ML20024A601

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Unresolved Safety Issues Summary.Data as of May 27,1983. (Aqua Book)
ML20024A601
Person / Time
Issue date: 06/30/1983
From:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
To:
References
NUREG-0606, NUREG-0606-V05-N02, NUREG-606, NUREG-606-V5-N2, NUDOCS 8306210383
Download: ML20024A601 (49)


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NUREG-0606 Vol. 5, No. 2 Mar U,1983 UNRESOLVED SAFETY ISSUES

SUMMARY

AQUA BOOK t

"Nf[d7I=1sI3 Prepared foc OFFICE OF RESOURCE MANAGEMENT NUC GULATORY M $$10N WASHINGTON, D.C. 20555

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1HE " UNRESOLVED SAFETY IS5UES" $UMMARY 15 DESIGNED TO PROVIDE THE MANAGEMENT OF THE NUCLEAR REGULATORY COMMISSION WITH A QUARTERLY OVERVIEW OF THE PROGRESS AND PLANS FOR CDMPLETION OF t

l GENERIC TASKS ADDRESSING " UNRESOLVED SAFETY IS5UES" REPORTED TO CONGRESS PUR$UANT TO SECTION l

240 0F THE ENERGY REORGANIZA110N ACT OF 1974 A5 AMENDED. THIS

SUMMARY

UTILIZE 5 DATA COLLECTED FROM THE OFFICE OF NUCLEAR REACTOR REGULATION, OFFICE OF NUCLEAR REGULATOPY RESEARCH, j

AND THE NATIONAL LABORATORIES AND 15 PREPARED BY THE OFFICE OF RESOURCE MANAGEMENT.

THE DEFINITION OF WHAT CONSTITUTES COMPLETION OF AN UNRESOLVED SAFETY ISSUE (U5I) H15 RECENTLY BEEN EXPANDED TO INCLUDE THE IMPLEMENTATION OF THE TECHNICAL RESOLUTION. THIS 15 IN ACKNOW-LEDGEMENT OF THE FACT THAT REAL SAFETY BENEFITS OCCUR ONLY AFTER THE IMPLEMENTATICM HAS TAKEN PLACE. IMPORTANT EL EMENTS OF THIS IMPLEMENI ATION PHASE ARE8 I

I.

THE PROVISION OF A PUBLIC COMMENT PERIOD FOLLOWING THE ISSUANCE OF A DRAFT NUREG REPORT INCORPORATING THE STAFF'S TECHNICAL RESOLUTION FOLLOWED SY A DISCUS $10N AND DISPOSITION OF THE COMMENIS RECEIVED IN A FINAL NUREG REPORT.

2.

THE PROVISION FOR INCORPORATION OF THE TECHNICAL RESOLUTION INTO THE MRC'5 REGULATIONS, ST ANDARD REVIEW PL AN, REGUL ATORY GUIDES, OR OTHER HRC OFFICI AL GUIDANCE OR REQUIREMENIS A5 APPROPRIATE.

3.

THE PROVISION FOR APPLICATION OF THE TECHNICAL RESOLUTION TO INDIVIDUAL OPERATING PLANTS IN THE FORM OF HARDWARE OR DESIGN CHANGES. TECHNICAL SPECIFICATION CHANGE, AND/OR CHANGE TO OPERATING PROCEDURES A5 APPROPRIATE.

THE SCHEDULES IN THIS BOOK INCLUDE A MILESTONE AT THE END OF EACH ACTION PLAN WHICH REPRESENTS THE INITI ATIDH OF THE IMPLEMENTATION PROCESS BOTH W!iH RESPECT TO INCORPORATION OF THE TECHNICAL RESOLUTIDH IN THE NRC OFFICIAL GUIDANCE OR REQUIREMENTS AND ALSO THE APPLICATION OF CHANGES TO INDIVIDUAL OPERATING PLANI 5.

THE SCHEDULE FOR IMPLEMENTATION WILL NOT NORMALLY BE INCLUDED IN THE TASK ACTION PLAN (5) FOR THE RESOLUTION OF A USI SINCE THE NATURE AND EXTENT OF THE ACTIVITIES NECESSARY 10 ACCOMPLISH THE IMPLEMENIATION CANNOT NORMALLY BE REASONABLY DETERMlHED PRIOR TO THE DETERMINATIDH OF A TECHNICAL RESOLUTION. THE PROGRESS AND STATUS FOR IMPLEMENTATION OF UNRESOLVED SAFETY ISSUES FOR WHICH A TECHNICAL RESOLUTION HAS BEEN CDMPLETED ARE REPORTED SPECIFICALLY IN A SEPARATE TABLE PROVIDED IN THIS

SUMMARY

KARL KNIEL, CHIEF OF THE GENERIC ISSUES BRANCH. DIVISION OF SAFETY TECHNOLOGY /NRR, 15 RESPONSIBLE FOR MANAGING THE GENERIC TASKS INCLUDED IN THIS SDMMARY.

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MAJOR MILESTONE

TABLE OF CONTENTS l

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PAGE NO.

TASK NO.

TASK MANAGER DESCRIPTION 1-2 AB8REVIATIONS 3-5 OVERVIEW 6-9 USI'$ FOR WHICH TECHNICAL RESOLUTION IS COMPLETE 10-12 A-1 ALECK SERK!Z WATER HAMMER 13-14 A-3. A-4. A-5 JACK STR05NIDER W. Ct. AND 88W STEAM GENERATOR TUBE INTEGRITY 15-16 A-12 RICHARD JOHNSON FRACTURE TOUGHNESS OF STEAM GENERATOR AND REACTOR COOLANT I

PUMP SUPPORTS l

j 17 A-17 FRANK COFFMAN SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS 18-21 A-40 SYED SHAUKAT SEISMIC DESIGN CRITERIA-SHORT TERM PROGRAM t

22-25 A-43 ALECK SERKIZ CONTAINMENT EMERGENCY SUMP PERFORMANCE-1 24-25 A-44 ALAN RU8IN STATION BLACK 0UT

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26-28 A-45 ANDREW MARCHESE SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS 29-31 A-46 T.Y. CHANG SEI5MIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS 32-36 A-47 ANDREW $2UKIEWICZ SAFETY IMPLICATIONS OF CONTROL S'15 TEM 5 37-39 A-48 TSUNG SU HYDROGEN CONTROL MEASURES AND EFFECTS OF NYDROGEN BURNS ON $AFETY EQUIPMENT 40-44 A-49 ROY WOOD $

PRESSURIZED THERMAL SHOCK I

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ATREVIATIONS AAS:

Accident Analysis Branch (Former NRR Branch)

EES:

Environmental Engineering Branch, Division abs Administration Branch, Training and of Engineering (NRR)

Adesnistration Staf f (IE)

EFPYs Effective Fu!!-Power Years

}

ACs Alternating Current EG8Gs Edgerton, Germeshausen 8 Grier ACR$s Advisory Committee on Reactor Safeguards EP Emergency Preparedness ads Assistant Director EPRIs Electric Power Research Institute AD88 Analysis and Development Branch, Division of EGBs Equipment Qualification Branch, Olvision Reactor Safety Research (RES) of Engineering (NRR)

AES Accident Evaluation Branch, Division of FIN:

Financial Systems Integration (NRR)

FSTFs Full-Scale Test Facility AEOD Office of the Analysis and Evaluation of FW Feeduator Operational Data FY Fiscal Year AIFs Atomic Industrial Forum GSBs Geosciences Branch, Division of Engineering (NRR)

APTSs Action Plan Tracking System GE:

General Electric ARL Alden Research Laboratory GIB:

Generic Issues Branch, Division of Safety ASS:

Auxiliary Systems tranch, Division of Technology (MRR)

Systems Integration (NRR)

HFEBs ASMEs American Society of Mechanical Enoineers Human Factors Engineering Branch, Division of Health, Siting and Waste Mont. (RES)

)

ASTMs American Society of Testing Materials HSSTs Heavy Section Steel Technolop ATWSs Anticipated Transient Without Scram ICSRs Instrumentation and Contral granch, B&Ws Babcock and Wilcon Company Division of Facility Operations (RES) i SNC8 Brookhaven National Conservatory ICSBs Instrumentation and Contro! Systems Branch, SNLs Brookhaven National Laboratory Division of Systems Integration (NRR)

BOP:

Balance of Plant IEs Office of Inspection and Enforcement i

SWRs Boiling Water Reactor IEEE Institute of Electrical and Electronics Engineers CEs Combustion Engineering. Incorporated INEL:

Idaho Nuclear Engineering Laboratory CES Chemical Engineering Sranch, Division of IPs Indian Point Engineering (NRR) 3 REPS Integrated Reliability Evaluation Program CFRs Code of Federal Regulations ISIS In-Service Inspection cps Construction Permit LAMLs Los Alamos National Laboratory CP3s Core Performance Branch, Division of LER:

Licensee Event Report 1

Systems Integration (NRR)

LLNL Lawrence Livermore National Laboratory CRs Contractor Report.

LOCA:

Loss-of-Coolant Accident CRGRs Comelitse to Rewtow Generic Requirements LPPs Lead Plant Program CSE:

Conta ~ nment Systems Branch, Divi sion of LTPs Long Term Program Systess Integration (HRR)

LWR 8 Light-Water Reactor DCs Dlrert Current MARK I-IIII Containment Types for Belling Water Reacters des Division of Engineering (NRR)

MEB Mechanical Engineering Branch, DEDR0GRs Depu :y Executive Director for Regional Division of Engineering (NRR)

Operations and Generic Requirements MEBRs Materials Engineering Branch.

