ML17328A103
| ML17328A103 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/03/1989 |
| From: | Giitter J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-88-16, NUDOCS 8908140231 | |
| Download: ML17328A103 (27) | |
Text
Docket Nos.
315 and 316 LICENSEE:
AMERICAN ELECTRIC POHER August 3, 1989 FACILITY: D.C.
COOK UNIT 2
SUBJECT:
'UMMARY OF MEETING WITH AEP AND NESTINGHOUSE TO DISCUSS CYCLE 8 RELOAD ANALYSIS.
On June 12, 1989, the staff met with AEP and Nestinghouse to discuss Cook Unit 2 reload analysis for cycle 8 and the associated Technical Specification (TS) changes to be proposed.
Meeting attendees are listed in Enclosure
- 1. Slides used during the presentation (all non-proprietary) are provided as Enclosure 2.
Changes to the Technical Specifications proposed by AEP included differing analysis assumptions (e.g., different values for peaking factors and moderator temperature coefficient), removal of cycle-specific parameters as allowed by Generic Letter 88-16, and revisions related to the Advanced Nuclear Fuel (ANF) analysis for cycle 6.
For cycle 8, AEP proposes to analyze only those events in the Original Final Safety Analysis Report (OFSAR).
The cycle 6 analysis, performed after AEP switched fuel vendors from Mestinghouse to ANF, included four additional events not analyzed in the OFSAR and considered three other events that were bounded by OFSAR analyses.
These seven events are listed in the meeting slides.
The staff indicated that AEP would be informed of the acceptability of excluding these additional seven events from the cycle 8 reload analysis.
Sincerely 8908i4023i 890803 PDR ADOCl( 05000316 P
PNU Original Signed by:
Joseph G. Giitter, Project Manager Project Directorate III-1 Division of Reactor Project - III, IV, V, and Special Projects
Enclosures:
As stated cc w/enclosures:
See next page
---Distribution>
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Mr. Milton Alexich Indiana Mi'chigan Power Company Donald C.
Cook Nuclear Plant CC:
Regional Administrator, Region III U.S.
Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Il1inois 60137 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box'818 Bridgeman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S.
Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvil le, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room j. - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N.
Logan Street Post Office Box 30035 Lansing, Michigan 48909 Mr.
S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Enclosure 1
LIST OF MEETING ATTENDEES NAME Tony Gody Thomas A. Georgantis Doug Malin Steve Brewer Rick Bennett Don Behnke Karl Toth Earl Novendstern Sandy Rupprecht Juan Nieto Vance Vanderburg Joseph G. Giitter Y. Gene Hsii Bob Jones AFFILIATION NRC AEPSC/NFSA AEPSC/NFSA AEPSC/NSSL AEPSC/NFSA '
W/NATD XEPSC/NSSL ll/CNFD P/NAT0 XEPSC/NSKL AEPSC/NFRA NRC/PDIII-I NRC/SRXB NRC/SRXB
Enclosure 2
AMERICAN ELECTRIC POWER SERVICE CORPORATION DONALD C.
COOK NUCLEAR PLANT UNIT 2, CYCLE 8 LICENSING SUBMITTAL PRESENTATION TO USNRC STAFF ROCKVILLE, MARYLAND JUNE 12, 1989
AEPSC PERSONNEL THOMAS A.
GEORGANTIS ASSOCIATE ENGINEER NUCLEAR FUEL AND ANALYSES DOUGLAS H. MALIN, MANAGER NUCLEAR FUEL AND ANALYSES STEVEN J.
- BREWER, MANAGER NUCLEAR SAFETY AND LICENSING VANCE VANDERBURG PRINCIPAL SCIENTIST NUCLEAR FUEL AND ANALYSES JUAN M. NIETO, SENIOR ENGINEER NUCLEAR SAFETY AND LICENSING RICHARD B.
- BENNETT, SENIOR ENGINEER NUCLEAR FUEL AND ANALYSES
WESTINGHOUSE PERSONNEL SADLER D.
