ML19224B905

Discusses ACRS TMI Subcommittee 790531-0601 Meeting Agenda Re Preliminary Discusion on Implications of TMI-2 for Bwr. Forwards Vugraphs to Be Used in Presentation

ML19224B905
Person / Time
Site:	Crane
Issue date:	05/29/1979
From:	Heltemes C Office of Nuclear Reactor Regulation
To:	Ross D Office of Nuclear Reactor Regulation
References
NUDOCS 7906270189
Download: ML19224B905 (19)

Text

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1 D. W ff hg UNITED STATES y

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g NUCLEAR REGULATORY COMMISSION 3

p WASHINGTON, D. C. 20555 YA' ~.

37c MEMORANDUM FOR:

D. F. Ross, Jr., Deputy Director Division of Project Management FROM:

C. J. Heltemes, Jr., Chief Standardization Branch, DPM

SUBJECT:

ACRS TMI-2 SUBCOMMITTEE MEETING - MAY 31 - JUNE 1,1979 One of the agenda items for the staff on May 31 is entitled, " Preliminary Discussion on Implications of TMI-2 for a BWR."

I have discussed this iten with the ACRS staff and attempted to persuade them it was prenature.

I pointed out that the review of IEB 79-08 for BWR's has not yet begun. The net result of these discussions was that the time allottec for this agenda iten has been reduced from 1-1/2 hours to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

I propose that we make a formal presentation along the following lines:

(1) Review of evaluation sequence for BWR's (2) Operating BWR's (3)

IES 79-08 items (4) Status of IEB 79-08 review (5) Summary of responses to IEB 79-08 (6) NUREG-0560 recommendations that affect BWR's A copy of each of the vugraphs that we propose to use is attached.

I propose that W. Kane make the presentation.

I assume that there will be appropriate representation by NRR management to handle questions of a policy nature.

Please advise if you require any modifications to this approach.

no.(,[L 1

. 'g. H'i u. w -e1temesJJr., Chief n

s Sta ndardi za tion' Bra nch Division of Project Management

Enclosures:

As stated 255 059 7906270/Sp'

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9 EVALUATIG1 SECLDIE TMI-2 ACCIIBfT i

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UTILITY EtiDOR IEBs fETit1GS EETlf48 ISSED 1

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BWP/1 1960 HUELDT BAY PGFI E

BWR/1 1962 BIG FOCK PON TC E

BWR/1 1962 L%1 LACFOSSE DPC A-C OYSTER CEEK JTF1 E

BW2 1969 NITE MIlf POINT 1 t0PC E

BW2 L%9 DRESIB12 EC E

R&3 1969 MILLSTG E 1 tiEC E

BWPM 1970 fGTICE11.0 NSP E

BW3 1971 DRESDEN 3 EC E

BW3 1971 QUADCITIES1 EC E

BWPM 1972 QUADCITIES2 EC E

RW3 1972

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]E CLE OLISSIE PILGRIM 1 E

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BhW4 1973 BDIG ERR (1 TVA E

BWW4 1973 PEA G B0HOM 2 EC E

EW4 1973 COOPERSTATIW NPPD E

FrW4 1974 DUANE AROLD IEL&D E

BVW4 1974 BR0'46 ERRY 2 WA E

BhW4 1974 RACH EDTTOM 3 E

E BhW4 1974 HATCH 1 E

E KW4 1974 FITZPATRICK PASN(

E EW4 1974 BRLIISWICK 2 CPFL E

EW4 1974 BENS ERRY 3 WA E

BVW4 1976 BRUNSWICK 1 CP8L E

B5W4 1976 HATCH 2 E

EW4 1978 255 062

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IEB 79-08 ITEMS

~

1. PEVIEW TE ESCRIPTION NO PELIMINARY OiP0f0 LOG / OF TE IMI-2 ACCIIEE WITH EMMSIS Gh

. TE SERI0lSESS NO C0fEEQUENCES OF BLOCKING BOTH TPAlf1S OF A SAETY SYSTEM, OPERATIGML ERFORS, TE FEED TO SYSTEPATICALLY

1. iALYZE RET C0f0ITI0f1S TO TAE APPROPRIATE CORRECTIVE ACTI0f1 INSTRUCTIG4 0F OEPATING PERTff!EL t0T TO 0\\ERRIE ESFs LNESS IT HILL ESULT IN LNSAFE CQOITIONS, N0 t0T T0 fWE OEPATI0fML ECISI0f1S BASED S0_ELY ON A SINGLE PLN1T PAP #ElER MBi OllERS ARE AVAILABE

, EVIEW BY ALL LICENSED OEPATORS NO PLANT PNMGElEfT #0 SUER-VITRS WITH 0 PATIGML ESPONSIBILITIES.

