ML20071E031
| ML20071E031 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1983 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0606, NUREG-0606-V05-N01, NUREG-606, NUREG-606-V5-N1, NUDOCS 8303140698 | |
| Download: ML20071E031 (49) | |
Text
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l NUREG-0606 Vol. 5. No.1 February 18,1983
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UNRESOLVED SAFETY ISSUES
SUMMARY
AQUA BOOK
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TABLE OF CONTENTS taqE NO.
I_A iR_Nn 1Aw anNAirt pr3CRintme s
4-2 An:REvtATIONS s-S OvrRvitu o-o USt'S FOR WNICN ftCHNICAL RESOLUTION tl COMPLETE 99-12 A-9 ALECR SERWIZ WATER HANrtER 93-94
.A-3.
A-4 A-S JACR STROSHIDER W. CE. AND 34W STEAM GENERATOR IUSE INTEGR!fY IS-96 A-92 RICHARD JOHMSON FRACTURE TOUGNNESS OF STEAM GENERATOR AND REACTOR COOLANT PUtir SfrPORfS 97 A-tf PAUL NORIAN (ACTING)
SYSTEMS INTERACTIONS IN NUCLEAR PDWEk PLANTS 18-29 4-44 SVED SH AUR AT SEISMIC DEST 64 CRITERIA-SNORT TERM FRPGRAM 22-23 A-43 ALECR SERR12 CONTAINMENT EMERGENCY SUMP PERFORMANCE 24-2S A-44 ALAN RUSIN STAfl0N BLACROUT 24-78 A-45 ANOREW MARCHESE SNUfDOWN DECAY NEAT REMOVAL REGUIREMENTS 29-36 A-46 f Y.
CNANu SEISNIC QUALIFICaf!0N OF EQUtPMENT IN OPERAf!NG PLANTS 52-34 A-4F ANDREW $2URIEWTC2 SArtfy IMPLICATIONS OF CONTROL SYSTEMS 37-19 A-48 15UNG SU HvDP0 GEN CONTROL PEASURES AND EFFECTS OF HYDROCEN BUENS ON SAFEff EquirMENT 40-43 A-49 ROY WOODS PRES $URIZED THERMAL SHOCK
ABBREVIATIONS AAts Aceldent Analysts tranch (Ferner NRR Sranch)
EEse Environmental E neering Branch. Dietelen Att Ad=6ntotratten tranch. Tra6atag and of Engineerine E R3 Adelaistrat ten Staf f (II)
EFPY:
Effect6ve Full-Peeeer Years ACs Alternating Current EG8Cr Edgetten. Germeshausen 4 Selee ACESt Adv6nery Coe=4ttee en Reacter Safeguards EPt E*ergency Preparedness ads Assistant Director EPRI:
Electrie Poe.er Research Institute ADS Analyst e and Develesment Branch Divisten of Etts Feuipment Gua14ftestion Branch. Divlelen Reacter Safety Research (RES) of Engineer 6ng (NRR)
AEls Ace 6 dent Evaluat6en tranch. Divleien of FIN:
Financial Systees Integration (NRR)
FSIFs Full-Scale Test Facility AE00s Of fice of the Analvet e and Evaluation of FWs Feeduator Operettenal Data FTe F6ocal Year AIF8 Ateste Industrial Forse GBs Seesciences Scanch. Olvlelen of Engineering (MRR)
APTSs Action Plan Tracking Syelse GE8 General Electr6e ARL8 Alden Research Laboratory GIS Geanete Issues Branch. Dielelen of Safety A55s Aust!6ery Systees Branch. Divleton of technetegy (NRR)
Systeme latogration (NRR)
NF($s Human Factere Engineering $ ranch. Olvle6en ASMEs American Society of Mechanleat Engineers of Mealth. Sl66ag and Maste Mget. (RES)
AstMa American Society of Test 6ng Mater 6als NSSit Neavy Sectlen Steel Technelegy ATWSt Anticipated Trane6ent W6thout Scree Icsts Instrumentation and Centrel Grench.
B4W Sabeech end W6tcom Company D6vielen of Factitty Operetiene (RES)
DNCs Breenhaven Nattenal Ceneerwatery ICS3s Instrumentatten and Centre! Systems Branch.
