ML20246F751
| ML20246F751 | |
| Person / Time | |
|---|---|
| Issue date: | 06/29/1989 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Calvo J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8907140013 | |
| Download: ML20246F751 (25) | |
Text
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June 29 1989-MEMORANDUM FOR:
Jose A. Calvo, Chief' i-Technical Specifications Branch Division of Operational Events Assessment, URR H
FROM:~
David C. k ist.Ser, Section Chief Special Projects Section Technical Specifications Branch Division of Operational Events Assessment, NRR
SUBJECT:
MINUTES OF MEETING WITH CABC0CK AND WILC0X OWNERS GROUP (B&WOG) ON THEIR NEW STANDARD TECHNICAL SPECIFICATIONS (STS)
On May 15, 1969 the NRC staff met with the Babcock and Wilcox Owners Group (B&WOG)-
to hear the presentation of their proposed new Standard Technical Specifications-(STS), and to present an overview of the planned review process. The format and organization of the new STS were presented by Courtney Stryth of the B&WOG. The review of the new B&WOG STS will be conducted in accordance with the schedule and milestone chart provided.
Original Signed by David C. fischer David C. Fischer, Section Chief Special Projects Section Technical Specifications Branch Divisien of Operational Events Assessment, NRR
Enclosures:
List of Attendees Milestenes for B&WOG r.ew STS (STS) and lead plant B&WOG Handout DISTRIBUTION:
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tiEETING WITH B&WOG Presentation of STS - May 15, 1989 NAME AFFILIATION Jim Miller NRC/0TSB/NRR Mark Reinhart NRC/0TSB/NRR John Reinhart Public Tom Dunning _
NRC/0TSB/NRR G. C. Schieck B&W Bill LeFave NRC/ DEST /SPLB Larry Kopp NRC/SRXB/NRR Lerry Phillips NRC/ DEST /SRXB John 0. Schiffgens NRC/0TSB/NRR Robert J. Giardina NRC/0TSB/NRR Bob Tjader NRC/0TSB/NER Howard Richings NRC/ DEST /SRXB J. Wermiel NRC/ DEST /SPLB C. Li NkC/ DEST /SPLB Jose A. Calvo NRC/0TSB/NRR James Wing NRC/FRAB/NRR Peter Prescott NRC/PEB R. R. $garro PPEL/BWROG Donald P. Hoffman EXCEL /BWROG TSC Calvin W. Moon NRC/0TSB/KER l
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-NRC/ DEST /ESGB Sai P. Chan hRC/ DEST /ESGB l-Joseph P. Joyce NRC/ DEST /SICB l
Scott Newberry NRC/ DEST /SICB l
Chris Hoxie NRC/0TSB/NRR Courtney Smytb GPUN/B&WOG Philip J. North Duke /B&WOG Daniel G. Green FPC/B&WOG Robert A. Turner BEWOG l
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m_-,- .-,g------,--r,- a I 9. B&WOG REVISED STANDARD TECHNICAL SPECIFICATIONS IRSTS) PROGRAM OBJECT,IVES INDUSTRY CHAPTER DEVELOPMENT ORGANIZATION OF BAW-2076 RELOCATION OF CERTAIN SPECIFICATIONS OVERVIEW 0F TECHNICAL CHANGES BASES CONTROL AD0PTI6N OF RSTS BY B&WOG PLANTS
SUMMARY
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i B&WOG REVISED STANDARD TECHNICAL SPECIFICATIONS OBJECTIVES FOCUS INCLUDE ONLY SPECS REQUIRED FOR SAFETY AND RELIEVE ADMINISTRATIVE BURDEN CLARLTl MAKE USER FRIENDLY AND MINIMIZE INTERPRETATION ACCURACY CORRECT KNOWN ERRORS, STRENGTHEN WEAKNESSES TRANSIENT REDUCTION REQUIRE PLANT SHUTDOWN ONLY WHEN NECESSARY FOR SAFETY UNDERSTANDING IMPROVE BASES TO SHARPEN ORIGIN AND IMPORTANCE OF REQUIREMENTS v