2. REVIEW CONTAlt0 BIT ISOLATION ESIGN #0 PROCEDLES TO ASSUE APPR)P-RIATE LIES ARE IS&ATED UP0fi AUTOPATIC SAFETY INJECTIGl.

3. ESCRIBE AUTOPATIC NO VN1UAL ACTIONS fEESSARY R)R PF0ER RJNCTIONING CF Tit SUXILIARY EAT PDOVAL SYSTEMS WhB1 THE PAIN FEEDWATER SYSTEM IS liMVAIL#tE.

4, DESCRIE ALL LES AIO lYPES OF \\ESSEL LEVEL INDICATION FOR EDTH AUT0nTIC AfD f%UAL INITIATIG10F SAFEIY SYSTEMS AfD OTER REDUNMIT INSTRlfENTATIOk AVAllABE TO GI\\E TE SA'E INREMTIG1.

5, EVIBI CEPATIiiG NO I 'AINING PR0037JES TO ASSUE T!MT OffPATORS DO NOT OVERRI[ ESFs UNESS IT WILL ESULi Ill UNSAE C0iOITIGlS, NO THAT Ult!sT0ilS DJ NOT [LY UFG1 \\ESSEL LEVEL IISICATIG! ALCGE FOR i'NA.

ACTIONS.

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6.

EVIBi N1 SATTY-ELATED VALNE POSITIONS, FOSITIONING EQUIREPBUS NO CONTPOLS TO ASSUE PPDFER OPERATION OF ESFs REVIEW PROEDUES TO ASSUE VAL \\ES AE ETUPNED NO I%ItHAINED IN 11EIR CORECT POSITION R)LLOWIfiG EESSARY PN11PLLATIONS.

7. EVIEW OEPATING FDDES NO PFOCEDL3ES TO ASSURE 1 FAT Ut0ESIED s

PlfPING OF FOTEtEIN1Y RADI0 ACTIVE GASES NO LIOJIDS WIll NOT OCCUR INADVERTBiTLY.

8. REVIEW N0 00DIFY AS EESSARY PAltRENN1E NO TEST PROEDUES TO ASSURE TFAT SAElY ELATED SYSTES ARE \\ERIFIED TO E OEPABLE PRIOR

~

TO REfDVAL FPOM OR ETURN TO SERVICE NO THAT OERATI0tML ERS0tUEL AE EXPLICITLY t0TIFIED.

9. REVIEW PROMPT RFORTING PROEDUES FOR NRC t0TIFICATIU4 IF TE REACTOR IS NOT IN A C0tEPollED OR DPECTED C0f0lTIU; 0F OERATION.

10. EVIBi OPEPATING t0 DES NO PROCEDURES R)R DEALING WITH SIG11 FICA'lT A'DUNTS OF HYDRDEN THAT FAY E GB;EPATED I)JRING A TPK;SIBiT OR ACCIDB4T.

11. PROPOSE CHA'ES AS REQUIED TO TECHNICAL SECIFICAT10f;S AS A ESULT

- 0F IfPLBEtEING ITEfB 1-10, 255 0;4

IE3 7E-08 RESP 0"SE SU W RY

!TEMS 1 THRU 10 c

REQUESTED EY 4/24/79 o

NRR 9AS RECEIVED RESPCNSES TO THESE ITEMS FOR THE FOLL0n'I"3 25 UNITS.