RUPPRECHT, MANAGER
'I OPERATING PLANT LICENSING NUCLEAR AND ADVANCED TECHNOLOGY DIVISION DONALD H.
- BEHNKE, ENGINEER OPERATING PLANT LICENSING NUCLEAR AND ADVANCED TECHNOLOGY DIVISION
DONALD C.
COOK NUCLEAR PLANT UNIT 2 FUEL FABRICATION VENDOR HISTORY CYCLE FUEL VENDOR WESTINGHOUSE WESTINGHOUSE WESTINGHOUSE ANF ANF ANF WESTINGHOUSE
TODAY' PRESENTATION "DONALD C.
COOK NUCLEAR PLANT UNIT 2, CYCLE 8 SUBMITTAL TECHNICAL SPECIFICATIONS" PRESENTED BY:
VANCE VANDERBURG "SAFETY ANALYSIS CHAPTER EVENTS TO BE ADDRESSED FOR COOK NUCLEAR PLANT UNIT 2, CYCLE 8" PRESENTED BY:
JUAN NIETO CLOSING REMARKS PRESENTED BY:
STEVE BREMER
PROPRIETARY INFORMATION PRESENTATIONS BASED ON INFORMATION IN PUBLIC DOMAIN APPROPRIATE INDIVIDUALSWILL BE ASKED TO LEAVE DURING REQUESTED DISCUSSION (IF ANY)
OF PROPRIETARY INFORMATION
DONALD C.
COOK NUCLEAR PLANT,'NIT.2 CYCLE 8 SUBMITTAL TECHNICAL SPECIFICATIONS
TYPES OF TECHNICAL SPECIFICATION CHANGES TO BE PROPOSED CHANGES ASSOCIATED WITH CYCLE 8 ANALYSIS ASSUMPTIONS OR, RESULTS REMOVAL OF CYCLE-SPECIFIC PARAMETER LIMITS (GL 88-16)
REVISIONS RELATED TO CYCLE 6 ANALYSES
EXAMPLES OF CHANGES ASSOCIATED WITH ANALYSIS ASSUMPTIONS OR RESULTS FQ MTC CHARGING SAFETY INJECTION FLOW IMBALANCE BIT REMOYAL OTET/OPDT SETPOINTS
EXAMPLES OF CYCLE-SPECIFIC PARAMETER LIMITS ROD INSERTION LIMITS AXIAL FLUX DIFFERENCE LIMITS SDM FOR MODES 4 AND 5 ALL RODS OUT DEFINITION
EXAMPLES OF REVISIONS RELATED TO THE CYCLE 6 ANALYSIS ACTIONS REQUIRED PRIOR TO BLOCKING SAFEGUARDS DURING COOLDOWN MODE 2 DNB TECHNICAL SPECIFICATIONS INCREASED FEEDWATER FLOW TRANSIENT IN MODES 3 AND 4
ACTIONS PRIOR TO BLOCKING SAFEGUARDS INCREASE OF SDM BY 300 PPM IS AN ACCEPTABLE METHOD FOR PROTECTING FROM RECRITICAL
~
USE PROCEDURAL CONTROL
MODE 2 DNB TECHNICAL SPECIFICATION PROCEDURAL CONTROLS AND NON-SAFETY GRADE EOUIPMENT PROVIDE PROTECTION ON APPROACH TO CRITICAL LEAVE THE NUMBER OF OPERATING PUMPS AS IS
-- T/S CONSERVATIVE
-- IN PRACTICE, STARTUP WITH FOUR PUMPS LEAVE NIS POWER RANGE PROTECTION IN MODE 3 WHEN CRITICAL AT LOW POWER MODE T/S ADD LITTLE PROTECTION PROCEDURAL CONTROL BORON CONCENTRATION FOR CRDM TESTING
INCREASED FEEDWATER FLOW TRANSIENT IN MODES 3 AND 4 PROTECTION TO LIMIT AMOUNT OF WATER THAT CAN BE ADDED,TO STEAM GENERATORS REVIEW NEEDED FOR MODE 4 USE PROCEDURAL CONTROL
PRESENTATION TO THE USNRC ON "SAFETY ANALYSIS CHAPTER EYENTS TO BE ADDRESSED FOR COOK NUCLEAR PLANT UNIT 2 CYCLE 8" BY'R.