DFOs Division of Facility Dperations (RES)

Division of Engineering Technology (RES)

DNFSs Division of Human Factors Safety (MRR)

MITs Massachusetts Institute of Technology DHR$s Decay Heat Removal Systems MSLBs Main Steam Line Sreak DLs Division of Licensing (NRR)

MTES:

Materials Engineering Branch, Division DOEs U. S. Department of Energy of Engineering (NRR)

DOR:

Division of Operatina Reactors NDEs Non-Destructive Esamination (Former NRR Divisioni NRCs Nuclear Regulatory Commisslan DRA Division of Risk Analysis (RES)

NREPs Neutron Resonance Escape Prabability DSIs Division of Systems Integration (NRR)

HRRs Office of Nuclea'r Reactor Regulation DSS:

Division of Systems Safety NS$8 Nuclear Steam System (Former NRR Division)

NUREGs Nuclear Regulatory Report (prepared in-house)

DSTs Division of Safety Technology (NRR)

Es Engineering E8s Enforcement Branch, Enforcement and Investigations Staff (IE)

ECC8 Emergency Core Cooling 1

i

I ABBREVIATIONS SSE:

Safe Shutdown Earthouake Operating License Standards Special Projects Branch Ots nRAS:

Operating Reactors Assessment Branch, Division of 55P3s Division of Licensing (MRR)

Licensing (MRR)-

ORBS operating Reactors Branch, Division of STPs Short-term Program TAPS Task Action Plan Licensing (MRR)

Technical Evaluation Report TER:

ORNLs Oak Ridge National Laboratory 05Ds Office of Standards Development TH:

Thermal Hydraulics TMr Task Manager (Former MRC Office)

OTSGs Once-Through Steam Generator TMis Three Mile Island University of California, Los Angeles PASNY:

Power Authority of the State of New York UCLAs Pacific Northwest Laboratory (Battelle)

U51:

Unresolved Safety Issue Westinghouse Electric Corporation PMLs PRAs Probabilistic Risk Assessment W:

P58:

Power Systems Branch, Division of WH Water Hammer Systems Integration (NRR)

Plant Systems Unit (AE00)

PSUs PTPBs Procedures and Test Review Branch, Division of Human Factors Safety (MRR)

Pressurized Water Reactor PWRs RAB Radiological Assessment Branch, Division of Systems Integration (NRR)

RCICs Reactor Core Isolation Cooling REFs Reference RE5:

Office of Nuclear Regulatory Research RFPs Request for Proposa!

RHR Residual Heat Removal RPVs Reactor Pressure vessel RMs Resource Management RRAS:

Reliability and Risk Assessments Branch Division of Safety Technology (NRR)

RRRCs Regulatory Requirements Review Committee Reactor Safety (Former NRR Sranch)

RS:

Reactor Systems Branch Division of R$3s Systems Integration (NRR)

R55 MAPS Reactor Safety Study Methodology Application Program RVs Reactor Vesse!

SA!:

Science App!Ications, Inc.

Stress-Corrosion Cracking Structural and Geotechnical Engineering Branch, Division SCC:

SGEBs of Engineering (MRR)

Systematic Evaluation Program SEPs SEP88 Systematic Evaluation Program 3 ranch, Diviolon of Licensing (MRR)

SER:

Safety Evaluation Report SGs Steam Generator SGWH Steam Generator Water Hammer SNL Sandia National Laboratory 50UGs Seismic Qualificatien Utilities Group SRPs Standard Review Plan SRVs Safety Relief Valve a

2

1 ABBREVIATIONS Safe Shutdown Earthquake SSE:

Standards Special Projects Branch Operating License SSPBs Operating Reactors Assessment Branch, Division of Divleton of Licensing (NRR)

OLs ORAS:

Licensing (NRR)

STP:

Short-term Program Operating Reactors tranch, Division of TAPS Task Action Plan ORBS Technical Evaluation Report Licensing (NRR)

TER:

ORNLs Oak Ridge National Laboratory TH:

Thermal Hydraulles Office of Standards Development TMs Task Manager OSDs Three Mile Island (Former NRC Office)

TM18 University of California, Los Angeles Once-Through Steam Generator UCLAs 075Gs Power Authority of the State of New York USIs Unresolved Safety Issue PASNY:

Pacific Northwest Laboratory (Battelle)

Westinghouse Electric Corporation us PNLs Probabilistic Risk Assessment PSBs Power Systems Branch, Division of WHs Water Hammer FRAs Systems Integration (NRR)

Plant Systems Unit (AE00)

PSUs Procedures and Test Review Branch, Division PTR5:

of Human Factors Safety (NRR)

Pressurized Water Reactor PWRs Radiological Assessment Branch, Division of 6

RABs Systems Integration (NRR)

RCICs Reactor Core Isolation Cooling Reference REFs Office of Nuclear Regulatory Research RESs RFPs Request for Proposal RHR:

Residual Heat Removat l

Reactor Pressure Wessel RPWI Resource Management RMs Rollabi!Ity and Risk Assessments Branch RRAB8 (NRR)

Division of Safety lechnology Regulatory Requirements Review Committee RRRCs Reactor Safety (Former NRR Branch)

RS:

Reactor Systems Branch, Division of RSBs Systems Integration (NRR)

Reactor Safety Study Methodology Application R$$ MAP Program l

RVs Reactor Vessel SAls Science Applications, Inc.

Stress-Corrosion CrackingStructural and Geotechnical Engineering Branch, Division SCC:

SGEBs of Engineering (MRR)

Systematic Evaluation Program Systematic Evaluation Program Branch, Divlslen SEPs SEP8:

of Licensing (NRR)

SER:

Safety Evaluation Report SGs Steam Generator SGWHs Steam Generator Water Hammer Sandia National Laboratory SNLs Seismic Qualification Utilities Group SOUGs SRPs Standard Rowlew Plan SRVs Safety Relief valve 2

PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS Keys N/$ - Not Scheduled USI Feb. 18. 1983 TITLE AQUA BOOK CURRENT REMARKS A-1, Water Hammer December 30, 1983 December 30, 1983 The staf f's tecivilcal findings are reported in NUREG-0927.

These findings were the basis for changes to SRP Sections 5.4.6, 5.4.7, 6.3.

9.2.1, 9.2.2, 10.3 and 10.4.7.

These documents. along with a Value-Impact Analysise ull! be issued for comment in May 1983.

A-3, Steam Generator Aprl! 30, 1983 April 30, 1983 The draf t NUREG report has been reviewed by the A-4 Tube Integrity technical branches and their comments incorporated.

A-5, The revised report is being prepared for management review and then will be issued for public comment.

The NRC has formed a Task Force to prepara proposed requirements.

A-12, Steam Generator July 1, 8983 July 1.

1983 Meetings were held with EPRI and Industry groups a Reactor in December 1980, to resolve use of fracture Coolant Pump mechanics methods for qualification of supports.

Supports NRC reviewer's comments on the final NUREG-0577 were not received until mid-January 1982. causing a delay in insulnq the final report. Comments made by EPRI and the AIF subcommittee on materlat requirements have been incorporated into the final NUREG. Preparation of the resolution package is neartnq completion for submittat to the CRGR for their final review and approval which is scheduled for June 1983.

A-17, Systems Inter-See Item II.C.3 October. 1984 Work originally planned under TAP A-l? and TMI actions in Action Plan Action Plan Item II.C.3. Systems Interaction.

Tracking System were combined under USI A-17 and a new Task Manager appointed.

3 1

PROGRAM OVERVIEW EFeb.

PROJECTED DATES FOR ISSUING NRC STAFF REP 18, 1983 USI AQUA BOOK CURRENT TITt A-40, Selsmic Deslqn March 16, 1984 Detober 10, 1984 The NRC staff has reached an agreement on acceptance of the proposed changes to the Criteria Standard Review Plan.

A schedule revision for completion of USI A-40 has been submitted to the NRR Director for approval.

A-43, Containment December 1, 1983 December 1, 1983 All technical support (NUREG/CRs) reports have been issued. HUREG-0897 and NUREG-0869 along with SRP Emergency Sump Section 6.2.2 were issued for pubtle comment in May 1983. When issued in final these documents will serve as the staff's resolution of USI A-43.

A-44, Station Blackout March 15, 1984 March 15, 1984 Draft contractor technical reports were provided in May 1982.

The schedule for this USI was revised to include a task to evaluate risk reductlen and costs of various plant flues needed for a value impact assessment. This additional task i s now complete and the draft resolution package is scheduled for submittal to the CRGR in June 1983.

A-45, Shutdown Decay Dctober 30, 1985 October 30, 1985 A Task Action Plan was issued on October 7, 1981.

with Revision I lesued on June 2, 1982.

A Revision Heat Removal 2 is now being reviewed by HRR management. A Requirements technical assistance contract package was approved on Aprl! 9, 1982 and' implemented with Sandla on May 10, 1983.

The first interim milestone report was issued for NRC staff review on December 22, 1982.

The second interim milestone report was issued for NRC staff review on March 29, 1983.

A-46, Se l-Aprl! 30, 1984 April 30, 1984 This program was redirecte e compatiblie with the Equipment Qualift ram Plan.

The ca p-final Task Action Plan has d.

Work han me Inq been initiated on all task contracte-s P1 well into their subtasks.

A-47, Safety Implica-January 30, 1986 September 30, 1985 An approved Task Action F1 ed on Sept.

27, 1982.

Technical Assistance contracts have tions of Control been established with ORNL and INF1.

Systems A-48. Hydrogen Control June 30, 1985 June 30, 1985 A Task Action Plan was approved on December 3,

1982. Work on this USI is limited to the generic Measures and resolution of hydrogen control and equipment Hydrogen Burns qualification for ice condenser and BWR Mark III on Safety Equipment containments. A Commission Paper regarding hydrogen control for Mark III and ice condenser containment has been reviewed by HRR reviewers and is scheduled 4

for CRGR review in May 1***

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1

PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS USI Feb. 18, 1983 TITLE AQUA BOOK CURRENT REMARKS A-49, Pressurized N/S N/S Thermal Shock A-49 was designated by the Commission as an USI on December 28. 1981.

The Task Action Plan was approved and issued on March 26. 1982.