BNLs Brookhaven Nat tenal Laboratory Devesten of Systees Integratten (NRR) 30Ps Salance of Plant IEs Of f 6ce of inepectlen and Enforcement BW4t Bell 6ng Water koacter IEEEE Institute of Electr6eal and Electronics Engineers CEI Combustion Enq6neeren9. Ineerperated INELs Idaho Nuetear Engineer 6ng Laboratory CES:
the=4 cal Eno6neering uranch. D6v6seen of ipr Indtan Pe6nt Enq6neering (MRR)
IREP Integrated Reliability Evaluatten Program CFRI Code of Federal Regulattene ISIS In-Servlee Inspectlen CP8 Cemetruetten Pere 64 LANLs Lee Alames flat tenal Laberatory CPAs Core Performance Scanch. Divleton of lER:
L6censee Event Report Systems Integration (MRR)
(LNLs Laserence Livermere National Laboratory CRt Centracter Report LOCA:
Lese-of-Cowlant Accident CRGRt Cemelttee to Reviene Generic Requirement, LPPt Lead Paar4 Progree CSS:
Centainment Systems tranch. Diw6elen of LTPt Long Tore Progree Systeso Integratten (NRR)
LWR Light-Watee React DCs D6cect Current MARR I-IIIs Containment Type,erfor Belling Water Reactere des D6v6eien of Engineering (NRR)
MEtt Mechanical Engeneering Branch.
DEDROGRs Deputy E=ecutive D6 rector for Reglenat D6v6elen of Engineertne (NRR)
Operattene and Generic Requirements MEBR:
Materlate Eng6meertne franch.
DFOs Dowle6en of Faellity Operattene (RES)
Down elen of Engineerfag Techselegy (RESS DHFSI D6vielen of Muman Factere Safety (MRR)
MIT Massachusette Institute of Technelegy DHRS:
Decay Meat Removat Svetens Mstat Ma6m Stese L6me Break DLt D6v6sion of L6 censing (N##3 MTES:
Materials Engineoc6ag $ ranch. 06vleien DOEs U. S. Department et Energy of Engineer 6ng (NRR)
DORe De ve elen of Operatin9 Reactere NDE:
Non-Destructtwe faaminatten (Former NRR D6,4stens NRC:
Muclear Regulatory Ceemiselon Deas 06 vision of Risk Analysis (RES)
MREPs Neutron Resonance Escape Probability DSIs Divlelen of Systems Integratten (NRR)
NRes DS$8 D6visten of Systees Safety Off6ce of Nuclear Reacter Reguletten M5Sn nuclear Steam System (Former NRR D6vio6en)
NUREGt Nuclear Regulatory Report (prepared in-house) 05f8 D6vts6en of Safety technelegy (NRR)
E' Enghneering Ett Enforcement Branch. Enfeeceeent and Investigat6ene Staff (IE)
ECC' Emergency Core Coel6ng 1
A8BREVIATIONS Ole Operating License
$$Es Safe Shutdown farthowake ORAtt Operating Reacters Assessment tranch. 06violen of
$$P3s Standards Spec 6al Projects Branch Lscenssag thaR3 D6v6 sten of Licensing (NRR)
ORS Operat6nq Reactern Sranch. Division of STP Short-term Program Locons6mq (NRR) 1APs lask Act6en Plan ORNLs Oak R6dge Nat6enal Laboratory TER:
Technical twalvation Report OSD:
Office of Standards Dewetopment TNs thermal Hydrawi6cs (Former NRC Off6ce) 1M lask Manager 0154:
Once-throwgh Steae Generater TMIs three M68e Island UCLA Un6versity of Callfernia Les Angeles Power Authorit.y of the State of New York PASNT:
Pacif6c Mertheest Laboratory (Sattellel Ugli Unresolved Safety Issue PNLs PRA:
Probabilistic Atsk Assessment W:
Westinghewee Electric Corporetten PSS:
Power Systees Branch. D6v6 sten of WHs Water Hammer Systems Integretten (MRR)
PSd Plant Systees Unit EAEOD)
PfRS:
Precedures and Test Review Scench. Divisten of Human Facters Safety ENRR)
PWRs Pressurlsed Water Reacter RAss Rad.elegscal Assessment $ ranch. Division of Sye+ ems Integratten (NRR)
ACICs Reacter Core Isolatten Coeling REFs Reference RES Off6ce of Nuclear Requistory Research RFPs Reevest for Proposal Rhts Residual Neat Remeval RPWs Reacter Pressure Wessel RMs Rosewece Management RRA34 Rollablitty and Risk Assessments Branch 06vio6en of Safety lechnelegy (NRRD RRRCs Regulatory Rogv6romonte Rev6ew Committee RSs teacter Safety (Former NRR Branch 3 RSS:
Reacter Systems tranch. Oteto6en of Systems Integretten (NRR3 RS$ MAPS teacter Safety Study Methodelegy Appilcatten Progree RVs Reacter Wesse!