INDUSTRY CHAPTER DEVELOPMENT AND B&WOG RSTS PREPARATION e DEVELOP WRITERS GUIDE e ASSIGN CHAPTERS TO LEAD ORGANIZATIONS e CHAPTERS DRAFTED BY INDUSTRY LEAD CHAPTER ORGANIZA-TION e REVIEW AND COMMENT BY CHAPTER TASK GROUPS e INDUSTRY COORDINATION WORKING GROUP REVIEW MEETINGS e ISSUE CHAPTERS TO INDUSTRY GROUPS FOR PREPARATION OF REVISED STS e PREPARATION OF B&WOG REVISED STS CHAPTERS - REVIEW BY CWNERS - ISSUE B&WOG RSTS 1
4 4 INDUSTRY CHAPTER LEADERS 1.0 USE AND APPLICATION WOG 2.0 SAFETY LIMITS B&WOG l 3.0 LCO & SURVEILLANCE WOG REQUIREMENT APPLICABILITY 3.1 REACTOR B&WOG 3.2 INSTRUMENTATION WOG RPS ESFAS/EFIC PAM 3.3 REACTOR COOLANT SYSTEM B&WOG 3.4 ECCS CEOG 3.5 CONTAINMENT SYSTEMS B&WOG 3.6 PLANT SYSTEMS CE0G 3.7 ELECTRICAL POWER SYSTEMS BWROG 3.8 SHUTDOWN / REFUELING WOG 4.0 DESIGN FEATURES 5.0 ADMINISTRATIVE CONTROLS i .1
ORGANIZATION OF BAW-2076 e REVISED TECHNICAL SPECIFICATION e DISCUSSION OF CHANGES FROM PREPARER'S TECHNICAL SPECIFICATIONS 1 e MARKUP 0F EXISTING TECHNICAL SPECIFICATIONS e BASES e MARKUP OF B&W STS AS REVISED BY GENERIC LETTERS
i ) j RELOCATION OF SPECIFICATIONS TO PLANT PROGRAMS e 0WNERS TO SELECT PLANT-SPECIFIC PROGRAM BEST SUITED FOR PARTICULAR SPECIFICATION: - NEW FSAR CHAPTER - PLANT PROCEDURES - PROCESS CONTROL PROGRAM - 0FFSITE DOSE CALCULATION MANUAL - QUALITY ASSURANCE PROGRAM - FIRE PROTECTION PROGRAM - RADIATION CONTROL PROGRAM e EXAMPLE RELOCATION: GL 89-01, RETS
OVERVIEW OF TECHNICALDIANGES e CHANGES INCLUDED IN THE RSTS ARE BELIEVED TO BE THE MININUM SET ACCEPTABLE FOR AD0PTION BY B&WOG PLANTS e CHANGES ARE JUSTIFIED TECHNICALLY IN THE DISCUSSION OF CHANGES AND BASES SECTIONS e CHANGES INCLUDE ADDITION OF NEW SPECIFICATIONS e MORE IMPORTANT TECHNICAL CHANGES ARE TO BE LISTED BY CHAPTER l - - - - - _ _ - - - - - - - - - -.. ~ _ - - - -
l l l \\ SIGNIFICANT TECHNICAL CHANGES BY CHAPTER 3.0 APPLICABILITY e SPECIFY ONLY ONE CONDITION AT A TIME MAY BE ENTERED e ADDED LC0 3.0.6 TO ALLOW REQUIRED ACTIONS TO BE DELAYED FOR EQUIPMENT REQUIRED TO BE TAKEN OUT OF SERVICE FOR SURVEILLANCE TESTING e SR 3.0.5 (FORMERLY 4.0.5) PERMITS 96 HOURS TO DETERMINE OPERABILITY WHEN DEGRADATION IS OBSERVED e
L I SIGNIFICANT TECHNICAL CHANGES BY CHAPTER (CONT'D) 3.1 REACTOR e' CORE OPERATING LIMITS REPORT (COLR) USED IN VARIOUS LCOs e EXTENDED ACTION TIME FOR AXIAL POWER IMBALANCE FROM 15 MINUTES'TO 2 HOURS e INCLUDED MINIMUM TEMPERATURE FOR CRITICALITY IN PHYSICS TEST EXCEPTIONS FQ AND F3 N RETAINED AS ACTION REQUIREMENTS WHEN e PRIMARY PROTECTION (ROD POSITION AND FLUX SHAPE) ARE NOT MET 1
) SIGNIFICANT TECHNICAL CHANGES BY CHAPTER (CONT'D) 3.2 INSTRUMENTATION e CORE OPERATING LIMITS REPORT (COLR) IS USED FOR VARIOUS SETP0INTS e SURVEILLANCE OF RPS BASED ON BAW-10167 e-SHUTDDWN NOT REQUIRED FOR TWO IR OR SR NEUTRON CHANNELS OUT-0F-SERVICE e REVISED REACTOR TRIP MODULE AND REACTOR TRIP BREAKER LC0 TO AGREE WITH B&W DESIGN AND GL 85-10 e EFIC ALLOWABLE OUTAGE TIME WAS MADE CONSISTENT WITH ITS ASSOCIATED TRAIN A0T e BYPASS OF A SINGLE EFIC CHANNEL IS PERMITTED WITH CONTINUED OPERATION e RISK BASED JUSTIFICATION HAS BEEN USED FOR NOT INCLUDING ALL CATEGORY 1 ACCIDENT MONITORING INSTRUMENTS
