ML20070H818

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Unresolved Safety Issues Summary.Data as of November 19, 1982. (Aqua Book)
ML20070H818
Person / Time
Issue date: 12/01/1982
From:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
To:
References
NUREG-0606, NUREG-0606-V04-N04, NUREG-606, NUREG-606-V4-N4, NUDOCS 8212270243
Download: ML20070H818 (50)
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NUREG-0606 Vol. 4, No. 4 November it.1982 UNRESOLVED SAFETY ISSUES

SUMMARY

1 AQUA BOOK atIP b shed mter 982 Prepared for: OFFICE OF RESOURCE MANAGEMENT TORY M $54011 WASHillGT0ll, DA 20555 / \\ \\ 1 l i

FOREWOC3 THE 'UNNESOLVf D S AFETY ISSUES"

SUMMARY

IS DESIGNED TO PROVIDE THE MAN AGEPENT OF THE MUCLE AR REGUL AIORY COMMISSION WIIM A QUARTERLY OVERVIEW OF THE PROGRESS AND PL AN's FOR COMPLETION OF GENERIC 1 ASES A'JDRESSING " UNRESOLVED SAFETY ISSUES

  • REPORTED TO CONGRESS PURSUANT TO SECTION 239 0F THE ENF0GY REORGANIZAi!0N ACT OF 1974 AS AMENDED.

THIS

SUMMARY

Ui!Li2ES DATA COLLECTED FROM THE OFF',CE OF NUCLEAR REACTOR REGULATION. OFFICE OF NUCLEAR REGULATORT RESEARCN. AND THE NATIONAL L ABORATORIES AND IS PREPARED SY THE OFFICE OF RESCURCE MANAGEMENI. THE DEFINITION OF WHAT CONSTITUTES COMPLETION OF AN UNRESOLVED SAFETY ISSUE IUSI) HAS RECENTLY SEEN EXPANDED TO INCLUDE THE IMPLEMENTA110N OF THE TECHNICAL RESOLUTION. THIS IS IN ACENOW-LEDGEMENT OF INE FACT THAT REAL SAFETY BENEFITS SCCUR ONLY AFTER THE IMPLEMENTATION NAS TAKEN (LACE. IMPORIANT 2LEMENTS OF TH15 IMPLEMENTATION PHASE ARE: THE PROVISION OF A PUBLIC COMMENT PERIOD FOLLOWING THE ISSUANCE OF A DRAFT NUREG REPORT INCORPORATING THE STAFF'S TECHhlCAL RESOLUTION FOLLOWED BY A DISCUSSION AND DISPOSti!ON OF THE COMMENTS RECEIVED IN A FINAL NUREG NEPORT. I 2. THE PROVISION FOR INCORPORATION OF THE TECHNICAL RESOLUTION INTO THE NRC'S REGULATIONS. = ST ANDARD REVIEW PL AN. REGULATORY GUIDES. OR OlHER NRC OFFICIAL GUIDANCE OR REQUIREMENIS AS APPROPRIATE. APPLICAi!ON OF THE TECHNICAL RESOLUTION TO IMD!v! DUAL OPER ATING PL AMi$ THE PROVISION FOR 3. IN THE FORM OF HARDWARE OR DESIGN CHANGES. IECHNICAL SPECIFICATION CHANGE. AND/OR CHANGE TO OPER ATING PR**EDURES AS APPROPRI AT E. THE SCHEDULES IN THIS BOOK INCLUDE A MILESTONE AT THE END OF EACM ACTION PLAN MdICH REPRESENTS INE INITIATION OF THE IMPtEMENTATION PROCESS POTH WITN RESPECT TO INCORP1RAi!ON OF THE TECHNICAL RESOLut!ON IN THE NRC 0FFICI AL GUIDANCE OR REQUIREMENTS AND ALSO THE APPLICATION OF CHANGES TO THE *CHEDULE FOR IMPLEMENTAi!DM WILL NOT NORMALLY BE INCLUDED IN INDIVIDUAL OPERATING PLANTS. THE TASE ACTION PLAN (S) FOR THE RESOLUTION OF A USI $1NCE THE MATURE AND EXTENT OF INE ACTIVITIES NECESSARY 10 ACCOMPLISH THE IMPLEMENT Ai!ON C ANNOT MORMALLY SE REASONABLY DETERMINED PRIOR TO THE THE PROGRfSS AND STATUS FOR IMPLEMENTATION OF UNRESOLVED DETERMINATION OF A TECNNICAL RESOLUTION.RESOLU110N HAS SEEN COMPLETED ARE REPORTED SPECIFICALLY IN & SAFETY ISSUES FOR WHICH A TECHNICAL SEPARATE TABLE PROVIDED IN THIS SUMMART. RARL EN!EL. CHIEF OF THE GENERIC ISSUES SRANCH. DIVISION OF SAFETY TECHNOLOGY /NRR IS RESPONSISLE FOR MANAGING THE GENERIC TASKS INCLUDED IN THIS SUFW9ARY. l l s