J.
M. NIETO/AEPSC ROCKVILLE, MD JUNE 12, 1989
DETAILED COMPARISON OF EVENTS ADDRESSED IN THE SAFETY ANALYSIS CHAPTERS OF THE ORIGINAL FSAR (OFSAR)
AND THE CYCLE 6 UPDATED FSAR (UFSAR).
OFSAR VS.
UFSAR EVENTS BOUNDED EVENTS ANALYZED:
TOTAL EVENTS ADDED:
C6 ADDED EVENTS (SRP/UFSAR SECTION) 1.
(15.3.4/14.4.4)
RCP SHAFT BREAK (ANALYZED) 2.
(15.4.3/14.5.3)
SINGLE RCCA WITHDRAWAL (ANALYZED) 3.
(15.4.7/14.5.7)
INADVERTENT,LOADING AND OPERATION OF FUEL ASSEMBLY IN AN IMPROPER POSITION (ANALYZED) 4.
(15.5.1/14.6.1)
INADVERTENT OPERATION OF THE ECCS THAT INCREASES REACTOR COOLANT INVENTORY (BOUNDED) 5.
(15.5.2/14.6.2)
INADVERTENT OPERATION OF CVCS THAT INCREASES REACTOR COOLANT INVENTORY (BOUNDED) 6.
(15.6.1/14.7.1)
INADVERTENT OPENING OF A PZR PORV (ANALYZED) 7.
(15.6.2/14.7.2)
RADIOLOGICAL CONSEQUENCES OF FAILURE OF SMALL LINES CARRYING PRIMARY COOLANT OUTSIDE CONTAINMENT (BOUNDED)
THE ANALYSIS USED FOR CYCLE 6 WAS DESIGNED TO ADDRESS NRC STAFF CONCERNS WITH ANF METHODOLOGY.
CYCLE 8 WILL RELY ON WESTINGHOUSE METHODOLOGY.
IN DISCUSSIONS RELATING TO THE CYCLE 6 EFFORT, THE NRC STAFF INDICATED THAT THERE l4AS NO DESIRE TO BACKFIT.
SEVERAL DONALD C.
COOK VINTAGE PLANTS ANALYZED BY WESTINGHOUSE HAVE A COMPARABLE LICENSING BASIS TO COOK NUCLEAR PLANT UNIT 2
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'HERE IS REASONABLE ASSURANCE THAT THE PUBLIC HEALTH AND SAFETY MILL BE PROTECTED IF THE LICENSING BASIS IN THE OFSAR IS USED FOR FUTURE CYCLES OF UNIT 2
- CONCLUSION DURING OUR UNIT 2 CYCLE 6 LICENSING CAMPAIGN, WE HAD OUR FUEL VENDOR, ANF, ANALYZE THE FOUR ADDITIONAL EVENTS THAT HAVE BEEN IDENTIFIED.
THIS SERVED TO INCREASE THE STAFF'S CONFIDENCE IN ANF'S METHODOLOGY AND"CAPABILITY TO ANALYZE OUR UNIT.
THIS WAS DONE WITH AN WAS UNDERSTANDING WITH THE STAFF THAT OUR LICENSING BASIS NOT BEING EXPANDED.
WE COMPLIED WITH THAT REQUEST AT THAT TIME, BUT WE ARE NOW CONCERNED THAT THAT. EFFORT COULD BE MISTAKENLY CONSTRUED AS A PRECEDENT FOR WHAT CONSTITUTES OUR LICENSING BASIS.
IN SUPPORT OF OURR NEW NDOR'S