ML20080K165
| ML20080K165 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1983 |
| From: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| To: | |
| References | |
| NUREG-0606, NUREG-0606-V05-N03, NUREG-606, NUREG-606-V5-N3, NUDOCS 8309280589 | |
| Download: ML20080K165 (50) | |
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r NUREG-0606 Vol. 5, No. 3 August 19,1983 UNRESOLVED SAFETY ISSUES SUMM.",RY i
i AQUA BOOK
$UNNE'$,bb'53 Prepared for: 0FFICE OF RESOURCE MANAGEMENT
[.s.$N ufssion I
WASHlHGTON, DA 20555
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4
FOREWORD THE ' UNRESOLVED SAFETY ISSUE 5"
SUMMARY
15 DESIGNED TO PROVICE THE MANAGEMENT OF THE NUCLEAR REGULATORY COMMISSION W!iH A QUARIERLY OVERVIEW OF THE PROGRESS AND PLANS FOR COMPLETION OF GENERIC T ASKS ADDRE551NG " UNRESOLVED SAFETY 155UES" REPORIED TO CONGRES5 PUR5UANT TO SECTION 210 0F THE ENERGY REORGANIZATION ACT OF 1974 AS AMENDED.
THIS
SUMMARY
Ui!LI2E5 DATA COLLECTED FROM THE OFFICE OF NUCLEAR REACTOR REGULATION. OFFICE OF MUCLEAR REGULAIORY RESEARCH.
AMD THE MATIONAL L ABORATORIES AND 15 PREP ARED BY THE OFFICE OF RESOURCE MANAGEMENT.
THE DEFINITION OF WHAT CONST!iUTES COMPLEi10N OF AN UNRESOLVED SAFETY ISSUE (U5!! HAS RECENTLY BEEN EXPAMDED TO INCLUDE THE IMPLEMENTATION OF THE TECHNICAL RE50Lui10N. THIS IS IN ACKNOW-LEDGEMENT OF THE FACT THAT REAL SAFETY BENEFli5 OCCUR ONLY AFTER THE IMPLEMENTAi!ON HA5 TAKEN PLACE. IMPORTANT ELEMENTS GF THIS IMPLEMENTATION PHASE ARES THE PROVISION OF A PUBLIC COMMFNT PERIOD FOLLOWING THE ISSUANCE OF A DRAFT MUREG 1.
REPORT IMCORPORATING THE STAFF'S TECHNICAL RESOLUTION FOLLOWED BY A DISCUSSION AND D15P051110N OF THE COMMENTS RECElvED IN A FINAL MUREG REPORT.
THE PROVISION FOR INCORPORATION OF THE TECHNICAL RESOLUTION INTO THE NRC'S REGULATIONS.
2.
STANDARD REVIEW PLAN. REGULATORY GUIDES. OR OTHER NRC OFFICIAL GUIDANCE OR REQUIREMENIS AS APPROPRIATE.
THE PROVISION FOR APPLICATION OF THE TECHNICAL RESOLUTION TO INDIVIDUAL OPERATING PLANTS 3.
IN THE FORM OF HARDWARE OR DESIGM CHANGES. TECHNICAL SPECIFICA110N CHANGE. AMD/OR CHANGE TO OPERATIMG PROCEDURES A5 APPROPRIATE.
INCLUDE A MILESTONE AT THE EMD OF EACH ACTION PLAN WHICH REPRESENTS THE SCHEDULES IN THIS BOOK OF THE TECHNICAL THE IMITIAi!ON OF THE IMPLEMENTATION PROCESS BOTH WITH RESPECT TO INCORPORATION RESOLUTION IN THE NRC OFFICIAL GUIDANCE OR NEGUIREPENTS AND ALSO THE APPLICATION OF CHANGE 5 TO INDIVIDUAL OPERATING PLANTS. THE SCHEDULE FOR IMPLEMENT ATION WILL NOI NORMALLY BE INCLUDED IN THE TA5K ACTION PLAN (5) FOR THE RESOLUTIOh DF A U51 51NCE THE MATURE AND EXTENT OF THE ACTIVITIES MECESS ARY TO ACCOMPLI $N THE IMPLEMENT ATION CAMMOT MORMALLY BE REASONASLY 'ritRMINEO PRIOR TO THE DETERMINATION OF A TECHNICAL RESOLUTION. THE PROGRESS AND STATUS FOR IMPS *ENTATION OF UNRESOLVED SAFETY 155UES FOR WHICH A TECHNICAL RE50Lui10N HAS BEEN COMPLETED ARE REPOR1LD SPECIFICALLY IN A SEPARATE TABLE PROVIDED IN THIS
SUMMARY
RARL RMIEL. CHIEF OF THE GENERIC ISSUES BRANCH. DIVISION OF SAFETY TECHM3 LOGY /NRR. 15 RESPONSIBLE FOR MANAGING THE GENERIC TASKS INCLUDED IN THIS SUfTtARY.
t 5
TABLE OF CONTENTS PACE NO.