Satt Sc6ence Appl 6eatlens. Inc.
SCC:
Stress-Corrosion Cracking SEBs Strweteral Engineering tranch. D6vlelen of Eng6neertne (NRR3 SEPs Systematic twelvetite Program SEPS:
Systematic Evatwattee Progree Branch. Olvleien of Licensing (NRR)
SER Safety Ewalvatten Report SGs Steam Generator SGWN Steam Generater Water Mammer SNLs Sand 6e Mattenal Laboratory SgUGs Se6 sees qualif6callen Utlaltles Grove SRPs Standard Review Plan SRVs Safety Re16ef Valve s
2
PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS Keyt N/S = Not Scheduled USI NOV. 19. 1982 111LE AeUA ROOK CURRENT REMARKS A-9. Water Nammer Novembee 38, 1983 Decembee 38, 1983 NURES/CR-2789 was leaved in July 1982. Development of a technical find 6ngs NUREG is underway.
Th6e draft NUREG t o being used to develop receemendallene to CRG4 for resolution.
A-3. Stese Generater March 38 1983 Aprt! 38 1983 The draf t NURES repeet has been reviewed by the A-4 Tube Integrity technical branches and their commente encorporated.
A-S.
The rev6 sed report le being preoared for manacenent reviene and then will be toeved for pwblic comment.
The NEC has formed a f ask Force to prepare proposed requiremente.
A-12. Steam Senerator June 4.
1983 July 1 1983 Meetings were held with EPRI and Industry groupe 8 Reacter in December 9980 to resolve use of fracture Ceolant Pump mechan 6ce methode for evalification of supporte.
Supporte NEC reviewer's commente on the f6aat NUREG-8577 were not received until mid-January 1982. caus6ng a delay to tesw6mg the 96nal report.
Commente made by EPRI and the AIP owbceemittee en material esquiremente have been incorrerated into the final NUREG. Preparatten of the resolutten eachase le nearing completten for submittat to the Director.
NRR ocheduled for Apell 1983 A-t?. Systems Inter-See itse II.C.3 See Item II.C.3 Work planned undee TAP A-97 ut!! be perfereed under actions in Action Plan in Ac4 ten Plan FMI Actten Plan item II.C.3. Systems Interaction.
Track 6ag Systee fracking System The statue of thee itee le reported in the overterly wodates of the TMI Act 6en Plan f racking System (APIS).
3
P300 RA:3 6VERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS USI N0y. 19 1982 B.lk IIILE AGUA BOOK ClL4REMT REMARKS A-40. Seismic Design March 16. 5984 March 96. 1984 The Nec staf f has reached an agreecent en Criterla acceptance of the proposed changes to the Standard Reviene Plan, the remaining schedule for th6s USI 4e dependent open recetpt of a schedule from the centracter. LINL.
A-43. Containment July 15. 1983 December t.
9933 All technical espoort (NU8f 0/CRet reporte have been Emergency Swep teswed. A resolutten NUREG to 6n the f6 mal stages of preparat6on and wi!! underge management concwerence.
A-44. Statten Slachewt December 15. 1983 March 15. 1944 Draft centracter technical reporte esere provided in May 8982, lhe schedule for this USE has been revised to 6nclude a task to evaluate r6sk reduction and cests of wartows plant flees needed for a value impact assessment.
A-45. Shutdown Decay October 30. 1945 October 39. 1985 A fask actlen Plan was lessed on October 7 1988 Neat Roseewal and routeed on Jwne 2.
8982.
A techn6 cal oestetance Requirements contract package esas approved on Apr4 8 9, 1982 and 6mplemented eet th Sandte en May te. 9982.
The f 6rst enterie milettene report esas t oewed for NEC staff rewtow on December 22. 9942.
A-46. Seleets evalifi-April 30, f944 Apell St. 1934 This program asas red 6rected to be made compatibile cation of Egulp-u6th the Equipment Swaltf4 cation Procese Plan.
The ment en Opera-femal Task achten Plan has been lenwed. Werk has 46mg Plante been insteated on all tasks w6th all contractere esell into their owbtasks.
A-47. Safety Implica-N/S January 30. 1986 An apoceved Task Actlen Plan esas issued on Sept.
46ene of Centre!
- 27. 1982.
Techn6 cal Assistance centracts have Systees been established eelth ORNL and INEL.
A-48. Hydrogen Central N/S Jwne 38. 1985 A draft Tash Attlen Plan was approved on December Measures and 3.