s r s ( TABLE OF CONTENTS PACE Nc. TASK NO. TASK MANAGER DESCRIPTION 1-2 AB5REVIATIONS 3-S 0VERv!EW 6-9 USI'$ FOR WHICN TECHNICAL RESOLUTION IS COMPLETE 10-12 A-1 ALECK SERK!Z WATER NAMMER 13-64 A-3, A-4. A-5 JACK STR0$ NICER W. CE AND BIW STEAM GENERATOR TUBE INTEGRITY 15-16 A-It RICHARO JOHNSON REACTOR VESSEL MATERIALS TOUGNNESS 17-18 A-12 RICHARO JONH30N FRACTURE TOUGNMESS OF STEAM GENERATOR ANO REACTOR COOLANT PUMP SUPPORTS 19 A-17 PAUL NORIAN (ACTING) SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS 20-22 A-39 TSUNG SU DETERMINATION OF SAFETY RELIEP VALVE (SRV) POOL OYNAMIC LOADS AMO TEMPER 4IURE LIMITS FOR BWR CONTAIMMENTS 23-26 A-48 PATRICK SEARS SEISMIC DESIGN CRITERIA-SNORT TERM PROGRAM 27-28 A-43 ALECK SERK!Z CCNTAINMENT EMERGENCY SUMP PERFORMANCE 29-30 A-44 PATRICK SARAN 0WSKY STATION SLACK 0UT ' 31-33 A-45 AMOREW MARChESE SNUTDOWN DECAY MEAT REMOVAL REQUIREMENTS 34-36 A-46 PATRICK SEARS SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS 37-38 A-47 ANDREW SZUKIEWICZ SAFETY IMPLICATIONS OF CONTROL SYSTEMS 39 A-48 TSUNG SU NYDROGEN CONTROL MEASURES AND EFFECTS OP NYDROGEN SURNS ON SAFETY Etu!PMENT 43-43 A-49 ROY N00DS PRES $URIZED THERMAL $ NOCK i I I