TASK NO.
TASK MnMACER DESCRIPff0N 1-2 ABBREVIATIONS 3-5 OVERVIEW USI'$ FOR WHICH TECHNICAL RESOLUTION IS COMPLETE 6-9 10-12 A-1 ALECK SEREIZ WATER HAMMER 13-14 A-3. A-4, A-S JACK STROSHIDER W. CE, AND 88W STEAM GENERATOR TUBE INTEGRITY 15-96 A-12 RICHARD JOHNSON FRACTURE TOUGHNESS OF STEAM GENERATOR AND REACTOR COOLANT PUMP SUPPORTS 17 A-17 FRANK COFFMAN SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS 98-21 A-40 SYED SHAUKAT SEISMIC DESIGN CRITERIA-SHORT TERM PROGRAM 22-23 A-43 ALECK SERK!Z CONTAINMENT EMERGENCY SUMP PERFORMANCE j
24-25 A-44 ALAN RUBIN STATION BLACKOUT 26-28 A-45 ANDREW MARCHESE SHufDOWN DECAY HEAT REMOVAL REQUIREMENTS 29-32 A-46 T.Y. CHANG SEISMIC QUALIFICAi!0N OF EQUIPMENT IN OPERATING PLANTS l
33-37 A-47 ANDREW SZUKIEWICZ SAFETY IMPLICATIONS OF CONTROL SYSTEMS l
{
38-40 A-48 TSUNO SU HYDROGEN CONTROL MEASURES AND EFFECTS OF NYDROGEN BURNS ON SAFETY EQUIPMENT 41-46 A-49 ROY WOODS PRESSURIZED THERMAL SHOCK
ABBREVIATIONS AABs Accident Analysis Branch (Former NRR tranch)
EEBs Environmental Fngineering Branch Divisten Als Administration Branch. Training and of Engineering (MRR)
Administration Staff (IE)
EFPYs Effective Full-Power Years ACs Alternating Current EG8G8 Edgerton. Germeshausen B Grier ACRS:
Advisory Committom en Reactor Safeguards EPs Emergency Preparedness AD8 Assistant Director EPRIs Electric Power Research Institute ADB Analysis and Development Branch. Division of EGB:
Equipment Qualification Branch. Divielen Reactor Safety Research (RES) of Engineering (NRR)
AEBs Accident Evaluation Branch Division of FIN 8 Financial Systems Integration (NRR)
FSTFs Fult-Scale Test Facitlty AE00:
Office of the Analysis and Evaluation of FWa Feedwater Fys Fiscal Year Operational Data Geosciences Branch. Division of Engineering (MRR3 AIFs Atomic Industrial Forum GSBs GE:
General Electric APTSs Action Plan Tracking System ARL8 Alden Research Laboratory GIBS Generic Iseums Branch. Division of Safety ASBs Auntilary Systems Branch. Division of Technology (NRR)
Systems Integration (NRR)
NFEBs Human Factors Engineering Branch Division of Health. Siting and Waste Mont. (RES)
ASPE:
American Society of Mechanical Engineers ASTMs American Society of Testing Materials NSSTs Heavy Section Steel Technology ICBRs Instrumentation and Control Branch, ATWSs Anticipated Transient Without Scram Division of Facility Operations (RES)
B4Ws Babcock and Wilcon Company BNCs Brookhaven National Conservatory IC9Bs Instrumentation and Control Systems Branch.
