-. ---~,n.~~n-,. 3 3

.gAJu_R mi 2-U ZTW3%gR-7 7-'vaZA.-._/OiTSTG_FZ;r a p^ Results of Analyses l

  • MHA bounds other accidents
  • No further plant modifications needed W w m s-4 W W E %i. m r Tr M M M M T W k

i p^ Licensing Actions l i 9i

  • Revise License Amendment Request j

l

  • Submit SGTR analysis results f
  • No change to SGTR Licensing Basis i

l w ,e l

  • Submit Habitability Report l

i

a.

i un_n____a.,_.--. l 4 4 s

Prairie Island r;*:. m sag p s e4 m _. + _.. .n.4l;..t.i:E. Q. a ?' T;y 1., A ',%. $,,, i . a; ;+%_, W .,w. _ 2:.,.a %y 5 .a w u:\\ \\~ ~. ,6 s. .,\\ u; ~..

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~ y . n x.; 7 st. . n s, ..' \\. \\_ A. ..si .\\ \\ '\\, \\; o 3 Tracer Gas Testing at Prairie Island Nuclear G.enerating Plant Lora Polley Control Room Ventilation System Engineer 7/16/98

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_.. g b_;.s... :.: ',.g Tf.h L.~9 ~ ~ ~ SA sg . A7 a; e-s+, Qs.fRA = n. B a c ;. 1..groun A. ~~. b . :xO..x N..... ::....;:nN,s.k.. .\\ g'. % %..,(, s a SSOPI - Spring 1997 '4,. ~ ~ '..; ~ m Agreed to test and re-do LOCA - Fall 1997 m Testing - Jan.1998 N, m Re-testing - July 1998 Prunt h1and s 1 1

Prairie Island s @b Nk M N Y NN w: :x;ggS.u.mm+x ...v v es 3..': nducted ^ o ,,s a .~'&[U.lf_) b * *E .j Q .4, t, x, 4#.O.:.3q.fs 'NJ. - LOCA'- NJ- 'MSLY - N.'. s .a, s. a ABSVrunningTrain. m ABN running' elay r A failure room included m ABSV running Train a ABN running relay B failure room not included - m ABSV running Train A failure damper failure a ABN running - Train B failure mse uuo4 ... ?;%. :. .... : h.. ~ s',.T_?'-N OWa e ea m es - ;...- N.. a,- N.,.w. m, y. n mg.h,, N.,g. 4. gc~..Ny.fx, a SAR 50 dfm'for steam exclusion dampers a Design Basesi 185.cfm for CR enveloje n Operable up to 422 cfm for a LOCA based on existing containment leak rates Prairie bland a 2 2 J \\

Prairie Island r.5.: m .y v..;tm., s w.. q4W.g.a er eis w.g. esu ts x.:: maw 2., w . rs, v %, . e. ~c. Q w. c..;;;.m n 4,1 - e: c. _s.. s., a yc 8 - cs. -ss m CD-34178 Tm'A OA a CD-34180 Trn B OA to PAC filter = 12'cfm ' to PiC filter = 47 Ufm a CD-34142 Tm A'to air a CD-34145 Trn B to air handler = 4 cfm handler = 19 cfm a CD-34176 Tm A OA a CD-34177 Trn B OA Roof = 274 cfm Roof = 119 cfm Praine bland E%4 E verm p;jc:.3.1.'.iwCon 01 Room:Eny?se ope Test i y,.-... _. ?g A..,.

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  • i

.-.-:~. :x ' m. . \\... ~, v A. N..,,_./Ms c.a c.-. t t s \\.,.... M.,. e,: l " s ',, s*N.', ~ \\'- . rl i i s .. ':3. ABN/TrnB ~ " ~ ~ ~ 6 i ~, ABN/ Trna -7'--------- s'. ABS /DMPR " - ' ' ~ " ~ ' " - ' ' * " .4 i IE*I ABSITrnB .a ABS / Trna * '^- ~ 4 i e ABN/RR/ Trna " - - ' ' " ' ' - ' " - * - - ". 0 100 200 300 400 traine hiana i 3 .i,

so.-.~a .an..a-xx~ ,a.--e+..a-.-._ .--..~.~n au. -+ -u.. -.-~. .w .n-.~. a .u.- Prairie Island wa vara, wpan c 9929:rSd . quen ~@n,K s:.hu itments ~ ?-cy 5j =4 Nqryg3p . ~. e 3. p. Nj.. .W.... m' Repair ~or' replace ~the door seals and r.e,' test.

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x. x . s aImp. rove plant mamtenance procedures for repair of CR dodr. seals -x m Repair or replace the two failed dampers a Update maintenance procedures for these dampers a Evaluate need for testing additional t dampers Prairie ts!&nd l g/~ w;(; ~ b.~a .w 1er subserc.1-a kc uen; actions n:mra., Aar=&O-w Q ..t.:.: m,., s, w c....,. 3. g ,.. a.

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~ Im. h4 $?#.) % 4,~., v.

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I' .; = z;.y.. Q ; >._ "3_- m Re-eva%,luating CR'p.ost-LOCA doses.\\ , z s . G,, a Re ' evaluating CR post MSLB~ doses ' . O A e Pf'& int I$l&Dd l t 4 4 I' i

Prairie Island n 1 .f' h c h, wee .c.*%a.rjyeg.M%. Conclu.r..r4.. M ~..,, 1 -- .c si.o.n > x..a n.s g %' x ~.. v.

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SM: ;. i-?%. 4 m.it =.N. ' (*, 2., a Dutside airintdke Nj. K..7-th'N, -a dampers were rule ~d ~ ~' =M.r n.=m mew 9, out as'a source of the'.- .M5 Wes r D..--.. p #e./t e.,z-g majority'of the in-IG &W leakage. g 7 a Ventilation Line-ups F... .r. g...qfey, do effect the results ., y ~,.. $ # 1 T ! Q,4 _ &, ~.. .t zdgA 4rsa Prsme bland d 5 3 .}}

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