ABBREVIATION 2 AAts Accident Analysis Branch (Former M U Branch) Eels Environmental Engineering Sranch. Diw6 sten Als Admin 6stration Branch. Training and of Engineering (NRR) Administration Staf f (IE) EFry E f f ect 6ve Fu!!-Power years ACs Alternat6ng Curroat EG8Gs Edgerton. Germeshausen 4 Grier ACR$8 Advisory Coamittee on Reactor Safeguards EPs Emeroency Preparedness AD: Assistent Director EPR!s Electric Power Research Institute ADBs Analysss and Dewetopment tranch Division of Eess Equipment eva16fication Branch. Dielslen Reactor Safety Rescacch (RC5) of Engineer 6ng (NRR) ACB Accident Evaluation Branch. Division of FIN: F6nancial Systems Integration (NCR) FIRLs franklin Instituto Research Laboratories AE00s Of fice of thm Analyst s and Evaluation of Fgts Flu 6d Structure Interaction Operational Data FSIFs Fut!-Scale test Fact!6ty AIFs Atomic Indastrial Forum FWs f eedwater APTSs Action Plan Tracking System Cas Geosciences tranch. Divisten of Engineering (NRR) ARLs Alden Rosearch Laboratory GE: Ceneral Electric AS$s Austilary Systems Branch. Division of G33s Gener6c losues Branch. D6vlelen of $afety Systems Intecration (102) Technology (MRR) ASMEs American Sectety of Mechanical Enqineers NFES: Human facters Engineering Stanch. Olvissen 451Ms American Soc 6ety of Test 6ng Materials of Health. 56ttag and Waste Mget. (RES) AIW$s Anticspated Trans6ent Without Scram HFSs D6 v a sten of Human Facters Saf ety (NRR) 81 tis Baticock and Wilcom Cc7assy N$$is Heavy Soetten Steel Technetegy BNCs Brookhaven National Con:,crwatery ICSRs Instrumentatten and Centre! Branch. Bt;L s Brookhaven Nattena! Laboratory Divlston of Facility Dperat6 ens (RES) SOPS Balance of Plant IC55: Instrumentation and Centrol Systems trench. Et!R s Boiling Water Reactor Divissen of Systems Integratten (NRR) CE: Corbustion Encinacring. Incorporated IEs Of fice of Inspection and Enf orcement CEtv Cles6 cal Engineer 6ng Branch. 06viston of IEEE: Inst 6tute of Electrical and Electron 6cs Engineers Engineering (NRR) INELe Idaho Nuclear Enq6neering Laboratory CFRs Code of Federal Regulations IREPs Integrated Ren t abilt ty Evaluat 6en Progree CDs Cor.donsat t on Isolatten I$3s In-Serw6ce Inspection cps Construction Perm 64 LER 16censee Event Report CPBs Core Performance Branch. Divialen of LG5: Licenstag Guidance Branch. D6visten of Systems Integration (NRR) Safety T ec hnelegy (NER) CRs Contractor Report LLLe Lawrence (twermore Laboratory CRGRs Cominittee for Reviens of Generic Requir. monte LOCAs Less-of* Coolant Accident C5Bs Containment Systems Branch. Otw6 sten et (PPs toad Plant Program Systems Integration (NRR) LTPs tong Term Program DCs Direct Current tWRs 16qht-Water Reacter CC: Division of Engineering (MRR) MARR I-III: Containment types for Selling Water Reacters DFOs Division of Factitty Operations (RES) Miss Mechanical Engtesering tranch. DHFSs Divis6en of Huisan Factors Safety (NRR) Division of Engineering (NRR) DHRS: Decay Heat Removat Systea MESRs Materials Engtmeering Branch. DLs Division of Licensing (NRR) E s we s6en of Engineering Technelegy (RES) DOEs U. S. Departmant of Energy MITs Massachusetts Inst 6tute of Technology DORS Diw6sion of Operating Reactors MMRSs Metallurgy and Mater 6als Branch, (Former NOR Divis6on) Dev6sion of Reacter Safety Research (RES) DRAs Divis6en of Risk Analysi s (RES) Mstas Main Steam Line treak I D5Is Division of Systems Integratton (NRR) MIE8s Matertale Engineer 6ng Branch. Divialen DS$3 Division of Systems Safety of Engineering (NRR) (Former NRR D6 vision) MDEs Non-Destruct 6ve Examination DSTs Ot w6 sion of Safety Technology (NRR) NREPs Neutron Resonance Escape Probability Es Engineering NRLs Naval Research Laboratory EB Enforcement Branch. Enforcement and NRRs Office of Nuclear Reacter Regulatten Invest 6qations Staff (IE) N55: Nuclear Steam System ECCs Emergency Core Coeling HuREGs Nuclear Regulation 1 i I l 4 e a