Division of Systems Integration (NRR)
BNL8 Brookhaven National Laboratory 30Ps Balance of Plant IEs Of fice of Inspection and Enforcement IEEE:
Institute of Electrical and Electronics Engineers BWRs Bolling Water Reactor CE:
Combustion Engineering. Incorporated INELs Idaho Nuclear Engineering Laboratory CES:
Chemical Engineering Branch Division of IPs Indian Point IREPs Integrated Reliability Evaluation Program Enoineering (NRR)
CFRs Code of Federal Regalations ISIS In-Service Inspection cps Construction Permit LANL8 Los Alanos National Laboratory CPts Core Performance Branch. Diviolon of LER:
Licensee Event Report Systees Integration (MRR)
L1NLs Lawrence Livermore National Laboratory CRs Contractor Report LOCAs Lose-of-Coolant Accident CRGR8 Committee to Review Generic Requirements LPPs Lead Plant Program CSBs containment Systems Branch. Divisian of LTPs Long Term Program LWR 8 Light-Water Reactor Systems Integration (NRR)
MARK 1-IIIs Containment Types for Belling Water Reactors DCs Direct Current des Division of Engineering (NRR)
MEBs Mechanical Engineering Branch.
Division of Engineering (MRR)
DEDRO3Rs Deputy Executive Director for Regional MEBR:
Materials Engineering sranch.
Operations and Generic Requirements Division of Engineersng Technologw (RES)
DFOs Division of Facility Operations (RES)
Massachusetts Institute of Technology DHFSs Division of Human Factors Safety (NRR)
MITs MSLBs Main Steam Line Break DHR$8 Decay Heat Removal Systems MTEBs Materlats Engineering Branch Divlslen DLs Division of Licensing (NRR) of Engineering (MAR)
DOEs U. S. Department of Energy DOR:
Division of Operating Reactors MDEs Non-Destructive Examinatl6n (Former NRR Division)
NRC Muclear Regulatory Commission DRAs Division of Risk Analysis (RES)
HREPs Neutron Resonance Escape Probability DSIs Division of Systems Integration (NRR)
HR P. s Office of Nuclear Reactor Regulation NSS:
Nuclear Steam System DS$s Division of Systems Saf ety (Former NRR Division)
HUREGs Nuclear Regulatory Report (prepared in-house)
DSTs Division of Safety Technology (NRR)
En Engineering EBs Enforcement Branch. Enforcement and Investigations Staff (IE)
ECCs Emergency Core Cooling 1
PROGRAM CVERVIE"1 PROJECTED DATES FOR ISSUING NRC STAFF REPORTS Key 1 N/5 - Not Scheduled USI May 27. t?83 E2.
TITLE AQUA BOOK CUPRENT REMARK 5 A-1. Water Hammer December 30. 1983 December 30. 1983 The staff's technical findings are reported in NUREG-0927.
These findings worn 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 Analysis, were issued for comment 6n May 1983.
The public comment period ended in July 1983 and comments received were used in preparing a resubm6ttal to CRGR.
A-3. Steam Generator July 30. 1983 July 30. 1983 The draf t NU6'EG report has been reviewed by the technical branches. their comments incorporated, and A-4 Tube Integrity transmitted to CRGR.
The revised report ull! be issued A-5, for public comment after mar.agement review. The NRC has formed a task Force to prepara proposed requirements.
A-12. Steam Generator July 1.
1983 September 15. 1983 Meetings were held with EPRI and Industry croops in December 1980. to resolve use of fracture
& Reactor mechanics methods for qualification of supports.
Coolant Pump NRC reviewer's comments on the final NUREG-0577 Supports were not received until mid-January 1982, causing a delay in issutnq the final report. Comments made by EPRI and the AIF subcormittee on material requirements have been incorporated into the final l
The resolution documents were forwarded to CRGR on July 11. 8983 and discussed in a meeting with them on July 27. 1933.
Some changes recommended by the CRCR were incorporated and the resolution package is undergoing Management Concurrence.
i I
A-17. Systems Inter-October 1984 Octobe. 1984 Work originally planned under TAP A-17 and TMI Action Plan Item !!.C.3. Systems Interaction.
actions were comb 6 ped under US1 A-I? and a new Task Nanager appointed.
3 l
l 4
PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS USI May 27, 1983
!!2 TITLE AQUA BOOK CURRENT REMARKS A-48, Hydrogen Control June 30. 1985 June 30, 1985 A Task Action Plan was approved on December Measures and 3,
1982. Work on this USI is limited to the generic resolution of hydrogen control and equipment Hydrogen Burns on Safety Equipment qualification for ice condenser and BNR Mark III containments. A Commission Paper regarding hydrogen control for Mark III and ice condenser containment was reviewed and endorsed by the CRGR on June 1, 1983.
The Commission Paper will be forwarded to the Commissioners by late August 1983.
A-49, Pressurized July 1985 December 31. 1985 A-49 was designated by the Commission as an USI on December 28. 1989.