1982. Werk on thle USI le 8tmeted to the generic Hydrogen Scene resolution of hydrogen centeel and sowipment en Safety Equipeent evallfteatten for ice condenser and BWR Mark III s
containments.
4
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i PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS E
{
-e "Isul'iaU**
TItte cu,aut arms 4-49. Presswelred N/S Therme! Shock N#%
4-49 esas doe 6gnated by the Commitolen se en DSI
'l en December 2s. 1981.
The fath Action Plan esas approved and teswed en March 26, 9942. NEC staff PTS receemendattene (SECV-82-465) were appeeved by the Cemetee6en in December 8942.
A none cute fee F15 resolutten le be6ng drafted and wit! be published for comment in June 1985.
l i
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4 i
5
Uil'S FC3 WHICH TECHNICAL EES5LUTION IS COMPLETE IMPLEMENTAi!DN 1ASE MANAGEtt US!
jgL TI!LE DATE COMPLEffD REPORf1 PutLlijLD IMPLEMENTATION STATUS TELEPHONE A-2.
ASYMMETRIC SLOWOOWN DEC. 8988 HUREG-0609 ALL PWR PLANT ASSESSMENTS FOR ASYMMETRIC JIM SHEA LOADS NAvf DEEN RECEIVED AND ARE CURREN1LY 492-7238 LOADS ON REACTOR BEING EVALUATED SV ST AFF AND CONTR AC10R PRIMARY C00LAMI SYSTEMS EG84.
AS A BASIS FOR THIS EVALUATION.
STAFF IS IMPLEMENTING CRITERIA DEVELOPED AS PART OF THE 1ASE ACTION PLAN A-2.
THESE CR11ER14 ARE INCLUDED IN NUREG-0609.
SAW AND CE OWNER $* GROUPS Nave RESPONDED 10 THE QUESTIONS RAISED AS A RESULT OF OUR INITIAL REVIEW OF THEIR SUDMITIALS ON INE ASSESSMENT OF THE PRIMARY SYS1EM COMPONENIS AND SUPPORTS TO ASYMMETRIC LOCA LOADS.
THESE RESPONSES ARE CURRENTLY BEING REVIEWED. E!GNI TERS HAVE BEEN RECEIVED FROM THE SUSCONTRACIOR AND OTHERS ARE EXPECIED ON A REGULAR SASIS OVER INE NEXI YEAR-PLUS.
THE WESIINGMOUSE OWNERS GROUPS EXPECT A RESOLUTION OF THIS ISSUE ON THE SASIS OF
- LEAR SEFORE SRFAE' CRIIERIA. AN INTERNAL REPORT.
RECDMMENDING ACCEPTANCE OF TH3 ' LEAR BEFORE BREAL' CONCEPT ISSUED Sf INE STAFF IN FESRUARY 1989 NAS REEN DISCUSSED WITN THE ACR$ ANO IS UNDER REVIEW BY NRR MANAGEMENT PRIOR TO REVE!W SY CRGR.
A-6.
MARR I SHORT TERM DEC. 1977 NUREG-0404 COMPLETE = ALL PLANT UNIQUE ANALYSES
=
AND EGUIPMENT MODIFICAIIONS AS REQUIRfD PROGRAM WERE REVIEWED AND ACCEPTED AND APPROPRIATE TECHNICAL SPECIFICATION CNANGES WERE MADE.
s 6
t l
USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLfMENTATION USI TASR MANAGER #
IITLE DATE CCMPLETED REPORTS PUBLISHED IPFLEMENT ATION ST Aful TElfPHONE A-7.
MARR I LONG TERM JULY 9540 NUREG-966t LICENSEES ARE IN THE PROCESS OF SYRON SIEGEL PROGRAM AUGUST 1982 NUREG-0661 SUPPL. DESIGNING AND INSTALLING M001FIC4710NS 492-7534 he. 1 TO MEET THE C0f1 MISSION'S ORDER Def f FOR EACH OPERATING PLANT.
IME LICENSEES ARE IN INE PROCESS OF PREPARING PLANI-UNIOUE ANALYSIS FOR SusMITTat 10 THE STAFF FOR POSI IMPLEMENIATION AUDIT REVIEW FOR COMPLIANCE WITN THE ACCEPTANCE CRITERIA CONIAINED IN APPENDIR A TO NUREG-0668 TEN LICENSEES / APPLICANTS NAVE SUBMITTED THEIR PLAMI-UNIGUE ANALYSIS. CUR CONTRACTOR $.
$NL AND INE FR ANELIN RESE ARCH CENIER. ARE REVIEWING THESE SUSMITIALS.