t l ABBREVIATIONS 00s Owner's Group SSEs Safe Shutdown Earthquake OLs Operating License SSP 3s Standards Special Projects Branch (MAR) ORAss Operating Reacters Assessment Branch. Divisten of STPs Short-term Program Licensing (NRR) TAPS Tan 6 Actlen Plan \\ ORBS Operating Reacters Branch. Olvisten of TMs Mas Leg Temperature i Licensing (MAR) TMs Task Manager ORNLe Oak Ridge Natlenal Laboratory TMit Three Mlle Island GSDs Office of Standards Development U518 Unresolved Safety issue (Permer NRC Office) W Westinghouse Electric Corporatten OYSGs Once-Threveh Steam Generator WHs Water Maomer l PASNY8 Power Authority of the State of New York WUTAs Washington Unlversity Technology Assectates l PNL Pacefle Northosest Laboratory (Sattelle) PRAs Probabillstle Risk Assessment PS: Plant Systems PSl8 Pewer Systems Branch. DIwlelen of Systems Integretten (NRR) PSU8 Plant Systems Unit (AE00) PSYSs Plant Systems tranc% (Perser NRR 3 ranch) PTRBs Procedures and Test Review Sranch. Division of Numan Pacters Safety (MRR) ) FWRt Pressueired Water Reactor es Quality Centret er Assurances I RASI Rad 6elegical Assessment Branch. Divisten of l Systems Integratten (MRR) RCICs Reacter Core Isolation Coeling I' REPS Reference 1 RF as Of fice of Nuclear Regulatory Research 'rPt Request for Proposal RNR8 Residual Neat Removal RPV8 Reacter Pressure Wessel PRAI Probability and Elsk Assessment prats Rellability and Risk Assessmente Branch (MRR) RRRCs Regulatory Requirements Review Committee RSs Reacter Safety (Former NRR 3 ranch) RSBs Reacter Systems tranch. Divisten of Systems Integration (NRR) RSR Reacter Safety Research R$$ MAPS Reacter Safety Study Methodelegy Apslicatten Progree 9AI8 Science App!lcattens. Inc. SCCs Stress-Corresten Cracking SES Structural Engineering Branch. Divlelen of Engineering (NRR) SEPs Systematic Evaluatten Program SEP8s Systematic Evaluatlen Program tranch. Olvisten of Licensing (NRR) Sets Safety Evaluatten Report SCs Steam Generator SGWHI Steam Generator Water Nammer SML: Sandle Mattenal Laberatory SRPs Standard Review Plan SRW Safety Rollef Valve 2

PROOR A'J CVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS Keys (1) LPP = lead Plant Program (2) LTP - Long Term Program M/S - Met Scheduled USI AUG. 28. 1982 TITLE AOLA BOOK CURRENT REMARKS A-1, Water Hammer August le 1983 November 38, l983 MURES/CR-2781 was issued in July 1982. Development of a technical. findinOs MURf 6 is underway. Thle draft NUREO in belne used to develop recommendatlens to CRGR for resolution. A-3, Steam Generater March 30. 1983 March 30. 1983 The draft MUREG report has been reviewed by the A-4, Tube Integrity technical branches and their comments incorporated. The revtsed report in being prepared for manaoement review A-5. and then ut!! be issued for pub!lc comment. The MRC has formed a Task Force to prepare proposed requirements. A-ll, Reacter Vesse! October 15, 1982 October 15. 6942 NUREG-077te Rev. 1, was completed and submitted Materials for review. This revislen addresses public comments received on the For Comment report. This report was Toughness issued in &ctober 1982, thereby resolving thle Unresolved Safety Issue. 3 j 1 h I i i

h l 1 i 1 i PROGRAM OVERVIEW PROJECTED DATES FOTs ISSUING NRC STAFF REPORTS i UST AUG. 29e 1982 HILE A9UA 900K __ CURRENT RDMRQ A-ft. Steae Generator December 38, 1982 June 6. 1983 Meetings were held with EPRI and Industry grewps 8 Reacter in December 1989, to resolve use of fracture Costant Pump mechantes methods for ovalificatten of supports. Supports NRC reviewer's comments en the final MUREG-0577 were not received until mid-January 8982. causing i a deley in lesulng the final report. Comments i made by EPRI and the AIP subcommittee en material reautremente have been incorporated into the final i l MUREC. 4-17. Systems Inter-See Itee II.C.3 See Itse II.C.3 Werk planned under TAP A-17 ullt be performed under actlens in Actten Plan in Action Plan IMI Action Plan ties II.C.3. Systems Interactlen. Tracking System Tracking Systee The status of this item t o reported in the overterly updates of the TMI Actlen Plan Tracking Systest (APTS). A-39. SRV Peet Mark II-Septeeber Mark II-September MUREG-9763 en in-plant SRV tests was completed and Dynaelc St. 1982

30. 1982 lesved in June 8988 MUREG-8783 en Peet Temperature toads Mark I!!-October Mark III-October L6mits was lesved in October 1989.
11. 1982 14 1982 MUREG-0802 en SRV Guencher Leads was loswed in October 1982.