The Task Action Plan was Thermal Shock approved and lusued on March 26. 1982. NRC staff PTS recommendations (SECY-82-465) were approved by the Commission in December 1982.
A new rule for PTS resolution has been drafted and will be published for pubtle comment during the summer of 1983.
5
USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION TASK MANAGER /
USI E2.
TITLE DATE COMPLETED REPORTS PUBLISHED IMPLEMENTATION STATQ1 TELEPHONE A-7, MARK I LONG TERM JULY 1980 HUkEG-0661 LICENSEES ARE IN THE PROCESS OF BYRON SIEGEL PROGRAN AUGUST 1982 NUREG-0661.
7PL.
DESIGNING AND INSTALLING MODIFICATIONS 492-7534 No, 1 TO MEET THE COMMISSION'S ORDER DATE FOR EACH CPERATING PLANT.
THE LICENSEES ARE IN THE PROCESS OF PREPARING PLANT-UNIQUE ANALYS!$ FOR SUBMITTAL 10 THE STAFF FOR POSI IMPLEMENIATION AUDIT REVIEW FOR COMPLIANCE WITH THE ACCEPTANCE CRITERIA CONTAINED IN APPENDIX A TO NUREG-0669.
TEN LICENSEE 5/ APPLICANTS HAVE SUBMITTED THEIR PLANT-UNIQUE ANALYSIS. CUR CONTRACTORS.
BNL AND THE FRANKLIN RESEARCH CENTER, ARE REVIEWING THESE SUBMITTALS. SEE MULTIPLANT ACTIDH ITEM D-01 IN NUREG-0748.
A-8, MARK II CONTAINMENT AUGUST 1981 NUREG-0808 THE REQUIREMENTS RECOMMENDED IN NUREG-BYROM SIEGEL 0808 ARE BEING IMPLEMENTED DURING THE 492-7534 POOL DYNAMIC LOADS OPERATING LICENSE REVIEW FOR EACM PLANT WITH A MARK !! CONTAINMENT. THESE REQUIREMENTS HAVE ALSO BEEN INCLULED AS AN ADDITION TO THE APPROPRIATE SECTION l
0F THE STANDARD REVIEW PLAN.
A-9, ATW5 SEPT. 1980 NUREG 0460, A TASK FORCE HAS BEEN ASSIGNED TO FORM A DAVID PYATT. RES VOL. 4 BASIS FOR THE FINAL ATWS RULE.
IN APRIL 443-7363 46FR$7521 1983. THE TASK FORCE AND STEERING GROUP DR AFTED THE FINAL RULE.
ELEMENTS OF THE RULE WERE PRESENTED TO THE CRGR ON APRIL 20, 1983.
TWO SUBSEQUENT NEEi!NGS WERE HELD ON MAY 25, 1983 AND JULY 12, 1983.
THE COMMISSION WAS BRIEFED ON SECY-83-293 ON AUGUST 3, 1983.
A PROPOSED AMENDMENT TO 50.62 15 BEING CONSIDERED FOR WESTINGHOUSE REACTORS AND SHOULD BE
(
PUBLISHED FOR PUBLIC COMMENT WITH THE FINAL RULE.
7
USl'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION TASK MANAGER /
U5g H2.
TITLE DATE COMPLETED REPORTS PUBLISHED IMPLEMENTATION STATUS TELEPHONE
~
A-36.
CONTROL OF HEAVY JULY 1980 NUREG-0612 IMPLEMENTATION REQUIREMENTS WERE DON HEIGHBORS LOADS NEAR SPENT ISSUED TO ALL LICENSEES BY LETTER 492-4837 FUEL DATED DECEMBER 22. 1980.
THE LETTER REQUESTEDs INTERIM ACTIONS 10 BE COMPLETED IN 90 DAYS. A PHASE I ACTION (REPORT CONIIRMATION AND JUSTIFirATION) IN SIX MONTHS AND PHASE It (SPECIFIC REQUIREMENTS)
IN MIME MONTHS.
ALL LICENSEES HAVE RESPONDED TO THE DECEMBER 22. 1980 GENERIC LETTER AND THEIR RESPONSES ARE BEING EVALUATED. AS OF AUGUST 1.
1983. 13 PNASE I REVIEWS HAVE BEEN COMPLETED AND IT 15 ANTICIPATED TO COMFLETE THE REMAINDER OF PHASE I IN FY-84.