MRC staff PT5 recommendations (SECY-82-465) were approved by the Commission in December 1982.

A new rule for PTS resolution is being drafted and will be published for comment in June 1983.

6

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5

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION USI TASK MANAGER /

TITLE DATE COMPLETED REPORTS PUBLISHED IMPLEMENTATION STATUS TELEPHONE A-2.

ASYMMETRIC BLLleDOWN DEC. 1988 NUREG-0609 ALL PWR PLANT ASSESSMENTS FOR ASYMMETRIC JIM SHEA LOADS ON REAC10R LOADS HAVE BEEN RECEIVED AND ARE CURRENTLY 492-7231 PRIMARY COOLANT BEING EVALUATED BY STAFF AND CONTRACTOR SYST EMS EGSG.

AS A BASIS FOR THIS EVALUATIDM, STAFF IS IMPLEMENTING CRITERIA DEVELOPED AS PART OF THE TASK ACTION PLAN A-2.

THESE CRITERIA ARE INCLUDED IN NUREG-0609.

88W AND CE OWNERS' CROUPS HAVE RESPONDED TO THE QUESTIONS RAISED AS A RESULT OF OUR INITIAL REVIEW OF THEIR SUBMITTALS ON THE ASSESSMENT OF THE PRIMARY SYSTEM COMPONENTS AND SUPPORTS TO ASYMMETRIC LOCA LOADS. THESE RESPONSES ARE CURRENTLY BEING REVIEWED. EIGHT TERS HAVE BEEN RECEIVED FROM THE SUBCONTRACTOR AND OTHERS ARE EXPECTED ON A REGULAR BASIS OVER THE NEXT YEAR-PLUS.

THE WESTINGHOUSE OWNERS GROUPS EXPECT A RESOLUTION OF THIS ISSUE ON THE BASIS OF

' LEAK BEFORE BREAK' CRITERIA. AN INTERNAL REPORT, RECOMMENDING ACCEPTANCE OF THE ' LEAK BEFORE 8REAK' CONCEPT ISSUED BY THE STAFF IN FEBRUARY 1985.

HAS BEEN DISCUSSED WITH THE ACR$ AND IS UNDER REVIEW BY HRR MANAGEMENT PRIOR TO REVEIW BY CRGR.

A-6, MARK I SHORT TERM

.DEC. 1977 NUREG-0408 COMPLETE - ALL PLANT UNIQUE ANALYSES PROGRAM AND EQUIPMENT MODIFICATIONS AS REQUIRED WERE REVIEWED AND ACCEPTED AND APPROPRIATE TECHNICAL SPECIFICATION CHANGES WERE MADE.

6

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE USI IMPLEMENTATION TASK MANAGER #

H2.

TITL E DATE COMPLETED REPORTS PUBtTSHED IMPLEMENTATION STATUS TELEPHONE A-7, MARK ! LONG TERM JULY 1980 NUREG-0661 LICENSEES ARE IN THE PROCESS OF BYRON SIEGEL PROCRAM AUGUST 1982 NUREG-0661, SUPPL. DESIGNING AND INSTALLING MODIFICATIONS 492-7534 No. 1 TO MEET THE COMMISSION'S ORDER DATE FOR EACH OPERATING PLANT.

THE LICENSEES ARE IN THE PROCESS OF PREPARING PLANT-UNIQUE ANALYSIS FOR SUBMITTAL TO THE STAFF FOR POST IMPLEMENTATION AUDIT REv!EW FOR COMPLIANCE WITH THE ACCEPTANCE CRITERIA CONTAINED IN APPENCIX A TO MUREG-0661.

TEN LICENSEES / APPLICANTS HAVE SUBMITTED I

THEIR PLANT-UNIQUE ANALYSIS. CUR CONTRACTORS, BNL AND THE FRANKLIN RESEARCH CENTER. ARE REVIEWING THESE SUBMITTALS.

A-8, MARK II CONTAINMENT AUGUST 1981 NUREG-0808 THE REQUIREMENTS RECOMMENDED IN NUREG-POOL DYNAMIC LOADS 0808 ARE SEING IMPLEMENTED DURING THE OPERATING LICENSE REVIEW FOR EACM PLANT WITH A MARK II CONTAINMENT. THESE REQUIREMENTS WILL AL50 SE INCLUDED AS AN ADDITION TO THE APPROPRIATE SECTION OF THE STANDARD REVIEW PLAN.

A-9, ATWS SEPT. 1980 NUREG 0460.

IN AUGUST 1982, TWO VERSIONS OF DAVID PYATT, RES VOL. 4 THE PROPOSED ATW5 RULE WERE ISSUED 443-5960 46FR57521 FOR COMMENTS THE STAFF VERSION AND AN ALTERNATE VER510N OF THE RULE PREPARED AT THE DIRECTION OF COMMISSIONER HENDRIE. FOLLOWING THE COMMENT PERIOD AND CONSIDERATION OF PUBLIC COMMENTS, A FINAL RULE WILL BE PREPARED FOR COMMI5510N CONSIDERATION.

A TASK FORCE HAS BEEN ASSIGNED TO FORM A BASIS FOR THE FINAL RULE.

IN APRIL 1983, THE TASK FORCE AND STEERING GR0ur DRAFTED THE FINAL RULE.

AFTER THE SALEM-l ATWS EVENT ON FEBRUARY 25, 1983.

SOME MODIFICATIONS TO THE FINAL RULE ARE BEING MADE.

ELEMENTS OF THE RULE WERE PRESENTED TO THE CRGR ON APRIL 20, 1983.

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USl'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION TASK MANAGER /

USI DATE COMPLETED REPORTS PUBLISHED IMPLEMENTATION STATUS TELEPHONE gg.

TITLE A-te, BWR FEEDWATER NOV. 1980 NUREG-0619 RESPONSES FROM LICENSEES TO AN ROBERT GILBERT I

IMPLEMENTATION LETTER HAVE BEEN 492-Ft28 N0Z2LE CRACKING RECEIVED AND RECOMMENDED TREATMENT OF THESE RESPONSE 5 HAVE BEEN SUBMITTED TO NRC MANAGEMENT. ADDITIONAL INFORMATION NAS BEEN REQUESTED OF f

LICENSEES. IMPLEMENTATION ACTION 15 1

PROCEEDING. THIRTELN PLANTS HAVE RECEIVED g

LETTERS ACCEPTING THEIR PROPOSED MODIFICATION PLANS.

TEN PLANIS ARE BEING REVIEWED AND NEGOTIATIONS ARE UNDER WAY TO OBTAIN LICENSEE COMMITMENTS TO IMPLEMENT ALL NUREG-0619 GUIDANCE. LACROSSE. BIG ROCK POINT.

AND DRE5 DEN 1 DO NOT HAVE SUSCEPTIBLE PLANT SYSTEM CONFIGURATIONS AND ARE CONSIDERED COMPLETE WITH REGARD TO THIS ACTION. HUMBOLDT BAY, BY VIRTUE OF ITS STATUS (SHUTDOWN. NO FORSEEABLE RESTART), !$ ALSO CONSIDERED COMPLETE.

A-11 REACTOR VESSEL OCTOBER 85, t982 NUREG-0744, GENFRIC LETTER 82-26 TRANSMITTED THIS AL DEAGAZIO VOLS. I AND II NUREG REPORT.

492-8945 M?.TERIALS TOUGNMESS A-24, QUALIFICATION AUG. 1981 NUREG-8588 EQB NAS THE LEAD IN IMPLEMENTING JOSE' CALVO THE POSITIONS IDEHi!FIED IN THE REPORT.

492-8563 OF CLASS 1E SAFETY RELATED EQUIPMENT A-26, REACTOR VESSEL SEPT. 1978 NUREG-0224 ALL PLANTS WERE REQUESTED TO PROVIDE AL DEADAZIO AN OVERPRESSURE PREVENTION SYSTEM 992-8945 PRESSURE TRANSIENT THAT WOULD BE USED WHENEVER THE PLANT PROTECTION WAS IN A COLD SHUTDOWN CONDITION. ALL PWR5 IMPLEMENTED THEIR SYSTEMS WITH PRELIMINARY APPROVAL FROM THE NRC. AND A COMPLETE REVIEW 100K PLACE ON A POSi-IMPLEMENTATION BASIS. NINE LICENSING ACTIONS REMAIN TO BE COMPLETED.

FOUR PLANT EVALUATIONS REMAIN TO BE COMPLETED. THE EVALUATIONS FOR FIVE OTHER PLAMIS HAVE BEEN COMPLETED AND ARE IN THE PROCESS OF BEING ISSUED.

8

(

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE I

l USI IMPLEMENTATION TASK MANAGER /

gg.

TITLE DATE COMPL ETED REPORTS PUBLISHED IPFLEMENTATION STATUS TELEPHONF A-31 RESIDUAL HEAT 1978 NO FORMAL REPORT RRRC APPROVED IMPLEMENTATION PLAN TOM NOVAE REMOVAL REQUIREMENTS SRP 5.4.7 REVISION JANUARY 31 1978.

IMPLEMENTATION 492-7817 FOR OPERATING REACTORS NOT CDMPLETE.

A-36, CONTROL OF HEAVY JULY 1980 MUREG-0612 IMPLEMENTATION REQUIREMENTS WERE BUD REQUA LOADS MEAR SPENT ISSUED TO ALL LICENSEES BY LETTER 492-78TT FUEL DATED DECEMBER 22, 1988.

THE LETTER REQUESTEDs INTERIM ACTIONS TO BE COMPLETED IN 98 DAYS. A PHASE I ACTION (REPORT, CONFIRMATION AND JUSTIFICATION) IN SIX MONTHS AND PHASE II (SPECIFIC REQUIREMENTS) i IN MIME MONTHS. ALL LICENSEES (EXCEPT ONE) HAVE RESPONDED TO THE DECEMBER 22, 1980 GENERIC LETTER AND THEIR RESPONSES HAVE BEEN EVALUATED. MINE PLANTS HAD REQUESTED EXTENSIONS TO THE SEPTEM8ER 22, 1981 RESPONSE DATE.