These three reports serve as the technical resolutten of USI A-39 A-40. Selsele Design July 45. 1983 March 16. 1986 A draft standard review plan change has been Celteria prepared and is under management review. A-43. Containment July 15. 1983 July 15. 1983 All technical support (NUREG/CRs) reporte have been Emergency Sump lesued except the ARL report en insvlatten debris transport and screen blockage effects. A reseletten NUREG is in the f6nal stages of preparatten and ullt underge management concurrence. A CRGR betafing ut t! be held Neventrer 24 1982 to discuss the resolutten of this USI. 4

PR3% RAM CVERVIEU PROJECTED DATES FOR ISSUING NRC STAFF REPORTS US! AUG. 20. 1982

11117, AQUA 800K CURRENT REMARKS A-44. Station Blackout October 15. 1983 December 15. 1983 Draft contracter technical reports were provided in May 1982. Final reports are now in preparatten.

A-45. Shutdown Decay October 30. 1985 October 39. 1985 A Task Action Plan was issued on October 7. 1981 Heat Removal and revised en June 2. 1982. A technical assistance Requirements contract package was approved on Apel! 9. 1982 and leptemented with Sandla en May 80. 1982. A-46. Selselo Quallft-Mat t. 1984 Apet! 30. 1984 This progree was redirected to be made compatibile cation of Equip-with the Equipment tualification Program Plan. The meet in Opera-final Task Actlen Plan has been issued. Idork has ting Plants been initiated on a!! tasks with all centracters me!! late their subtasks. A-47. Safety leolica-M/S M/S An approved Task Actlen Plan was issued en Sept. tiens of Contret

27. 9982.

Technica! *?sistance centracts have Systems been established with ORML and IMEL. A-48. Hydroten Centrol M/S M/S A draft Task Actlen Plan was issued en Apell 2, Measures and 1982 for MRC comments. Werk has been suspended pending Mydrngen 8 urns management declelen en the scope of the TAP. en Safety Equipment A-49. Pressurized M/S M/S A-49 waa designated by the Ceemissten as an USI Thereat Sheck en December 25. 1941 The Task Actlen Plan was approved and issued en March 26. 1982. The draft short-tere peettien is under preparatten and util be completed in November 1982. As a result of the findings of the short-tere program, the A-49 network le gelng to be extensively revised. o 5 1

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION USI 1ASR MANAGERf IIfLE DATE CDMPLETED REPORTS PUBLISHED IPFLEMENTATION STATUS TELEPMaNR 4-2, ASYMMETRIC BLOWDOWN DEC. 1980 NUREG-0409 ALL PWR PLANT ASSESSMENTS FOR ASYMMETRIC JIM SN!A LCADS ON REACTOR LOADS HAVE BEEN RECEIVED AND ARE CURRENTLY 492-72Li PRIMARf COOL ANT BEING EVALUATED BY ST AFF AND CONTRACTOR SYSTEMS EG4G. AS A SAS!$ FOR THIS Ed4LUAI!ON. STAFF IS IMPLEMINTING CRITERIA DEVELOPED AS PART OF INE IASR ACTION PLAN A-2. THESE CRITERI A ARE INCLUOLD IN NURES-6699. 88W AND CE OWNERS' GROUPS H AVE RESPONDED TO THE GUESTIONS RAISED AS A RESULT OF OUR IN!!!AL REVIEW OF THEIR SUBMITTALS ON THE ASSESSMENT OF THE PRIMARY SYSTEM COMPONENTS AD.D SUPPORTS TO ASYMMETRIC LOCA LOADS. THESE RESPONSES ARE CURREN1LY BEING REVIEWED AND THE REVIEW IS EXPECTED TO DE COMPLETED BY NOVEMSER 1985. TME WESTINGHOUSE OWNERS GROUPS EXPECT A RESOLUTION OF iMIS ISSUE ON THE BASIS OF ' LEAR BEFORE BREAR' CRITERIA. AN INTERNAL REPORT, RECOMMENDING ACCEPTANCE OF IME ' LEAR SE7nRE BREAR* CONCEPT ISSUE 0 BY THE STAFF IN FEBRUARY 1981, MAS BEEN DISCUSSED WITN THE ACRS AND IS UNDER REVIEW SY NRR MANAGEMENT PRIDR TO REVIEW SY CRGR. A-6, MARR I SHORT TERM DEC. 1977 NUREG-9408 CDMPLETE - ALL PLANT UN!4UE ANALYSES PROGRAM AND E4UIPMENT MODIFICATIONS AS REQUIRED WERE REVIEWED AND ACCEPIED AND APPROPR-Init TECHNICAL SPECIFICATI01 CHANGES WERE MADE. 6 i