4 i SIGNIFICANT TECHNICAL CHANGES BY CHAPTER (CONT'D) e RCS PT LIMITS MOVED TO PTLR ) i i e SOAK TIME ADDED TO TIME TO ACHIEVE COLD SHUTDOWN WHEN PT LIMIT IS EXCEEDED i e RC LOOPS MODE 3, 4, AND 5 REQUIRES FLOW ONLY DURING ESRON DILUTION e ADDED NOTE TO ALLOW INSITU TESTING OF SAFETY VALVES IN MODE 3 e ADDED INCREASED RCS INVENTORY BALANCE WHEN RB SUMP ) LEVEL IS IN0PERABLE i I
SIGNIFICANT TECHNICAL CHANGCS BY CHAPTER (CONT'D) 3.4 ECCS e EXTENDED THE A0T FOR THE CORE FLOOD TANK WHEN IN0PERABLE DUE TO BORON CONCENTRATION 3.5 CONTAINMENT e APPENDIX J LEAKAGE LIMITS HAVE BEEN MOVED TO DIVISION 4.0 " DESIGN FEATURES" e RELOCATED CONTAINMENT ISOLATION VALVE LIST TO THE FSAR e COMBINED CONTAINMENT SPRAY AND COOLING TO EXTEND THE A0T FOR RB COOLING IN CONSIDERATION OF THE REDUNDANCY PROVIDED BY RB SPRAY hh _m..____._-______:_m_
SIGNIFICANT TECHNICAL CHANGES BY CHAPTER (CONT'D) 3.6 PLANT SYSTEMS o REVISED NUMBER OF MSSVs ALLOWED TO BE INOPERABLE BASED ON REACTOR POWER AND REACTOR TRIP SETPOINT 4 e AFTER 45 DAY DECAY THE FUEL POOL VENTILATION IS NOT REQUIRED TG 3F. OPERABLE o ADDED NEW TS FOR MFW ISOLATION VALVES 31Z__ ELECTRICAL e REDUCED NUMBER 01 DG COLD FAST STARTS e DELETED STAGGERED TESTING FOR 31 DAY DG SURVEILLANCE DETAILS OF AC & DC BUSES ARE LOCATED IN THE BASES e
'5IGNIFICANTTECHNICALCHANGESBYCHAPTER(CONT'D) d 3.8 SHUTDOWN AND-_ REFUELING e SHUTDOWN BORON CONCENTRATION IS REFERENCED TO THE COLR o ADDED REQUIREMENT TO RECIRCULATE COOLANT DURING BORON CONCENTRATION REDUCTIONS e M0MENTARY OPENING OF RB AIRLOCK IS PERMITTED DURING REFUELING e CONTAINMENT ISOLATION BY EQUIVALENT MEANS IS PERMITTED e OPERATION OF DHR IS BASED ON MAINTAINING TEMPERA-TURE NOT FLOW e DHR IS PERMITTED TO BE OUT-0F-SERVICE FOR PREVENTA-TIVE MAINTENANCE FOR 7 DAYS l
B&WOG TECHNICAL SPECIFICATION BASES CONTROL e BASES BACKUP DOCUMENTS PREPARED e BASES STATE REASONS FOR REQUIREMENTS e PROPOSED CHANGES REVIEWED BY ON-SITE SAFETY REVIEW COMMITTEE o CHANGES DUE TO PROPOSED TECHNICAL SPECIFICATION CHANGES WILL BE REVIEWED BY NRC PRIOR TO IMPLEMEN-TATION e' OTHER CHANGES WILL BE REVIEWED BY NRC IF THEY: CHANGE THE STATED REASON FOR THE REQUIRE-MENT ALLOW COMPLYING WITH THE REQUIREMENT IN A LESS CONSERVATIVE WAY REDUCE TrlE MARGIN OF SAFETY ASSOCIATED WITH A TECHNICf.L SPECIFICATION CHANGES MEETING THESE CRITERIA WILL BE I REGARDED AS APPROVED UPON RECEIPT OF AN NRC LETTER OR [603 DAYS AFTER SUBMITTAL TO THE NRC 3 CHANGES NOT MEETING THESE CRITERIA WILL BE IMPLEMENTED AND PROVIDED TO THE NRC AT THE ANNUAL FSAR UPDATE I ) {
w GROUNDRULES FOR ADOPTION OF RSTS BY B&WOG PLANTS e RSTS FORM THE BASIS FOR PLANT-SPECIFIC SPECIFI-CATIONS e ADOPTION OF RSTS WILL INCUR SUBSTANTIAL ADDITIONAL COST - NEW TEST PROCEDURES AND PROGRAMS - PERSONNEL TRAINING ~ - PROVISIONS FOR DOCUMENTATION PREVIOUSLY IN PMs e COST OF IMPLEMENTATION NEEDS TO BE REASONABLE e STS AND " CUSTOM SPECIFICATION" PLANTS WILL SEE CHANGES AND COSTS DIFFERENTLY 1 o CHANGES INCLUDED IN RSTS ARE CONSIDERED MINIMUM ACCEPTABLE TO JUSTIFY AD0PTION BY B&WOG PLANTS e A PROGRAM IS PLANNED TO JUSTIFY ADDITIONAL CHANGES i
