ML20248A703
| ML20248A703 | |
| Person / Time | |
|---|---|
| Issue date: | 07/19/1989 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Calvo J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8908080374 | |
| Download: ML20248A703 (25) | |
Text
,.
.q JUL 191999 MEMORANDUM FOR:
Jose A. Calvo, Chief Technical Specifications Branch Division of Operational Events Assessment. NRR.
FROM:.
David C. Fischer. Section Leader I
Special Projects Section
. Technical Specifications' Branch.
Division of Operational Events Assessment NRR
SUBJECT:
MINUTES OF MEETING WITH THE'B&W OWNERS GROUP (B&WOG) ON THE
-l TECHNICAL BASIS AND SCOPE OF THE B&WOG CORE OPERATING LIMITS l
REPORT (COLR) j 1
i
)
On June 29, 1989, the NRC staff met with the B&WOG.to discuss.the B&WOG proposed-1 COLR. ' The staff agreed, with the qualifications-stated below, that values for.
the following parameters could be placed in a COLR:
a)
Refueling boron concentration. The fundamental requirement, that-k
<.95 with all rods out during refueling. operations, is to be-r$NineII in STS.
.J b)
The curves which bound the safety limits.and the maximum allowable setpoints. The actual safety limits'upon which these curves are based (e.g., the 95% probability, 95% confiden~ce DNB limit; minimum DNBR of 1,3; and linear heat rate of 21 kw/ft ) are to be retained in STS.
In addition, the " Allowable Values" column may be deleted from Table 2.2-1, j
" Reactor Protection System Instrumentation Trip.Setpoints"..
Other Owners Groups may also choose to take advantage of these staff decisions.
Odginal syned By l
David C. Fischer, Section Leader Special Projects Section Technical Specifications Branch.
Division of 0perational Events Assessment, NRR
Enclosures:
List of Attendees B&WOG Slides (handouts)
DISTRIBUTION:
Please see attached (MINS MTG B&WOG 6/29) 41 OTSf[;D A:NRR OT
- NRR OTSB:00EA:NRR:
JOS N fgens:pmc rt DCFischer 0
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8908080374 890719 NE MEMEB MW
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s "JUL 191989 DISTRIBUTION:
1 TEMurley JHConran PDR j
JHSniezek CHBerlinger OTSB Members FJMiraglia CJHaughney OTSB R/F 0MCrutchfield JLieberman DOEA R/F l'
SAVarga LCShao
[j['?Centrah Files ~
l BKGrimes JWRoe GClainas-ELJordan l
FJCongel CIGrimes j
FGillespie WGKennedy Regional Administrators GMHolahan MGMalsch NRC Participants CERossi BDLiaw
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_ ~ _ _ _
m m vv.e BWOG/NRC MEETING JUNE 29, 1989 CORE OPERATING LIMITS-REFORT R&HE TITLE ORGANIZATION J.H. Taylor Licensing Manager BEW J.J. Sapyta Project Manager S&W Fuel Company Richard A. Kochendarfer Supervisory Engineer B&W Fuel Company-Brian J. Delano Principal Engineer B&W Fuel Company Randy H. Ellison Supervisory Engineer B&W William A. Rush Supervisor Core Reload AP&L Company Margaret Snow Licensing Engineer APEL Company Bob Tjader Rx Engineer OTSB Sheri Juergens General Engineer OTSB Joe McCarthy Sr. Faels Engineer GPU Nuclear Tracey saville Senior Engineer Duke Power Company Raymond Sund Senior Engineer-Nuclear Toledo Edison q
i Robert Schomaker Perform. Anal. Unit Mgr.
.B&W Gary Hanson Unit Manager B&W Fuel: Company
~
Frank McPhatter Licensing Engineer B&W Fuel Company Daniel Fieno Sr. Reactor Physicists NRC/SRXB Wayne Hodges Branch Chief NRC/SRXB 8
David Fischer Section Chief NRC/NRR/ DOER /OTSB i
l D.M. O'Shea Chairman BWOG Core FPC Performance Committee Larry Kopp Nuclear Engineer NRC/NRR/SRXB i
Mark Reinhart Sr. Operations Engineer NRC/NRR/0TSB g
John Schiffgens NRC/NRR/OTSB I
i
i I
i
'I NAME TITLE ORGANIZATION a
Courtney Smyth Chainaan BWOG Tech GPUN/B&WOG Spec Committee l
Howard Richings NRC/RSB 1
Larry Phillips Section Chief NRC/NRR/SRXB.
Jose Calvo Director OTSB OTSB 1
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I MEETING ON TECHNICAL BASIS AND SCOPE OF t
B&WOG CORE OPERATING LIMITS REPORT AGENDA NRC WHITE FLINT BUILDING, ROOM BB 1
JUNE 29, 1989, 1:00 P.M.
r I.
Introduction D. M. O'Shea II. Nuclear Imbalance Safety Limits R. A. Kochendarfer 11.1.
Safety Analysis, Safety Limits, Allowable Values, and Setpoints R. H. Ellison 1
IV. Operating Limits, QPT, and Peaking I
Factors R. A. Kochendarfer l
V.
Refueling Boron and MTC G. E. Hanson VI.
Discussion VII.