6 A-39, DETERMINATION OF MARK I-82-29-80 NUREG-0763 GENERIC LETTERS TRANSMITTING THESE BYRON SIEGEL SAFETY RELIEF VALVE MARK II-89-38-82 NUREG-8783 MUREGS TO BWR APPLICANTS AND LICENSEES 492-7534 (SRV) POOL DYNAMIC MARK III-10-14-82 NUREG-0802 HAVE BEEN ISSUED.

LOADS AND TEMPERATURE LIMITS FOR SWR CONTAINMENT A-42, PIPE CRACKS IN JULY 1980 MUREG-8383 REV. 1 IN FEBRUARY 1989, NUREG-8313. REV. I WAS DICK CLARE BOILING WATER ISSUED TO ALL HOLDERS OF BWR OPERATING 492-T162 REACTORS LICEN5ES OR CONSTRUCTION PERMITS AND TO ALL APPLICANTS FOR OPERATING LICENSES. SY JULY 1.

1981, THE APPLICANTS / LICENSEES WERE TO PROVIDE THEIR PROGRAM FOR REPLACEMENT OF SERVICE SENSITITIVE LINES AND WELDS. THEIR PROGRAM FOR AUGMENTED INSERVICE INSPECTION, THEIR PROGRAM FOR IMPROVING THE WATER CHEMISTRY ENVIRONMENT AND INCOP0 RATION OF ADEGUATE LEAK DETECTION CAPABILITY. ALL LICENSEES HAVE RESPONDED AND THEIR REPLIES ARE SEING EVALUATED BY A TECHNICAL SUPPORT CONTRACTOR (INEL).

INITIAL TER'S ARE SCHEDULED TO BE COMPLETED IN THE SECOMO AND THIRD QUARTERS OF FYS3.

9 4

i l

WATER HAMMER (A-1)

AS OF WEEK ENDING M AY 27. tse KEY PERSONNEL TASK REVIEWERS SCHEDULED COMPLETION TASK MANAGER NAME BRANCH 1978 ANNUAL Atsen Senstz men xasrn REPORT Q

S.nacxAv PTRB/D61FS C. GRAVES RSS/DSI CURRENT MPA ANALYST LLA'eIER XB192

  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION
  • TECHNICAL ASSISTANCE CONTRACTS
  • POTENTIAL PROBLEMS Sines 1900 these home been seer 138 Inmedones enesialag None.

Reseevelen efterte for A 1 are being eenducted usmear FIN No. AS461 of INEL Seth EGl>G 4dehe and Quadron i

weier^

in SWRo and PWRe reperend. The tweeer

.. ter stearn :

2 have htwelwed senem staff are beme utshaed.

. _ _. feedrtnge and piping. Sie RHR syseent ECC erstems, and _ ~

sprey. serwece wwmeer fece water ered stearn Eneo. The incidente have been et.

trebuted to sucet causes se rapid se *

' et senem peceetsL steenwertwen seues of sueeer, punip eenrmgs wwlth i

parteney ornpf7 unos and rapid weeve snetion. Meet of the damage reported hee been reisevetv edner, inwoh>

Ing pipe hengere and resteines however. shore howe been severes incedenne swhich hows resuhed in piping end wehee damage.

Tosh Acelen Plast TAP A1. eubelwideo resolueen of this Unreseeved Sofety Issue IUSD into the fotowing smoke:

l Teek 1: Weser Mommer Summary Ruperte Teek 2 Rosetuteen of Wuseer Honumer Issue Teek 3: Water Hemmer Peelden for Operedng Amecture l

Teek 4: Weser Hemmer Safety Studies Teek 1 and 4 have been compisemd and the reporte are i

l

  • a ** *** 'e'"rmes"er'e =to"s'e p"erm' e't.**"*""s"p* ort
  • STATUS

SUMMARY

d den M op th

' i l

teen since, e.estee above, damage estributed as tweeer sup shemose." " mode se in.se ead

' "'=es.

hee been reteWwefy ntiner. The lang eorm eeM FIN NO. CONTRACTOR OBLIGATED EXPENDED 8*-

Coon en I

of Teek 3, is en integrei part of she resoluden of shie se ee/en. ehe Caen

.ohe ess e d

_ _ me. It renese I

noeue'

  • ACRS INTERFACE INFORMATION esseo= se * *e A

e en,33 to issue she A 1 package "kr l

Teek 2 represente the resetuden sepect of Sito USl and piene for M eA e presented.

  1. h,YgE-ACIIS mempt hee been bepe edwteed of Wee ess>

AeSt EGDO 4debe

~

Cosman Sp esse gg ehsene estudese end.

e*Ame -

Otr 1 eM M e2FF.M

%,g,,,%,.g,,,,,,g gggggg g,,e,,,,,.forfR.I?,e 4 F' l

Feesestne _

-of the A t.. ^^ pesteen Oer. I eM M MW

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gg,,

gg g,,,

IC8tGR), a wee no CftS 5

1 Cosene w v

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to. e

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.n.eeer 1e 4.F. "Cesidenesee end F '

Syesenne.* These one the US4 A-t websolaisest Asutrese unie be deemed "For ?

" ese basy M e as-de, poseed eer puhee wie to preveded.

1 10 e imoicATES A CHANGE IN INFORMATION

WATER HAMMER (A-1) mxu RESOLUTION OF A-1, WATER HAMMER

','*"8,

.,s.-

~_
::::

a

?"-

" = '

mammm5mm wagg

'an mom amm ammmmma mamm I

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i :=._

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m..

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ear "a

& m m m m*"N N a m m m m m m m a e

,y b o m m E m*'"m T a m m m m m m m Q Y

.dd*TY y-EVALUATION OF

.c WATER HAMMER w

as as42c r

,. s

\\

a EVENTS AND

  • -*mmN""*-"""-

eset aats ent42r S

E

,,,,aa w.=,==,,,,,,,,

p rammamamm OF POTENTIAL sces s

" **7 ostsaac RESOLUTIONS

,,,Tc

'ji'j8l' o

~-

r *-----M52 wmm2=:mmmmmmmmmp".

eq

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11 l

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WATER HAMMER (A-1) Continued l

l

._e et._._e 4 % ~ pere,m.n

.e n_

n_

es _ -

NRR.

l e..s

.e

. _ C.mp.een NR R.e.

e.

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.. CRGR

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. D _ en CMGR C.,

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R-4 R-4 g

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l l

l TASK 1 REPORTS TASK 4.1 REPORT TASK 4.4 REPORTS NUR EG-0582," Water Hansmer in Nuclear Peever Plants" Chapman, R.L., et af "Revene and Evehsenen of Actual and W-

.. R L.,"An Anosyne Teel for Predactang the Treneses J#8YI878 Posentaes Weser Hemmer Even. m Nescener Piones" EG6G 8svairedynesswee Reenneng 8rene the Rased Fiskas of Yemens Pegeng lateruse Rpt., CAAP-TR442 (Rev. II, September 1979 Sveeems" EG&G Bneerun Apt RE E 7D000, Fahnsary 1979 Chapman. R.L.,"Weser Hanwner Studiet" EG4G latenne Rpt., CAAA TR 063 (Res.13, July 1990 (Propered for NRC Uesh TASK 4.2 REPORT gg,g,,, g, g,, = A, g,,,yg,,g p,,,,g,,, g,, p.,,,,,,,,, g,,,,,,,,g Ansev.s of Noctuer Pepeng Sv.em. Seepos.d to F ause Treneen.,"

NUREG/CR 2069,"Compdation of Achsel and $wepected Wme' EG&G interan Rpt., RE E 79413. Fenwwery IPresered for NRC inearnel Hanwner Events in Nuclear Power Plan.," hesy 1992.

Wednt AC Berry, RA "A SteerefhArt Literesure Usel Reveen, es Weser :"

." EG4G Interne Interont Rpt.

RE-A-74044 Aped 1979 propered for NRC Use)

Denemmet P.N.,"An investagstaen of the Sesem Veed Celtepes Water Hessuseer Ismhanne Adeshonent." EG&G Inneresse Rpt, RE-A 7tr229 Pehneery 1979 (rny-es for NRC ene nas uses TASK 2 REPORT TASK 4.3 REPORT

,,,,,,,4 y,,,,,,, %,, _

Light Weser Reester Planet Asty 1992 h

'gggg,",g yg y

7, I

NUREG/CR-2791," Evaluation of Water Hasmsner Even.in P

"An men of teen I 1990 (Peepseed for NRC Insemaa usel TASK 4.5 REPORT sonen,s.P,"..

ies W.cor :-

Anos eneendsvesse v

Renew," EG&G presummary Rye. EGG CAAP413% Ju8v 1990 Prepared for NRC for Use. e Prefugninery er Werbeg Desument) er 12

WEST., CE & B&W STEAM GENERATOR TUBE INTEGRITY lr L

5 5

AS OF WEEK ENDING MAv n. ions i

KEY PERSONNEL TASK REVIEWERS J. RAJA =

MEs/DE SCHEDULED COMPLETION

s. mRmm CEs/w TASK MANAGER NAME BRANCH 1978 ANNUAL J. sTROsNIM R

"-n F.ODAR ADB/R$R REPORT

'e'

J. sTRosniDER MEoRaiEs F. AustutEwicz AEs/Ds:

g) y W. PASEDAG AE8/D$3 L. FRANK MEBR/REs d 8**'

CURRENT MPA ANALYST C. PAR $ZEWSKI CE S/DE gg,,, g

  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION
  • TECHNICAL ASSISTANCE CONTRACTS
  • POTENTIAL PROBLEMS N fene='as **a'a' es*== *e -

.comw end

.. w.d enon a-o ead ea" he -* * *e *= cas-v ~^.=

wwwaed me= se== s.e.e.

se, is A. nes h n ded., m

.e.e= w Nan...er son.

a.me -e = w*

_ esse = n=ese-, =r way iy es,e n. de,.ded, enre.en endissed yem cones.ayof genes to oordy th.amy of men we.'Technecol Aetweeses (A4 A4 and A6) r.leted to PVOR see.sn

. of ei. seest w "senC. Doyedenen and

.w n a rNL. Th. =

hures and eyclie weemot weeking reducean to ests. eenester leonenge

. Seeam T Tub e

Th. wwnery

.. _ et dayeded see.su _

tubes and the 8"neratorm and estreteen induesd fotegue ere.eks.