UII'S FOR CHICH TECHNICAL RES!LUTION 13 C2:'PLETE IMPLEMENTATION USI TASR MANAGER / JLL TITLE DATE COMPLETED REPORTS PUBLISMED IMPLEMENTATION STATUS TELEPNnNR A-7, MARK I LONG TERM JULY 1980 MUREG-0668 LICENSEES ARE IN THE PROCESS OF BYROM $1EGEL PROGRAM AUGUST 1982 MUREG-0669, SUPPL. DESIGNING AND INST ALLING Mon!FICATIONS 492-T554 No. I 10 MEET THE COMMISSION'S ORDER DATE FOR EACH OPERATING PLANT. THE LTCENSEES ARE IN iME PROCESS OF PREPARING PLANT = UNIQUE ANALYSIS FOR SUSMITIAL TO THE STAFF FOR POSI IMPLEMENTATION AUDIT REVIEW FOR COMt!ANCE WITN THE ACCEPTANCE CRITERIA CONTAINED IN APPENDIE A TO MUREG-0669 THREE LI;ENSEES/ APPLICANTS NAVE SUDMITIED THEIR PLANT-UNIQUE ANALYSIS. A-4, Mdt II CONTAINMENT AUGUST 1989 NUREG-0808 THE REGUIREMENTS RECOMMENDED IN NUREG-PO' '. DYNAMIC LOADS 0808 ARE DEING IMPLEMENTED DURING THE OPERATING LICENSE REVIEW FOR EACM PLANT W!iN A MARK II CONTAINMENT. THESE REQUIREMENTS WILL ALSO DE INCLUDED AS AN ADDITION TO IHE APPROPRIATE SECTION OF THE ST ANDARD REVIEW PL AN. A-9, ATWS SEPI. 9980 MUREG 0468, TWO VERSIONS OF THE PROPOSED ATWS DAVID PYAff, PES WOL. 4 RULE MAVE BEEN ISSUED FOR COMMENf3 445-S940 46FRS7523 THE SIAFF VERSION AND AN ALTERNAIE WERSION OF THE RULE PREPARED AT THE DIRECTION OF COMMISSIONER MENDRIE. FOLLOWING THE COMMENT PERIOD AND CONSIDERATION OF PUSLIC COMMENTS, 4 FINAL RULE WILL SE PREPARED FOR COMMISSION CONSIDERATION. A TASE FORCE MAS SEEN ASSIGNED TO FORM A BAS!$ FOR 1NE FINAL RULE. i j 7 [ l s

l USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE i 1 l IMPLEMENTATION USI TASK MANAGERS