Conclusion i
4 1
l l
MEETING OBJECTIVE TO ARRIVE AT AGREEMENT ON THE CONTENT OF THE CORE OPERATING LIi4ITs REPORT (COLR)
CONSIDERATIONS IN PLACING PARAMETERS IN COLR SAFETY.RELATED ISSUES THE CRITERIA AND METHODS USED FOR THE DEVELOPMENT OF THE SAFETY LIMITS AND SETPOINTS WILL BE APPROVED BY THE NRC.
THE TOPICAL REPORT DESCRIBING THE CRITERIA AND METHODS WILL BE REFERENCED IN THE TECHNICAL SPECIFICATIONS.
THE DOCUMENTED STANDARD METHODS WILL PROVIDE THE NRC CLARIFICATION OF THE B&W TECHNIQUES.
TESTING, CALIBRATION, AND REPORTING REQUIREMENTS STILL IN PLACE.
1 i
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CONSIDERATIONS IN PLACING PARAMETERS IN COLR l
NRC RESOURCE IMPACT REDUCTION IN THE NRC REVIEW PROCESS DURING NORMAL RELOAD CYCLES.
l
CGh5IDERATIONS IN PLACING PARAMETERS IN COLR OPERATIONAL AND DESIGN FLEXIBILITY PROVIDE ADDITIONAL FLEXIBILITY FOR OPERATION AND' CORE DESIGN TO ADDRESS CORE PEAKING, OCCUPATIONAL DOSE, AND ACCIDENT RELEASES.
IRIP REDUCTION REACTOR VESSEL FLUENCE REDUCTION I
FUEL LEAKAGE REDUCTION RADWASTE CONCERNS OCCUPATIONAL DOSE REACTOR COOLANT ACTIVITY CONTINUE TO MEET ORIGINAL DESIGN CRITERIA WITH l
APPROVED METHODS.
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l SETPOINTS AND ALLOWABLE VALUES ALLOWABLE VALUES ALLOW FOR LARGER OPERATIONAL MARGIN WHILE AVOIDING LER CONDITIONS.
ALLOWABLE VALUES CAN LEAD TO MORE COMPLICATED TESTING AND SETPOINT DETERMINATIONS THAN OTHERWISE.
B&W OPERATING PLANTS HAVE NOT UTILIZED THE ALLOWABLE VALUE CAPABILITY WITHIN CURRENT TECHNICAL SPECIFICATIONS.
THE ALLOWABLE VALUES HAVE-BEEN THE SAME AS THE TECHNICAL SPECIFICATION SETPOINTS.
REMOVAL OF THE ALLOWABLE VALUES FROM THE RSTS DOES NOT ALTER THE APPROACH TO OPERATION AND TESTING THAT THE PLANTS CURRENTLY USE.
l
t FACTORS AFFECTING TRIP SETPOINTS i
CYCLE SPECIFIC PEAKING CHANGES DURING FUEL CYCLE DESIGN OPERABILITY INCREASE CHANGES BY PLAYING ONE TRIP OFF AGAINST ANOTHE.R REVISED DNB CORRELATION REVISED INSTRUMENTATION AND CALIBRATION ERROR TREATMENT CHANGES IN CORE FLOW FUEL ASSEMBLY CHANGES FOR IMPROVED NEUTRON ECONOMY I
REVISED LOSS OF FLOW ANN.YSIS (DNB WORK) l l
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OPERATING LIMITS, QUADRANT POWER TILT, AND PEAKING FACTORS e
Operating Limit Generation e
Fg and Fdelta H Limits and Monitoring
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l OPERATING LIMIT GENERATION FOR EACH FUEL RELOAD Criteria preserved:
LOCA kW/ft limit LOFA initial Conditions (DNB)
Using Technical Specification Limits on:
Control Rod Position Axial Power Shaping Rod Position Quadrant Power Tilt Axial Power imbalance
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DELTA H a
1.
Monitoring only appropriate when at the Tech Spec limits on i
rod and APSR position imbalance quadrant tilt I
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When monitoring is
- required, the fixed incore detector 4
system is utilized.
a.
Instantaneous b.
Based on 354 individual detectors-c.
Automatic comparison to the LOCA and-DNB criteria l
.___________w
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REFUELING BORON CONCENTRATION o
The current Standard Technical Specification (STS) criterion that the Refueling Boron Concentration (RBC) ensure a core K,gg s.95 during refueling operations has been moved to the Bases of the Revised Standard Technical Specifications (RSTS).
The Core Operating Limits Report (COLR) will contain the o
calculated RBC that meets the above criterion.
o The RBC that meets this criterion must be calculated for either the STS or RSTS, since this is the only way to ensure the plant knows the required concentration.
o Placement of the calculated RBC in the COLR has no impact on plant safety, o
All required surveillance and action statements remain in the RSTS.
1
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i MODERATOR TEMPERATURE COEFFICIENT The Moderator Temperature Coefficient (MTC) ismits that o
represent the FSAR Safety Analyses assumptions are the
" core operating limits" for MTC, and are provided in the COLR.
Location of these MTC limits in the COLR has no impact o
on plant safety, since any changes to the FSAR safety analyses would require separate NRC review.
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o All required surveillance and action statements remain in i
the RSTS.
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