BRUNSWICK 1 & 2 4/23/79 PEACH SOTTOM 2 3 3 4/25/79 MINE MILE POINT 1 4/24/79 COOPER 4/25/79 MILLSTONE 1 4/24/79 DRESDEN 2 a 3 4/27/79 3ROWN'S FERRY 1,2,3 4/24/79 QUAD CITIES 1 8 2 4/27/79 OYSTER CREEK 4/25/79 VERMONT YA'lKEE 4/27/79 PILGRIM 1 4/25/79 DUANE ARNOLD 4/27/79 HATCH 1 S 2 4/25/79 MUMBOLDT BAY 5/01/79 FITZPATRICK 4/25/79 MONTICELLO 5/01/79 LACROSSE 5/02/79 DRESDEN 1 RESP 0MSES INCLUDED ONLY ITEMS 1, 8, AND 9 WITH COMMITME.'!T TO PROVIDE REMAINDER PRIOR TO FUEL LOADING.

o NRR IS AWAITING RESPONSES Ct! 1 ADDITIONAL U"IT.

ITEM 11 o

REQUESTED BY 5/14/73 o

NRR HAS RECEIVED RESPONSES FOR THE FOLLOWING 13 UNITS DRESDEN 2 & 3 4/27/79 PEACH BOTTOM 2 & 3 5/14/79 QUAD CITIES 1 & 2 4/27/79 MILLSTONE 1 5/14/79 HUMBOLDT BAY 5/01/79 BRUNSWICK 2 a 3 5/15/79 NINE MILE POINT 1 5/14/79 PILGRIM 1 5/15/79 M0!!TICELLO 5/16/79 o

NRR IS AWAITING RESPONSES ON 13 ADDITIONAL Ut!ITS 25

SU21ARY OF RESPONSES TO IEB 79-OH BWR UTILITIES ITEM 1 REVIEW OF DESCRIPTIDN AND CllR030LOGX

RESPONSE

PROGRAMS IIAVE BEEN INITIATED TO INFORM Ti1E APPROPRIATE OPERATIONAL AND SUPERVISORY PERSONNEL AS TO Tile SIGNIFICANCE OF Tile TMI-2 ACCIDENT AND ITS IMPLICATIONS FOR BWRs.

ITEM 2 COBIAIEMENT IS3LATI0fl RESEORSE CONTAINMENT ISOLATION OCCURS CONCURRENTLY WITil AUTOMATIC ECCS INITIATION, ll0 WEVER, FOR SOME PLANTS Tile NEED FOR PROCEDURAL CllANGES AND POSSIBLE ilARDWARE CllANGES flAS BEEN IDENTIFIED.

ITEM 3 ACIl0NS_dECESSARY FOR AUXILIARY llEaI_ ret 10YALSISLEfiS RESEC)NSE OVER Tile Sl10RT-TERM SYSTEM ACTUATION AND CONTROL IS AUTOMATIC.

OVER THE LONG-TERM MANUAL ACTIONS ARE REQUIRED TO GO TO COLD SiluTDOWN.

PROCEDURAL C}lANGES WERE IDENTIFIED FOR SOME PLANTS.

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ITEM 7 UNDESIRED PUMPING OF RADI0 ACTIVE EFFLUENIS.

RESPONSE -

PROGRAMS llAVE BEEN INITIATED TO VERIFY THAT CURRENT SYSTEM DESIGNS AND PROCEDURES WILL PREVENT THE INADVERTENT RELEASE OF RADI0 ACTIVE EFFLUENTS.

FOR SOME PLANTS CHANGES TO PROCEDURES liAVE BEEN IDENTIFIED.

ITE!' 8 VERITICATION_OF SAFETY-RELATED SYSTEM OPERABILLTl

RESPONSE

PROGRAMS HAVE BEEN INITIATED TO REVIEW PROCEDURES FOR MAINTENANCE AND TESTING TO VERIFY OPERABILITY OF SAFETY SYSTEMS WilEN TilEY ARE RETUfNEDTOSERVICEASWELLASNOTIFICATIONOFOPERATORPERSONNE Wij[f{ SUCil SYSTEMS ARF REMOVED FROM SERVICE.

REVISIONS TO PROCEDURES idREFOUNDTOBENECESSARYINSOMEPLANTS.

(

LTEL9.