111Lf, DATE COMPLETED REP 0Ril PUBLISHED IMPLEMENTAff0N STATUS TELEPHONE

\\ A-10. SWR FEEDWATER M0W. 1980 MUREG-06t9 RESPONSES FROM LICENSEES TO AN Paut721) O'CONNOR N0Z2LE CRACF.IMG IMPLEMENTATION LETTER MAVE BEEN 492 RECEIVED AND RECDPMENDED TRE&iMENT OP TMESE RESPONSES MAVE SEEN SUBMITTED TO MRC MANAGEMENT. ADDITIONAL INFORMATION MAS SEEN REGUESTED OF LICENSEES. IMPLEPENTATION ACTION IS PROCEEDING. THIRTEEN PLANTS MAVE RECE1VED LETTERS ACCEPTING THEIR PROPOSED MODIFICATION PLANS. TEN PLANTS ARE BEING REVIEWED AND NEGoiI ATIONS ARE UNDER WAY 10 CSTAIN LICENSEE COMMITMENTS TO IMPLEMENT ALL MUREG-$619 GUIDANCE. LACROSSE. BIG ROCK POINT. AND DRESDEN 1 DG MOT MVE SUSCEPTISLE PL ANT SYSTEM CONFIGUR ATIONS AND ARE CONSIDERED COMPLETE WITN REGARD TO IMIS ACTION. HUM 90LDT BAY. BY VIRTUE OF IIS STATUS (SMUIDOWN. NO FORSEEASLE RESTART 3e IS ALSO CONSIDERED COMPLETE. A-St. REACTOR VESSEL OCTOBER 15. 1982 MUREG-8744. GENERIC LEff ER TR ANSMIf f!NG THIS AL DEAGAZIO MATERIALS TOUCHNISS VOLS. I AMD II MUREG REPORT IS BEING PREPARED BY DL. 492-6945 l A-24. GUALIFICAi!CN AUG. 1981 NUREG-9584 Ett MAS TME LEAD IN IMPLEMENTING JOSE' CALVO OF CLASS tE THE POSITIONS IDENTIFIED IN THE REPORT. 492-4565 SAFETY RELATED E4UIPMENT A-26. REACTOR VESSEL SEPT. 1978 MUREG-9724 Att PL ANTS WERE REGUESTED TO PROVIDE AL DEASAZIO PRESSURE TRANSIEhT AN OVERPRES5URE PREVENTION SYSTEM 992-8945 PRofECTION THAT WoutD BE USED WHENEVER THE PLANT WAS IN A COLD SMUTDOWN CONDIi!ON. ALL PWRS IMPLEMENTED INEIR SYSTEMS NITN PRELIMINARY APPROVAL FROM THE MRC AND = A COMPLETE REVIEW 100K PLACE WM A POST-IMPLEMENTATION BASIS. THE REVIEW CONSISTS OF THREE PARTSt 43 ELECTRICAL ASPECTSs 93 REACTOR SYSTEM ASPECTS 3 C3 TECHNICAL SPECIFICATIONS. PLANTS REMAINING 10 SE EVALUATED ARE BEING REVIEWED BY CONTR ACT WITN EGAG. THIS INCLUDES FIVE OF iME TWELVE REMAINING PLANTS. FOR THE OTHER SEVEN PLANTS. SIX SER'S M AVE BEEN COMPLET ED AND ARE IN THE PROCESS OF BEING ISSUED. 8

i l USI'S FSR WHICH TECHNICAL [ESILUTION C3 COMPLETE 1 l l I IMPLEMENTAi!9N IASK MANAGER / l USI TITL E f) ATE CCMPLETED PEPORTS PUBLISHED IMPLEMENTAffBN STAYUS IELEPHONE l A-St. RESIDUAL NEAT 1978 MO FORMAL REPORT RRRC APPROVED IMPLEMENTATION PLAN TOM NOVAK REMOVAL REGUIREMENTS SRP S.4.7 REVISION JANUARY St. 1978. IMPLEMENTATION 492-7487 FOR OPERATING REACTORS Not COMPLEli. A-36. CONTROL OF HEAVY JULY 1980 NUREG-0612 IMPLEMENTATION REOUIREMENTS WERE DUD RE4UA LOADS MEAR SPENT ISSUED TO ALL LICENSEES SY LETIER 492-7477 FUEL DATED DECEMsER 22. 1980. THE LETTER l REQUESTED 3 INTERIM ACTIONS TO SE j COMPLETED IN 90 DAYS. A PHASE I ACTION (REPORI. CONFIRMATION AND JUS!!FICATION) IN SIX MONINS AND PHASE II (SPECIFIC REQUIREMENTS) IN MIME MONTMS. ALL LICENSEES (EXCEPT ONE) MAVE RESPONDED 10 THE Of CEMBER