A SANDIA = Presid. essesseines ense ais of sneene gemeener Rupene toessm*

I r

, e.f day ded quhes to to.4 ese. does

^^

. Elne h whtsgg tub.e h in.operateng enestere en esde es seeabeuh eencern is t.he.,

E.

Rkd es henthng e,eysm _.

m h har eh ensuphng plan for inearesse '

th ir int.gnty du mg smeenne oper.tsen and under acodont eenditieses 4LOCA er e mesa ses.m dese.1mises Insonet 600

, to stream serveseen kn. hepok) wee edequese, safety esteryns, erseheng en wtmyy weser. Metal sy 9

m

~

~

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,nerates tubes home evetseed doyedstion ehse to C BNL - Precede,tes,h, ment,, and to mesmgo and sween seeressen escheng. Both types

-m%,

een phosph.e.

ese

-oelat

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o g-e ese-ene

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w d.,,e e

='* "ka 'e

  • STAT'JS

SUMMARY

.ei heney noe w uw se s e,

r. io.=rs,a s.i w.e saws one ee.gh us - =
  • e m.=

me.desa a oesne. u.na a.m 4 y. im. s. nee Th. maC hoe.m med e Tom passe.nd- =w oeswen 4

- - hepe.ned.e.*en.o=

w us.ene ho m.

e.n..nde.n.ee oce. s.no a th.e..p.r need., time we mundo no eenee.n. o. The-.

n. - n.s espes

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. Th osens ma f -==. et e.,*nes,n e,.g.n.e,e,n.

_ heen epe

.d se the Genne sobe seasse tensch as esees poets an sh.

ih..eeuit the seeceemferenteel disecteen by flew inclue.d ochr. mon npene. es 30 tek.

..e., e eyeese _em and piene eeneed ime e.nes es and h.ee be.e.n hesweed to 1.bes lesseed ' ^ es

-u mne.

s T=.

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esseh e. om.eenge.ad denting.

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-- e w=

  • ACRS INTERFACE INFORMATION FIN NO. CONTRACTOR OBLIGATED EXPENDED e wmE

' wd ee m.

e.eYaee7

~

~

^" " ***

Th. eureene seemse es she peerem eso. emeussed 2314 PNL

$75.000

$75.000 weeh the ACRS howeel C.

-^

_en B2315 PNL

$ EON

$Em Th. psopened soeuteeniwies eie. ensueued wnsi este NE Seessa Genesseer Ownese' Group en Jue an. test freen sh. youp weee. ' v sepeoneer N. tM Selene. Appenemens. Ins. -

" a Vetu./heiseet

'.e th end seemed shear final draft supere.ea Sepeenter 23. IM Thes esport wee eene se og pWeg aw-for a The omff's cooloed...

ese he propese-

  1. een for.
e. ch. Dheeser. EenA by 4/e3.

13 e iNoicATes a CHANGE IN INFORMATION

9 C

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s FRACTURE TOUGHNESS OF STEAM GENERATOR AND

^

REACTOR COOLANT PUMP SUPPORTS (A-12)

,,o,,,,,,,,,,,

,,,,,,,,,s KEY PERSONNEL

-. TASK REVli3NERG SCHEDULED COMPLETION

.Aany Etuoi MT E.= >

1978 A'NNUAL TASK MANAGER NAME SRANCH RCPORT Acousf im nicwno a. aoNNeoN sones x2d7is-Q,,,) [. JM ~

oAve snLEns MTEstos V

NEtt RANoALL MTEston CURRENT MPA ANALYST o,.a,,,,,,

or,,,oo

~_

L. LANtER X28102 I *TECNtaCAL ASSISTANCE CONTRACTS

  • POTENTIAL PROBLEMS
  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION sense teh-me.e. h. p.e-ded ees-e.ee ese N

o.es me as-. es me i e-a.no==e= ** N-* aane NONE T

' fee lessioNor emereng and stehsonne.alue.e seesghseest el the speggessak Power Scenese Usese Nos. 9 and 2 e _

of esseshens law Grose wese reseed as es the poesneses See lesneNet emerung and The fossel asapur to the generes.

het been lee fractesre seeschnees of the seesse generecer and oesbanetted and k enchsdod as en appones to eeseter emetent passeep seppert snotoriets See memo NUM E G4577.

seesheses. Two ene,one esset spoo' TASTE 4 A3670s and ASTM AS72 70el owessed meet of the Lemeense Usermose 90edonal Let pree6ded e seat nieeeroes need lor these supperes. Toughness eMen.

. et she sommessees seessee~_

esseek mee eregesiaNy spacessed and noe un the seeemene ASTM esed week esause of the semperse esseng em.

more made en these heats for eineh se. eyes meeG.en the venue essapeet ^ -

prw eneses sneeseems use _

The seesghness of the cronsnes..

e

, Aas sensi es.ed se he edee sw. h== n= ee sh-noen et We AS72 stemt ses scheme 86W pose er en g

operossag eenspeemere et 00mp, le the eens ed Nereh Asens Umwe Nos.1 and 2. the appheent has agreed es eene the.oesnpererepre se the ASTM A572 s

..sospre.esa s====

m,,es,,s e. me. sees eveessa tenopeesgesre et 225eF proar se eeeeeer _

eineree,,eshe.se se lemmes s. hoes 1000 peso. Aenesserf pressesresc.e ew e he phed =

. es se he.e d.eeed N.no me es-e-e,s,,

- isee se.hes.n me soense,ed ep-ahne

.s.4,.

re.e e.e e.pp-e pie =r*.

  • STATUS

SUMMARY

s.n===*r =ee-* ead de*** '"" reg *e"re"n'9 U*e en other necesar plente the -

( *. '

es,ppe,e ser she Norm Anne fecehties are opphceMe noosee _

esed emeteadose esdesses mese W ee gener PvvR plasses. Se emme therefore meesese'Y Sergh ese soumEG SFF and theensymenong eeresse e' l\\

g es eseesses the frecieste eeughness of the steem himy 10.1M see _ _

- undesoF M eEWn*

  • 9 stecerises fee eN sparehngpgWR pienes and these gag,,,,,

,oe eg,esee, a g 3 e w

gesserseer and rescoor eestene possup sespoese p one r mee.

so _

e se CP and OL eemes.

  • ACRS INTERFACE INFORMATION

' FIN NO. CONTRACTOR O8 LIGATED EXPENOED t,,,,,,,e, toer,,,,,,,o, e,se i e e,remesa mese

=8-

'"6"*"*""

  • ^ " " * -

cense. _

s cope=== es ans ---e med NA, _

hie ---me e'eh de Thss paessamhey esN"be omseshgated en e"W,,es,s. -

Co,,,se e.,.u us,,e,,,,,=es.a.ese he.o orded w m wee

. ' hv E sensommig W h me N W W w

,,,,, gg g,g g,

peschmey se sesem geneseter and ps#"es, esonene

$ A4e3 LLIAL

$4 K SS E est pesump enspperes es esegensey aposened he the T&p e

some been - _

bues fined eIUetGG and med.

. ' hee been pseessed Schodnte has toen s ienced to oestore CAGA ** esse et aanpen e

sanoneseso _ _

  1. Ten CRGA poseege emme _

^ he the eensf.

meg.

_ einsey -. - he she esUottG end asse sap eerenese. R wee Gesuppded es sie Doetees. NRR 9ee esseene g a sqpeCArts A CHANGE IN INFORMATION

FRACTURE TOUGHNESS OF STEAM GENERATOR AND l

1 REACTOR COOLANT PUMP SUPPORTS (A-12)

== -

=-

":l0:."""

& ~. - q = 4 - f. _ g... _ _

= 4 :_ 4 ~_ q _____ 4 m

=

=.

=r

= = ~.

E ~ = C _ -

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559 ::::.