A-8 MARE II CONTAINMENT AUCUST 1981 NURLG-0898 YME REGUIREMENTS RECOPR9 ENDED IN NUREG-POOL DYMAMIC LOADS Gats ARE SEING IMPLEMENTED OURING THE OPERat!NG LICENSE REVIEW FOR EACM PLANT WITH A MARE II CONTAIMMENT. THESE REGUIREMENTS WILL ALSO SE INCLUDED AS AN A00!! ION TO INE APPROPRISTE SECT 10N OF THE STANDARD REVIEW PLAN.
A-9.
ATWS SEPT. 1989 NUREG 8460.
TWO VERSIONS OP THE PROPOSED ATWS DAVID PTATT. RES VOL. 4 RULE MavE BEEN ISSUED FOR COMMENfs 445-5960 46FR17$2I THE STAFF VERS.ON AND AN ALTERNAit VERSION OP THE RULE PREPARED AT THE DIRECTION OF COMMISSIONER MENDRIE.
FOLLOWING THE CCfPENT PERIOD AND CONSIDERATION OF PUBLIC COMMENTS. A FINAL RULE WILL BE PREPARED FOR COMMISSION CONSIDERATION. A TASR FORCE MAS GEEN ASSIGNED TO FORM A S ASIS FOR INE FINAL RELE.
7
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TITLE DATE COMPLETED REPORTS PUBLISNED IMPLEMfMTATION STATUS TEttPHONE A-S t.
RESIDUAL NEAT 1978 NO FORMAL REPORT RRRC APPROVED IMPLEMENTATION PLAN TOM NOVAK REMOVAL REGUIREMENTS SRP 5.4.7 REv!SION JANUARY St. 9978.
IMPLEMENTATION 492-7417 FOR OPERATING REALTORS NOI COMPLETE.
A-36.
CONTROL OF NEAVY JULY 9980 NURE4-0692 IMPLEMENTAi!DM Rf40!REMENTS WERf SUD REGUA LOADS MEAR SPENT ISSUEO 10 ALL LICENSEES BT LEffER 492-7877 FUEL DATED DECEMSER 22, 1980.
YNE LEffEt REGUESTEDs INTERIM ACTIONS TO SE COMPLETED In 90 DAYS, A PNASE I ACTION tREPORT. CONFIRMATION AND JUSTIFICATION) IN SIM MONTNS AND PNASE II (SPECIFIC RE9UIREMENTS)
IN NINE MONTHS.
ALL LICENSEES (fICEPT ONE) M AVE RESPONDED TO THE CECEMSER
- 22. 1980 CENERIC LETTER AND INEIR RESPONSES MAVE SEEN tvatU41ED. WINE PL ANTS MAD Rf eUE$f fD EXIENSIONS TO THE SEPTEM8ER 22. 1980 RESPONSE DATE.
A-39 OETERMINATION OF MARE I-92-29-88 NUREG-8743 GENERIC LEffERS TRANSMITTING THESE BYRON SIE0EL SAFETY RELIEF VALVE MARE 31-09-30-82 NUREG-0783 NUREGS TO BWR APPLICANIS AND LICENSEES 492-7$34 (SRV) POOL DYNAMIC MARK III-t9-94-82 NUREG-0802 NAVE SEEN ISSUED.
LOADS AND TEMPERATURE LIMITS FOR BWR CONTAINMENT A-42.
PIPE CRACKS IN JULY 1989 NUREG-0313 REW, t IN FESR6JARY 9989. NURE0*0313. Eff. I WAS DICK CLARE SOILING WATER ISSUED 80 ALL NOLDERS OF SWR OPERATING 492*7162 REACIORS LICENSES OR CONSTRUCTION PERMIf5 AND TO ALL APPLICANTS FOR OPERATING LICENSES. SY JULY 1 1989 INE APPLICANTSiLICENSEES WERE TO PROVIDE THEIR PROGRAM FOR REPLACEMENT OF SERVICE SENSITITIVE LINES AND WELDS. THEIR PROGRAM FOR AUGMENTED INSERVICE INSPECTION.
THEIR PROGRAM FOR IMPROMING INF b4TER CHEMISTRY ENVIRONMENT AE0 INC0PORATION OF ADEGUAff LEAR DEFECTION CAPABILITY, att LICENSEES MAVE RESPONDED AND INEIR REPLIES ARE SEING fv8LUAIED BY A TECHNICAL SUPPORT CONTRACIOR (INEL).
INITIAL fER'S ARE SCHEDULED TO BE COMPLETED IN THE SECOND AND INIRD SUARIERS OF Fv83.
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