O 4 l 1
SUMMARY
q e MAJOR EXPENDITURE OF DEVELOPING RSTS WAS DEVELOP-MENT OF IMPROVED BASES l e THE BENEFIT OF THIS EXPENDITURE HAS BEEN REALIZED BY THE IMPROVED BASES o AD0PTION OF RSTS BY B&WOG PLANTS WILL REQUIRE SUBSTANTIAL ADDITIONAL EXPENDITURE i - IMPROVEMENTS MUST JUSTIFY THE COST OF l AD0PTION e EXISTING PLANT TECHNICAL SPECIFICATIONS ARE SAFE
~ Boron Concentration 3.8.1 !~ 3.8 SHUTDOWN AND REFUELING OPERATIONS .3.8.1 Boron Concentration LCO 3.8.1
- a. Boron concentration of filled portions of the reactor coolant system and the refueling canal shall be maintained as specified in the CORE OPERATING LIMITS REPORT and,
- b. Boron concentration shall not be reduced unless reactor coolant is recirculating.
APPLICABILITY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE ALTERATIONS 15' minutes outside limit. and positive reactivity addition. E AND Boron concentration being reduced and A.2 Initiate reactor coolant 15 minutes reactor coolant not recirculation. recir,culating. MQ E A.3 Initiate boration to Boron concentration restore the required 15 minutes outside limit and baron concentration. reactor coolant not recirculating. AND 1 hour ' A.4 Perform SR 3.8.1.1. EQ Once per nour thereafter. AND A.5 Continue boration as Until required required in A.3 above. boron concen-tration is restored. Final Draft Date: 4/B9 Unit Name 3.8-1 Amendment i
V: Boron Concentration I ? 3.8.1 a SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1' ' Verify baron concentration of the reactor 72 hours coolant system and 'the refueling canal within limits. SR 3.8.1.2 Verify reactor coolant is recirculation 0 Within 15 minutes prior to reduc-ing reactor coolant boron concentrations. u. L i Final Draft ~" Date: 4/89 Unit Name 3.8-2 Amendment
i- .-T Main Steam Isolation Valves 3.6.2 e (, 3.6 PLANT SYSTEMS 3.6;2 Main Steam isolation Valves LCO 3.6.2 [Two) main steam isolation valves (MSIV) shall be OPERABLE APPLICABILITY: MODES 1, 2, and 3. ..............................N0TE-------------------........... [ Provisions of LCO 3.0.4 are not appitcable) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME' A. One MSIV inoperable. A.1 Restore MSIV to OPERABLE 4 hours status. E A.2.1 Close inoperable MSIV. 4 hours [BiQ) A.2.2 Be in MODE 2. 4 hours B. One MSIV inoperable in B.1 Restore MSIV to OPERABLE 4 hours MODES 2 or 3. status. E B.2 Close inoperable MSIV. 4 hours i ~ C. Required Actions NOT C.1 Be in MODE 3. 6 hours met within required Completion Time. AND C.2 Be in MODE 4. ,12 hours Final Draft Date: 4/89 unit ta. m. e e a
t '- ,..<i-Main Steam Isolation Lives j e -3,6.2 SURVEILLANCE REQUIREMENTS -] 1 SURVEILLANCE FREQUENCY SR 3.6.2.1
NOTE---------------------
d Provisions of SR 3.0.4 are not applicable l Verify MSIV closure time f [6] seconds when d actuated by an [SFRCS main steam line low 18 months pressure] test signal 1 SR 3.6.2.2 Verify MSIV closure time s [6.5) seconds when actuated by an [SFRCS steam generator / feed-18 months water high differential pressure) test signal Final Draft J Date: 4/89 ) na m_. 8 J <}}