EE ::::-

59 p___q ____e:rg.:;___e_ _9_=_g_==4_=_g g

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l

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16

SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS (A-17)

AS OF WEEK ENDfNG MAY77,1WO KEY PERSONNEL TASK REVIEWERS 8 c "caRIS ARAF DST SCHEDULED COMPLETION TASK MANAGER NAME BRANCH

  1. FRANK COFFMAN X27487 1978 ANNUAL

,,, 8 79 gg M

REPORT s t. CanuAN RRAS/os?

l ssCONRAN RAAS/OST MPA ANALYST CURRENT

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KEY PERSONNEL TASK REVIEWERS

  1. D. LANGFORD Rse/ Dst SCHEDULED COMPLETION TASK MANAGER NAME BRANCH
  1. D. MATCHER RRAS/ W

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f Nn"AY""'esEmeo ORIGINAL s T. CHAN AssiDes S

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l SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS (A-45) ,, o,,,,x,,,,,, .A. SCHEDULED COMPLETION 5"5" 2 KEY PERSONNEL TASK REVIEWERS TASK MANAGER NAME BRANCH was eneumiNAny ANonEw uAnCUESE M2 M. CUNNfNGHAM DnARES ORIGINAL nas/oss A. eusuu nnAs/ost { T.mansu

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u.D.ecember 1980, so,.e.e.e. g-e.e. e-m., s.*es=. The i.o.e.e.ene a R== Anmyne end - to ,o,,,, e e - -e,,e, ,,,,,,se ee he-es im - Da**"g=ee.'n A e,ngn d ="end*** *****'t'p'oetas eues

  • RiaAnayees-a ade F W.R M N ut - -

ig, e e e games s,, .seds, mas, - e,s.e.. e coese, - - n, "w"n e has ere.pe be-d sa -hem-moy here enchasces hiput freni chek.Sesid. e LAeestasy progsom se ,ee,,he,,es ene. t One NRC %,, _se T, hem,,e,seddent.,We s,eedF fus,ie.esAhen.ee oseey nom. Re e.e w emesse setoeve se seesweep and nok seemeer eene ser she. sessiger DHRS dougn eheressoresses to the pienes po.o. green sunmeng snuse to appeeme.d.a.nd.a.tteenad. ,,es, doce,,,, ,e,,,e,, es,dd . opere n. ee e en eneh. e e -O sen.ng e,e.e.,,,,, m em. hoes espe,sey. dose wet a eo m -wm a==1== e.r edinwAsimoo nssmAr,.ndinte. h e ^ ~ p e,d pees,,ese, o.a ,,p, de-a de ey hea - W ~ ' ^ W e, ","g** ,y,,w, ,,,,,,,,,,,,,,,g, Wieeso.ra s.ayishee.sey'eedese e e euwes eesk to 9to pista. m, moy 10,1932 yeg Sea.i. i.,= =. d. n.e .e ,me. sfe Co Te Am. -w ,,,,,gg,,,,,,,g_- g__ , em, se _ _ - owesell prepost ^ seehnmaldirection eswes engeene seestme, and eesh essen, no e (pgN A1315) to prookie _ % n,,e e g - e,,,,,, ,,,,,,,,,,,,,,,,,e,e,,,e.,o,,,e,,,,g,,,, ,,og,,, he PWR pimisk hichadong him not Ibsened to _ ' _ woe,e posseita thee M decoy home. _ on,de yo,ge,evenne and.emos LOCAs. Tiens we ease in-and lassayeesse.for the antase Teek A4,,proyent eien.ce. en w isese ns ees.oe.,ethe,s,. _ - - - e -- -- and wh r usens semang meng en3, e., _ he ee ed.emed g des - no .e need and resehee dempt eyesene em beseg weses --. (WWIIe) enesene ene ennesewed desey heet - tweemsne [g 7, -- g, e Seemy teene we.she.somesmaaeyw d==ynam - een e es ..nwyes. .ppen ,se e,, end - Casee, _ _ end e _. nessed westen - m esed.^ si..Bf.RR and RES NRR nee w. The e., web passpoos o.f Tenk 44 to to suedu.ete Gio adegame.y of ^ - usesor ' esed esehsent - ' ..aspeanen e,=se.en.d.to w-e, p=n. he.

a. - pas,

.i, ev or to.ie.-e e,e _ _ dos ,n.__ rRA - seeaae emedy - -- e.ns.ee, n mAsees,e.,ie.e.eedee.e ,heet m e we. - Ten

  • es ehmen operouw of ennene by HRR and.e ed. des,,e es e Seneer Cenesee Rewcom Seerd hos been gressor then dysetes a __ _ -

mes sonmeense see of ofmande=== esoEns e=ead ** **** ===*e the we= s-n--vt eagswe stones ter esseong and.heure LWR.e, techseng Wie stedy of -, ee do.e, .e is. and se _ e e. -~ e e,e- *= +e mso-*w

n. ees,ee.

en ,eme- -

  • STATUS

SUMMARY

- Do mp.e=

  • en== se >dse e==baar w d==v he ev.u-o no een.m.

h ene p=.n The teek nionsger mes essessed to ese,ch tm and e . Dovetepenene of sieaiee for :. ' me DMfl sysessek 4,en Task Acmen Peen ese puheehoe en Idey 2R.131. - ^ of eelselng pienee so adoneffy Wiese to whleh DHft geoed on husented see t end ACRS Revestem s eegebe-O es TAP A e wee spesewed en Ossetor 7.1531. - Deveispment of a paese ter -. ", near esgubessents W The Dheetor of Seap d sees oppseue she seemeseed e wee eny. for DMIt eysensne seedred es meet the esseptonee

  • ACRS INTERFACE INFORMATION HN NO. CONTRACTOR OBLICATED EXPENDED sune.ns oves se.r tse.t A m esc.h=ce.so a.es

=e.. Mi. end -nOur es ieced on The m"e r.wie..d,*a. m.mng w.e w

  • =ene

- Teek Imenager tde8ed the luE-en Jisly gnB UCLA 6 10 GW 9 10 GW Wedeus epsons were _. - see1eek A 46 eecos of ^ esepe. Sunang and _ _ g, %,,,h,,,g,ogi,ge,,,,,,g, S.13t en she poement phes and sensene of the A331 gegt g Egg egg g 133.333 whites hacended -opeen umee._ ^ by The A4Teek ActonPheITAPL $ 41M Senae Stel.M 91.10BM eme A. pe,eeser og psRA as pet 132. A enchass.af. - ACRS

  • em Desey Meet Resteued Syew sesne IDHfeSt asise en _^

27.1ML an.d Teek

  • IeneIndse.e ten,seslag Sundne which hoe been Re see,d en Ap e app,oved e, the Sensee Caserect poetego we d S. isnt and _

.mai asene,w 3.evedad se _ we en medoes es ei pene - - the Centracter (Sendelen eAey 10.15m Howesten 1 ef el sho A4 p,eyese. gggg gigg TAP A 45 consentene enh the ebewe eteene eues tetoed - pershoe meestnee weeti che fue _ and ener OfefeL $338.05B en June 2. M en DMRS we be heed se the wed en A4

  1. The esseend aneeste eineseene,soport en cessoang of a

peorensee ased eartem pre _- missese. nee e,e twR$ ese sweauseen w Does nees Re-eves Cee, ms hy" wee lemmed he d.e s fasen for esRC eneN soweeu en e bessett 2s. MB Recutese 2 es TAP A4 hee been ^end to heeng ^ by enmA 3 8 INDICATES A CHANGE IN INFORMAftON

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SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS (A-45)(CONTINUED) PRELIMINARY NETWORK s= 7r.. T' ~~===.: = ss=n

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I i 1 l SEISMIC QUALIFICATION OF EQUIPMENT lN OPERATING PLANTS (A-46) l ,s oP we,x suo,,o . AT,.,,, Priviaocuem caAtto' SCHEDULED COMPLETION l KEY PERSONNEL TASK REVIEWERS TASK MANAGER NAME BRANCH i '8' I T. Y. CHANG X27dSB ORIGINAL JEflRY JACKSON EOS/DE pg 04 N48 C REffMETH HEflIIIGNG SEPS/DL CURRENT l MPA ANALYST of0HM MX PSSCSI 3.5T. MARY M28330

  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION
  • TECHNICAL ASSISTANCE CONTRACTS
  • POTENTIAL PROBLEMS IhEL h wee kwe Yeek 3 They sow e _.
ewk
  1. The s0U0 as to che posees of ferimiene on^

gen e soon tc novi net fSsnp 44 mes esprosed as a USf by the Nec nas has passed e eenwart weeh Sevesseen Reneersh Inommee to suveey esemas eushfseteen abrary assech end sesnecese east teboresones een sesseng e,e es,ew.ew pe.see,,,,t so pend,e seen se I eseneng an one eueencemen of eeuemmene a dreet es,s. se,,,,,,,,,, The doesyi eresario este sutethods for the essenese 'se*'s mee deemed de Decenter egEl atone suece the eeuway uses to en -.. etenwee he ( and e ecerseef esempseent fash 4 se wee es un she oweres peepocs scheduas huisses s I gesehteesseen of esi use A as aw, eseu e. Tens pee nw assisess ao eise. s sensase Queencemen Umanes o.eup tsoues has ces. est neeleer power plantes haue emdergene anywfocent, change asuems the seeres of she _ _ _ ? necess Inded e esyntuose oniouse of deae en eemsymons in vessely being ^ by the stoft. l -nouser p=n= wh ch he o unde-ear *. sty, ehe maryns o,.f safety pesuer propam. f se see,se so.s een, euskee. suutdor doen ese. _ he nucleos pienes ,ee.eded m ee.g.ng enshened leads ered perfersus the entended selety has ease been essesesse A espeet en the steufe of The sesenus due pese peereen was deemed at seposanter tm funetoons niey very _ - ..ise operateseg plang LLaH et a pere of Tesh e. m _ ie fosseety W geselefeesteese of the es tresig the plant to e este easednesen wheat 6tnet esport to be, geseedicemen A sueuse, therefore, he to essenere the skelety et omeng these does per _' by LLfft, de _ subsect to e seesssess event. The ensecteve of thes ^ west en ^ _ _ Unreneeved Sofety lesess is se eseshhsh an empseest est E'8L 8'8e - _ es he gesellfeed en of _ ~ thet eewed he used se pedge Wie .. es esteet. _ ^ _ es the essessise guehfeceesen of. e evpeces pWym and a typeset gwn a dreft sopore en and clostrecal ogueesstent se eN operetwee plants en the empie was leeued en ^ tW gett has hoe of setempeeeng to backfet sesroent doespe ease s-e sneses poen se of shop wem en ^ ^ erseeres for new paang This _ - won eeneers, dwe8ep#'s gene'ee meer. _ epeewe pion egenesment segesered to setely shuteioen the paene, 'se*st en shes septe emes ineued en _-. ten as neu as egissponent euhese fenceeen es not _. for esfe _^ _ best geheng fashste seestd steelt ese adverse eendimens whech snight tesepeer _^ feasteens. Albe, emphet geside4enes sten he usteldeshed for ese set. _ - ".seng. equepsutent whete sessense qualeficatiest eyes teased to be ^ ep. A, , treakdoene of the tesle e se feHome: n.evelop Besse for E. D to Tash 9 oes shed S'",,,o'g '*"*"""8 0"dd=""" . ACRS INTERFACE INFORMATION AN NO. CONTRACTOR 08UGATED EkPENDED