REVIEW PROMPT REPORTI'lG PROCEDURES

RESPONSE

PROCEDURES IIAVE BEEN REVIEWED TO DETERMINE IF NRC CAN BE NOTIFIED WITHIN ONE HOUR AND IF AN OPEN COMMUNICATION CHANNEL CAN BE SET UP.

CHANGES TO PROCEDURES IIAVE BEEN IDENTIFIED FOR A NUMBER OF PLANTS.

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ITEM 111 PROCED11RES FOR DEALING WITil llYDROGEfl RESf0ILSE -

MULTIPLE FLOW PATilS EXIST FOR VENTING llYDR0 GEN FROM Tile REACTOR VESSEL TO Tile CONTAINMENT AND SYSTEM AND/0R PROCEDURES ARE AVAILABLE FOR llANDLING flYDR0 GEN IN Tile CONTAINMENT.

PROCEDURAL CllANGES liAVE BEEN IDENTIFIED FOR SOME PLANTS.

I ITEM 11 TECllNICAL SPECIFICATIONS CllANGES BESE0RSE -

PROGRAMS IIAVE BEEN INITIATED TO DETERMINE Tile NEED FOR CilANGES TO TECllNICAL SPECIFICATIONS.

NO CllANGES WERE IDENTIFIED IN Tile INITIAL RESPONSE.

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SUMMARY

OF CHANGFS BY BWR UTILITIES IN RESPONSE TO IES 79-03 IEE /9-US liEMS PLANT 1

2 3

I4 5

6 7

_8 9

10

' 11 -

DRESDEN N

N N

N N

N N

N HUMBOLDT BAY P

P BIG ROCK POINT N

N N

N N

N N

N N

N N

LACROSSE P

N OYSTER CREEK P

P N

NINE MILE POINT 1 P

P /D P

P DRESDEN 2 & 3 P

P P

MILLSTONE 1 P

P P

P MONTICELLO P

OUAD CITIES 1 & 2 P

P PILGRIM 1 P

P D

P VERMONT YANKEE P

P N

BROWNS FERRY 1,2,8 3 P

.P N

COOPER N

PEACH BOTTOM 2 & 3 P

P P

P DUANE ARNOLD P

P P

N HATCH 1 & 2 P

P P

P FITZPATRICK D

P P

N BRUNSWICK 1 8 2 P

NOTES:

P ItJDICATES ONE OR MORE PROCEDURE CHANGES D

INDICATES ONE OR MORE DESIGN CHAT 1GES N

INDICATES NO RESPONSE U/U (J D

FUTUE 18 79-08 ACTIVITIES e

TASK FORE WILL It41TIATE EVIEW OF THE ESP 31SES TO lEB 79-08 m OR ABOUT JLNE L 1979 e

MEETlk6S Willi BWR UTILITIES AS EQUIED e

IIBTIFICATION OF POTE4TIAL PEBLB1 AEAS TO OTHER TASK FORES e

SAFETY EVALUATIQlS 01 IEB 79-08114 THE FORi 0F LETTERS TO liiDIVIDUAL UTILTIIES lii JLEE 1979 Bewc, 2ewset e

l NUREG-05E0_RECOLEENDALIDilS_ AFFECT I TLG_BMs PLANT C0AIRQL SYSTEMS.

1.

Tile ROLE OF CONTROL SYSTEMS IN ALL PLANTS, AND TilEIR SIGNIFICANCE TO SAFETY, Sil00LD BE REEVALUATED.

2.

AN ASSESSMENT Sil0VLD BE mal)E OF Tile BALAilCE BETWEEN ADDITIONAL AUTOMATI0fl VERSUS IMPROVED OPERATOR RESPONSE TO MAINTAIN ADEQUATE PLANT CONDITIONS.

3.

CRITERIA Sil00LD BE DEFINED AND ESTABLISilED FOR EQUIPMENT AND SYSTEMS TilAT ARE IMPORTANT TO SAFE PLANT OPERATION BUT ARE NOT REQUIRED TO BE CLASS 1E.

DAIa_EROM OPERATliiG PLANTS 4.

A STUDY Sil0ULD BE MADE OF REPORTING AND DATA-ASSEMBLY PROCESSES USED TO ACCUMULATE AND ASSESS Tile SIGNIFICANCE OF OPERATING PLANT DATA.

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