22. 1984 GENERIC LETTER AND INEIR i

RESPONSES NAVE SEEN EVALUATED. NINE PL ANTS NAD REQUESTED EXTENSIONS 10 THE SEPTEMBER 22. 1988 RESPONSE DATE. ( REWAUNEE IS SCHEDULED TO RESPOND BY i (1t/14/42. A-39. DETERMINATION OF MARK I-02-29-80 NUREG-8743 GENERIC LETTER TRANSMITTING ALL THREE BYRON SIEGEL S AFETY RELI'.F VALVE MARK II-99-38*S2 NUREG-0783 NUREGS TO SWR APPLICANTS AND LICENSEES 492-7S34 (SRV) POOL DYNAMIC MARE III-90-14-42 NUREG*S602 IS IN THE DL CONCUNRENCE CHAIN. LOADS AND TEMPERAi4RE l I LIMITS FOR SWR CONTAIMMENT A-42, PIPE CRACRS IN JULY 1940 NUREG-4513 REV. 9 IN FEBRUARY 1981. NUREG-0313. REV. 1 WAS DICE CIARE SOILING WATER ISSUEC 10 ALL N0LDERS OF SWR OPE. RATING 492-7862 REACTORS LICENSES OR CONSTRUCTION PERMIIS AND TO ALL APPLICANTS FOR OPERATING LICENSES. tY JbLY f. 1989 THE APPLICANTS / LICENSEES WERE 10 PROVIDE THEIR PROGRAM FOR REPL ACEMENT OF SERVICE SENSITITIVE LINES AND WELDS. THEIR PROGRAM FOR AUGMENTED INSERVICE INSPECTION. THEIR PROGRAM FOR IMPROVING INE WATER CHEMISTRY ENVIRONMENT AND INCOPORATION OF ADE00 ATE LEAE DETECTION CAPABILITY. ALL LICENSEES HAVE RESPONDED AND THEIR REPLIES ARE BEING EVALUATED BY A TECHNICAL OUPPoti i CONTRACTOR (INEL). Ih!TIAL TER'S AmE SCNEDULED TO DE COMPLETED IN IME SECOND AND THIRD 4UARTERS OF FYs3. 9 e

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== L.~~~ PRESSURIZED THERMAL SHOCK (A-49) Ys .-,, Q Y ^ana.%'~~-*- M AS A RESULT OF THE SHORT TERM .e s.a== d FINDINGS. THE A4 NETWORK IS ^

  • d D._ _ _ _ _ _ GOING TO BE EXTENSN 6

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1- + = PRESSURIZED THERMAL SHOCK (A-49) ""~ '"~ m,, h=O h~ Continued Y AS A RESULT OF THE SHORT TERM FINDINGS, THE A-40 NETWORK IS 8 00 LNG TO BE EXTENSIVELY REVISED. I 'w"'*"" D v=.* 2 x,. U" _ On g m.-= =:_y. s- _ ::= ..= .,. n -,- n -- o -- a -.. @ e :n =- p -e -g v y s, v i i i 1 i I l l I a=,"** 1 a-s-i L ** c

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""C**""* "8"'"U"***********'88 us mucteam neoutavcay connasses NUREG-0606. Vol. 4. No. 4 SISLIOGMAPHIC DATA SHEET . titta a=o suoresta sa.even m. .aees a me.e e, mas thresolved Safety Issues Susumery (Aqua 8004) 3 ascaria=vs acce ssen. =o. p aurecasa s oars aeront coueterno asome tee g we se l November 1982 e cea.oam o casamisation e.nus a o unsumo acoarss e.,*,.ie c s ears nacoat issueo Office of Resource Management Decem'ber lve*a

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m2 Management Information tranch U. 5. Nuclear Regulatory Casumission e am., Washington. D. C. 20555 e no.e e-en is neo son =o oncas ravion =aus amo uniumo aconaas a.re,e se c # io enon ct ins.vwona u= 1 mo Office of Resource Management Managemant Information Branch ,,contanc,=o U. 5. Nuclear Regulatory Cosumission Washington. D. C. 20555

a _ _.a..

a_ ,,,v o.a..on, August 21. 1982 November 19. 1982 i,...., ,ss_t.u.=,a.v o s ,a..s, a nc. P7 vide en overvfew of the status of the progress and plans for resolution of the generic tasks addressing ' Unresolved Safety Issues" as reported to Congress. e r me v noaos a=o coruus= amatvs.s

n. La sca* ions t 7a s00 =Ts.it as OPE = E=De o Ttaus is avastagetsTv slaftW =T to si unif v CL Ass tra s.a.eu 7' %Q O. Fa f.E b
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