  • STATUS

SUMMARY

T=*8 Teek 3 Deve6ep asenheds See I*Estu Quehhseeme A prenminary Teek Acmen Plan swes - _ ^ se the A0423 LLNL og5K SME lose p

  1. we4 en se seekele

^ by We eme-bean.g shot fe. saap h 4.sueet be delayed tesesse_ m.e e - e of Egerapneens anOperosene planto ACns. The etsff piene se meet with the ACRS et = = $ao . i.sous rh. -e appropriate ameo is preseni me e==. of preeres. ' _ have e teeseng en she owesee Use A 45 vesh d see,,,,e ou,,,,e,,en e..,,,e,,,,,,,, A33e7 SNL ems steen gee 3 Uenig fe.estfeucteer piene Dynonne m e. pen - De.eiep ouednes.,ee f. ommef.etion Teek e acapense specer Took 8 Docusions Reenfes of Task A 44 esed Propere e Fenal NUPEG JJ 8 INDICATES A CHANGE IN INFORMATIOff

l 1 SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS (A-46) y W W Ca.s.t./Se..efe m.et a.,i= e-0 -1482 UWhose A .e e. 5 06 82C PEAP Defme """"W fm Set Wi" Task 1: ___.s 0616427Ces.pwee. seas need userosme P*essse UEM

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== e. @',* 'L'32" "l:'4 '".*.*.*"'-' *. _:$ 4 3) .e._,,,_. " To to seasheduend et e apeor does. O

i l SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS (A-46) i Continued l iE2iE. :*:'?

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SAFETY IMPLICATIONS OF CONTROL SYSTEMS (A-47) ,, o g,,,,,,,,,,

  • o'^*

"8" SCHEDULED COMPLETION KEY PERSONNEL TASK REVIEWERS

  • *"'"*"^'

TASK MANAGER NAME BRANCH m as ^"0""' S n m czsesse e s ORIGINAL o.SASDEKAS OFO/RES W. KENNEDY PTAS/DNFS M g sesanS CURRENT MP'A'AN DST E.CHELLIAH RRAS/DET 3.ST.L^b7.

  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION
  • TECHNICAL ASSISTANCE CONTRACTS
  • POTENTIAL PROBLEMS Dwing the west of Jedy 23,1895

"_e Obenan. , opereene espertonee infe**neden w k tesEL. EGGG pdehe Feast. Seesses leer.nese head en foonSetofy Caseeral Svetesses for the Steacteer Teek A47 neo approved se a US$ by the NftC in Close seerdinetten wW be seguired on Test A47 be6 ee woo D'**"'h"' 188E ween Nan and RES. RES. ~' wie be esembed from she Divesten of Fecanetse Operamens and the end Leumeence r Lehe ser the. _ er em Steem Syeeene INSS4 and the Botence of Peent(DOPl Thee lueue eenoorne the peessettel for eseldente er Dewielen of Steet Anosyslet The Dowleton of Feclaues eussing she A 47 entscehee and to assoas the eype of _ heeng emede essee sevese a e semede of sentef Opseestone meII prevede inpese fresse their eeeensch pro soevouss enes eesid hese he "by sheseep funst6esis eney esaur- , or a e resuN of the <eente leurrency being doveteped Ise _ ;.tesse wish sesene. Gemener _ weeh OENsL and Sendio Lehe Obsein , design hefernseelen (Lo ochemodse These fuehwee er snes. myseene fedures er essest _ ^ seeldeses er.. ^ eender _ _. _ _ end eseald be 47F en sensef eyseene 1_ _ _ The Ofwloise of were held Jedy 9.131. A Teetwesse ^ IT A.8 and eyeessne descripetonal fee the geo*Sofety Censul to edenen to any esseeres evenom feehere shee sney heen Resis Anesysis unde provede bout on their eerrent em eeneest adah OfMIL GFNs 34eEM wee esenhashed Syeeune sleeigne for the NSS and she SOP doelene. 4mnasted the esesuL Afeheu$s te en genereNy hehewed OnesL eeegresse l'E _ ^ " er Pressurtood shseech senstistes. ntS su eendmos e se iew ee sim. Shock'l. OWier vesseMA ordwides are being dipsesse eypse of PWet desigse tono gets peesst. TredlSestegy - ewere sent regesbed to prewide West esseerst sygeesse Gesiuses are sees New4y to seessN IIe eve 8umeed es doennestne their signdheense to A47 and Osenee. and eno CE stone. Cohere Conos. esed per. desigse er speseelseg _. ' _ ese fees >Sofety Gees of sessey henseems estoste somed good es seresse Genn she eeemesses teeneNied in Teeks 1. 2. 3 and e of Syeesssee and therstere site 1_^ esisy be dif-esence er voeuN en eeneterse that sofwey systems are not estoy be IdengRed leger. Teek Aseen Penn A47. A seeareas T.A. _ _ en fecuft te obeelst shes es seps wech. endepen ecueen heve not been per. perferne the seutow en ewie SWR eype eenign, geouwse Gersumed to support thee belief. The poesnt6el Ger en fewy. and one PWII spee doetsse.^^ f ^ gg 3. eastdant that ausged eftsst e - ^ eentel system. w uhIIstL.GFles Aegyn. and stes oftsses of the emneret eye.sene 9estu.see e eeS Ti.e.echs ee ' ^ o Ohw - w posse.ne Thes es = i na meie sese-en. eisu .e.n..em p e.. pen.sei..ses h.,eenshee e de.ney .s -se.e.r . best redner pient.epoestte seasous edS t E stem cas.es S ese-. - = Wams he so.ese.,e donn.e.one.rnene.u.sessen.ed Samy Th - se. e smen een-== =wn neon. O.-an ed. issus is ene, no essed Transione for ytenegoessfie reviewe. A spoorhe euhesek of this 7.n*as."e '"i..e.n"eT.s,d..i."e"" Osee.O.or 8 e*,,",e", Q'"*",j"' ' ' * " ' ' ' '" "e e .se.o to. orn s.d e ne 1 Essesses (Au Othemel Cenerel Spesem Astlose psevenesse usedfor sueelgoesus doelpe seemuses se That Here So sey - " e thg : Ces. eses Efsene of Lee of Po-or en see Evan m Systems

  • ACRS INTERFACE INFORMATION HN NO. CONTRACTOR OSUGATED EXPENDED

= STATUS

SUMMARY

,A4en

== ease.s3 enname A sh hoe been esasaeA An asese.ed ihm g 7,,, se,,,,,,,,,,*"e,Eg h*""'"'

== -m see m.ne,s eessdy. - ef e., A enort esder uses pleoed wede usEL thesy 1 tgan to 8'8- -*'t en e pont peine sevenue. esedes ggesmeses of _. Teek AstonPlanunweeseessedwage 8' saniedseen et she eeneet ACRSen054749. -. -. en some'PerII-sype pienee se Omas( end e geva eype peone se NeEL to essedesesey Discue of Wee setsweelse idensIned ase TAP A47 enes diesesseed week she ACR$ T - en The - _ - Pwet deshen semese et18eELwas Decenator 2L EM esorted Feheuery 1. tm M 8 INDICATES A CHANGE ne INFORMATION

h $l ?, $l !($) !9 yg g e,. f!kh ws bh a(), 9, h' g y ,I'I 1'!)' 'J;j J;j M i h> !h2 t , jf I.!il e Il y jlF l !P--- - !@ g ,97 - 1g.1i I >';92 o yn .,,j n!I1 !97--- !@ !qp, g I, ' 11, m r 3' jI,i -llj'i Jllil Jl. 9 !!1111 !!j!1 j!9? Q ,::::7- ,ll. n o l l!92 3 h l II W_i , lj,' l i ~ l u5 -~l $h I!.>I'}\\ e 2' I l .l.: w lhY n' e a-l!} ,,j Il ldl! dl !!??

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CE-PWR SAFETY IMPLICATIONS OF CONTROL SYSTEMS (A-47) l PLANT REVIEW Cont.inued (CALVERT CLIFFS) I

  • NOT SCHEDULED (N/S! OATES I

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HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS ON SAFETY EQUIPMENT (A-48) AS Or wEEx ENDiNG A< zr. - KEY PERSONNEL TASK REVIEWERS xRv$rTOr PARcztiv$x1 ce s/Dr/NRa SCHEDULED COMPLETION TASK MANAGER ,,N,AME N n,cw ARD CLEVE LAND RSC/ DST /NRR mmumsu xxxTr a vtR=oN Roonn DL/N"" ORIGINAL ew ARtrS TiNuts R csB/DSI/NRR JOHN L ARKINS SAS/DAT/RES JOHN LONo R$a/DSI/NRR MARTEN FLEISMAN R A8/DR A/RE S CURRENT wux Au c arc r Op rDE /NR R

  1. HAROLD POLK SoESIDElesRR O.sT.uARv xane

= PROBLEM DESCRIPTION

  • RES INTERFACE INFORMATION

. TECHNICAL ASSISTANCE CONTRACTS

  • POTENTIAL PROBLEMS

^enemme sewe.d es the TO BE DEVILOPED h mes meme hee Teek.mber 1980.A de wee opereeed as e USI by me NRC in Th.ese e.m Dee hp eg n tenue . by RSS The esenho of Theretee. chem se e _ ^ Get new An$ngs resewiated seester seeadense wheek soeuit en a she.e ^ progr.mo ese he - _ ines eeush may aunpose she eussene ese.eduse ^ The mesment schedub wee * ^ The h. ..o e n e. sees - e.en.e.en she he.e of see t een t.rg g.sene esare.es. ef the. feet eseddu.g unch eteen. ekseye ese ~.- as h.gh . and/ee by e ' _ _ of weger. Esener. ens. g.med seess ghe TMI 2 ess.ess.as.