SEE MULTIPLANT ACTION ITEM G-10 IN NUREG-0748.
A-39.
DETERMINATION OF MARK I-02-29-80 NUREG-0763 GENERIC 1ETTERS TRAN5MITTING THESE BYRON $1EGEL SAFETY RELIEF VALVE MARK II-09-30-82 HUREG-0783 NUREGS TO BWR APPLICAHIS AND LICENSEES 492-7534 (SRV) POOL DYNAMIC MARK III-10-16-82 NUREG-0802 HAVE BEEN ISSUED. IMPLEMENTATION ON MARK I PLANTS IS PART OF USI A-7.
LOADS AND TEMPERATURE IMPLEMENTATIDH ON MARK II AND MARK LIMITS FOR BWR III PLANTS IS BEING PERFORMED DURING CONTAINMENT THE OPERATING LICENSE REVIEW FOR EACH PLANT.
A-42, PIPE CRACKS IN JULY 1980 NUREG-0313 REV. 1 IN FEBRUARY 1981 HUREG-0313. REV. 1 WAS DICK CLARK ISSUED 10 aLL NOLDERS OF BWR OPERATING 492-7162 BOILING WATER LICEN!ES 0.
- 'NSTRUCTION PERMITS AND TO ALL REACTORS APPLICANTS FtR OPERATING LICENSES. BY JULY 1
1981 THE APPLICANTS / LICENSEES WERE TO PROVIDE THEIR PROGRAM FOR REPLACEMENT OF SERVICE SENSITITIVE LINES AND WELDS. THEIR PROGRAM FOR AUGMENTFD INSERVICE INSPECTION.
THEIR PROGRAM FOR IMPROVING THE WATER CHEMISTRY ENVIRONMENT AND INCOPORATION OF ADEQUATE LEAK DETECTION CAPABILITY. ALL LICENSEES HAVE RESPONDED AND THEIR REPLIES ARE BEING EVALUATED BY A TECHNICAL SUPPORT CONTRACTOR (INEL).
INITIAL TER'S ARE 10 BE C0f1PLETED IN THE SECOND AND THIRD QUARTERS OF FY33.
IMPLEMENIATION NAS CURRENTLY RECEIVED ADDITIONAL ATTENTION AND PROMINENCE BECAUSE OF COMi!NUED CRACKING EXPERIENCE. SEE Mutt! PLANT ACTION ITEM J-05 IN NUREG-0748.
9
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TASK 10 n = =c RESOLUTION OF A-1. WATER HAMMER E.;, ",,,,
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TASK 1 REPORTS TASK 4,1 REPORT TASK 4.4 REPORTS Chapman, R.L., et el,"Rownew and E voluemen of Actual and W --
_ ft L.,"An Ane*yes Teod for Predesting the Transene NUREG-0682,"Weter Hammer 6n Nueteer Power Plantsf' Potensees Weser Honumer Even. te Necesse Plante," EGGG Hydrodynemece P,seutting frem the Resed Fdhag of Voodos Pgeng July 1979 Interwn Rpt, CAAP-TR 042 (Rev,1), ?
1979 Swesent" EG&G catorum Ape. RE-E N000 Fahnsory 1979 Chapman, R.L.,"Weser Honemer Studeen." EG4G inter 6ae Rpt, CAAPTR4EWI (Rev.1), Jufy 1980 (Propered for NRC Unen Marter D K.,"An Anseyesse P.em.edue for Performens tonessures--
rec TASK 4.2 REPORT An.i,.of Nuenee, P,ene svs 6.m.m. sed to e iuse r NUREC/CR-2059, *T,empdessen of Asases and Suspected Weeer EG4G tesene Roe R E E-79 413. f shawary (Prepored for NRC Internal Hammer Even. In Nuesser Power Planet" May 1982.
Westent J C., Sorry, R A.,"A Staneof-the Art Litoreeste Uest Revoew of Wo.e Honumer," EG&G laserm Insene nyt.,
RE A-7tHM4, Apne 19FS (Prepared for NRC Usel Denunes P.N.,"An anweet.geteen of she Steam Veed ceasepes Weser Hemmer inemovens Mechenem," E G&G :
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,1979 (Prepared for NRC lenemet Usel TASK 2 REPORT TASK 4.3 REPORT
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ese Weser Honumer Analves and System Reveew," EG&G prolunmery Ret EGGCAAP 6131 July 1990 (Prepared for NMC for Uns - e Preisnenery er Werkeng W---=1 i
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