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SUMMARY

To et Devt(DetD vs.e v.oh are a cieniva .e.,s e.ed en um.t.nd. eee d - e ew dove seed se. hewn en the Gesen.pg pegee s

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  • i=Decates a cnAmoa im e=*onwariose

HYDROGEN CONTROL MEASURES & EFFECTS OF HYDROGEN BURNS ON SAFETY EQUIPMENT (A-48) = .- _o

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I i HYDROGEN CONTROL MEASURES & EFFECTS OF HYDROGEN BURNS ON SAFETY EQUIPMENT (A-48) Continued l

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l l i 1 l l l l \\ PRESSURIZED THERMAL SHOCK (A-49) ,s og,,,x,,o,,o mA, .,,s, KEY PERSONNEL TASK REVIEWERS n seasoa omos? SCHEDULED COMPLETION N BRA" " TASK MANAGER sa es i nov =*os m2*m = nAmoAn uTtsee ORIGINAL o visswoo one AoL 'C""*"* a J. sTnasmoEn us CURRENT MPA ANALYST P.uTTom cisiost " *^o'"s us a sT.uAny -- a PROBLEM DESCRIPTION

  • RES INTERFACE INFORMATION eTECHNICAL ASSISTANCE CONTRACTS e POTENTIAL PROBLEMS This seen.es.se e.e. e use by me anc =

An,e,, - e.,,,e.e,.. -en e, e , Coneese. .,,,e..e,,. so .e liteatreet bredeelen of reester pressurg wesee6 oueid

  1. senegh she Devenien e4 Ihek Ameevels. Etts IFIIe # gem seek __

eseneses se to oposed er poem eseeme PTS Desernher 1901. sen een si,gge senesemos. - perheus _ . seemse somg the VtEA and plate sweeter 6els ____ the frece e eeughnese sensel 9mehsse needse ese se PT5 sede, and

  • of the snoterdees. The freemre spieghnees _

es reeseen heduced change is 1_. ^ hy presence Other sneier emnatiseers era The seneseems Es. _ ese seemedens techmesol n of certain me,wrtede nasch se cooper C-e,ee,n,,e on,6mes,, gn, eeerch, Pregnene . o,,,s,e,,,,e pts proyee. These e m, Prinnery syseene Insegrey ne , th n,es .e wechsre _ _ menn a more ukey

      • "o ***u*emas mne secure same ese. w e nes,en yeennese,,

e by er us and sweetes se speeweep, semese so pts esse end heind [ C. ode Appeceeens Program through she civision .ech 3e - me vene.et.es.r e re.,en.ee m e - - ms e eise ees., os.r,e,en hmeerny. e est Seves preneurised e,._eence may ogiere'nudupee seawee and - evenes are es133 Lwn p.em seeneer, enemena, 1. esses sen emeneeoes sm, improper opereeer,. "_

-___. eeresin precureer events heve :... -^ thee noeis reame.e venees s.neensee.

Pourmany messeened -se inmern, sound have d emessenes se224 poemen, bassa caes see tenwes m.e.d eeensreed eneer u ehe ve.nees had b,ee.n A3115 Code" -and A mer. hl, hremmed. Theresers e pene an e s7o2e m Co weseel fedure dise se e severe presonertaed ""'**"""**'**a-Ases7 Co.e- -en. AE . STATUS

SUMMARY

A7027 Ametyeres nem en Lwn safee, WAC sen PT.s.- . IseCTstesse e A7297 inAC Cels Asessiones sesse se b. mDesesAe,i=> Aso. 39408 Pressuresed Thorsnee gioch sees see PTS as beene messed one w. he

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  • ACRS INTERFACE INFORMATION FIN NO. CONTRACTOR 08uGATED EXPENDED s A e ee ease e.ee no.e.e.-een one.se.se e.m n

an==e hoe noen hee end.m he =hesehe m ,. = = P. amo. m ee 136 ISECT 3 m The genes senese nesseory.seh the " - en hingelbe

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  2. The Pts psegsaan has been eueded ines etue pesen. e
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-es e pts mese ens pueesseen. e teng esse progsom,-Consinneen,e seguemene Cheses to C.oneesen se.e Seek Deftnsetens aut the A S Test Acela PlesL* The snel feek Aeglen Plan for A4 eues appsowed end teamed on enesch X Inst

  1. Restolen 9 af the TAP.es eene se the Deerser of WAR Ger oppsomel 4 S e sNotCATis A CHANGE IN INFORMATION 40

PRESSURIZED THERMAL SHOCK (A-49) SHORTTERM PROGRAM TASK A: Review of informaten requested same - mac mac a T. 2e % -"- G) =-M9---G '--4 V selected utihtes "* ** Yme. n-TASK B-O igation of a new SEES - *~ V' j o 0 0 ' * = ' "

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  • PTS Rule also requires consideration of flux reducten option for all PWRS. This Teek (C) le euch conaderation in the immediate future to prevent preclusion of this option for the oldest (leed) plants.

41 i I e L Nc. (

-t PRESSURIZED THERMAL SHOCK (A-49) LONG TERM PROGRAM Task 1: Development of a Revised Regulatory Guide 1.99 Draft revision of the trend curves in Reg. Guide 1.99, Revision 1, ** Effects of Residual Elements on Predicted Radia-tion Damage to Reactor vessel Materials": This task is no longer considered to be necessary for completion of A 43. Its scheduled completion is a longer term item than A49, and adequate guidance regardmg this subject is contained within Task (bl. A detsiiod schedule for this task is therefore not presented. Task 2: Ongoing Program to improve Procedures and Operator Training This progrerm is ongomo separate from the A49 PTS effort and is much broader than PTS, consulenng PTS as one of the many types of incidents for which procedures and training should be impro sd, on a combined / integrated basis. Generic Letter 82-33 contains a description of the overaN program and schedule. The PTS effort cannot and should not be separated from the overaN effort, and so a detailed PTS schedule is not presented here. The ongomo program will be completed and appEed to each plant, however, on a schedule compatible with w,eb, of the final PTS resolution for each plant (i.e., before acceptance of plant specific analyses required by the PTS rule, Task (b) above.)

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l l l l ) l f,",y f cau s35 u s NUCLE AR REcuL Afony comussioN ' "' '0" ' " **' " " "' *" #### BIBLIOGRAPHIC DATA SHEET NUREG-0606. Vol. 5. No. 2 4 TIT LE AND $USTiT LE dase rsbene ke, ef apPespe we 2 4*w o eSa # Unresolved Safety Issues Susanary (Aqua Book) 3 REciPiENi s Accession No T.AUTHOnlB)

5. DATE REPORT COMett TED lvtam esose TM l-

.kne 1 ont S PERFORMING ORGANI2ATION NAME AND MAILING ADDRESS #acb8 le Cedr# DATE REPORT r15UED l Office of Resource Management "E l y3" j Management Information Branch U. S. Nuclear Regulatory Commisssion 8""**" Washington, D.C. 20555 e awe areas

12. $PONSonaNG ORGAN 12ATION NAME AND MalLING ADDRESS #acb8 le C**J 10 PROACT TA50nORK UNIT NO Cffice of Resoruce Management Management Information Branch is contract No U. S. Nuclear Regulatory Consnission Washington, D.C.

20555 13 TYPE OF REPORT et mico cova na D #4ebs ve eewst February 19.1983 - May 27.1983 15 $UPPLE A*ErdT ARY NO7ES 3 4 A '" * ** 8 IE Ag51R ACT OOD wows o* drasi Provide an overview of the status of the progress and plans for resolution of the generic tasks addressing " Unresolved Safety Issues" as reported to Congress. ) 1 I 17 EE v WORDS AND DOCUMENT Analysis 37a DESCRiPTORS I l l 5 70 4DENTip IE RS OPE N E NDE D TE RMS IS AV AiLAtitiTV ST ATEL'ENT IS C UR 87 7 LASStre.sveese 21 ND 08 P A TJ S CI* II'd Unlimited ic gT,vggr.e.m n Pa.cf ' '.s. -RiRm,.= R,.,,,,,,.. ,,,,n,

,",",f, ' '*" 335 u s NuctE AR Recut ArORv CouvessioN BIBLIOGRAPHIC DATA SHEET NUREG-0606, Vol. 5 No. 2 4 sittE AND sussstel Aeove,awne.,o w ere.no 2 newness Unresolved Safety Issues Summary M a 8ook) 3 RECsPiENT'5 ACCESSs0N NO

7. AUTHOR 153
s. DATE REPORT COMPLE Tf D esameTee l YEAR June 1 ant 9 PE RFORMsNG ORGANi2AitON N Anet AND M AIUNG ADDRE$s Aache le Coms OATE REPORT f$$utD Office of Resource Management u3vn l1983 v

vaam e Management Information Branch U. S. Nuclear Regulatory Commisssion Washington, D.C. 20555 , a,..,,,,,,

12. SPONSORING ORGANA 2ATION NAMF AND MAILING ADDRESS # ache le comi Office of Resoruce Management Management Information Branch ti coNTRAcv No U. 5. Nuclear Regulatory Commission Washington, D.C.

20555 is tvPE Os REPORT ,ee mion covt ato eace se February 19.1983 - May 27,1983 15 5UPPLEUENT ARY NOTE 5 14 d e*** * ** # SE A851R A;T 000 =e-es er mas Provide an overview of the status of the progress and plans for resolution of the generic tasks addressing " Unresolved Safety Issues" as reported to Congress.

17. RE v WORDS AND DOCUMENT ANAtysis 17e DESCRIPTOsts I?e DE NTIFit R$ OPE N E NDE D TE RMS is Avait Asiutv si ATEutNT is y Cumerv ctAss are =eem si No os Pc.Es unclassified Unlimited to g T,v, g r se.
ea.CE

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