ML20039H050
| ML20039H050 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/06/1982 |
| From: | Miner S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201190465 | |
| Download: ML20039H050 (9) | |
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Docket flo. 50-316 J
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LICENSEE: Indiana & Michigan Electric Company 4
FACILITY:
D. C. Cook Nuclear Plant, Unit No. 2 SufrARY OF ffEETIf!G HELD ON DECEfiBER 8,1981 UITH INDIANA AND !!!CHIGAN ELECTRIC COMPANY AND A"ERIC/9 ELECTRIC POWER SERVICE CORPORATION TO DISCUSS THE USE OF EXXON NUCLEAR FUEL FOR Ti!E FUEL CYCLE NO. 4 RELOAD OF D. C.
COOK flVCLEAR PLAMT UNIT NO. 2 AND A PROPOSED INCREASE IN UNIT NO. 2 POWER ABCUT 1%
A neeting was held December 8,1981 between members of Indiana & Michigan Electric Company (licensee), American Electric Power Service Corporation, Exxon fluclear and the NRC. The purpose of the meeting was to give the licensee the opportunity of (1) discussing with the flRC staff the infomation required to justify a proposed Unit No. 2 power increase, and the supporting infomation to be supplied with regard to the reload of Unit to. 2 with Exxon fuel. The attendees list (Enclosure 1) and copjes of the meeting viewgraphs are attached.
A.
Proposed Power Increase The licensee stated that they will propose to increase the Themal Power of Unit 2 from 3391 int to 3425 fUt following the September 1982 refueling. Subsequently, during a telephone conversation the licensee stated the the Themal Power increase will be limited to 3411 fMt (the current maximum for a 4 loop Westinghouse Plants).
The licensee stated the the increase can be acconplished without any hardware changes. We had the following comments:
(1) They probably will have to amend the environmental report.
(2) They should review the new decay heat load to detemine whether there will be an impact.
(3) They should review and provide for the record any analysis which references power level.
(4) The current burnup level for fuel handling is 25,000 !MD/ fit.
If they expect burnup beyond this it will have to be addressed.
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., I (5) If the fission product inventory, enrichment or burnups are i
different from those currently used in the analysis of nomal radioactive releases or releases due to accidents or transients, the impact of this on the Safety Analysis in the FSAR should be provided.
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Unit No. 2 Core Reload for Cycle 4 l
The fuel for the reload will be 17x17 fuel supplied by Exxon Nuclear.
The current core is loaddd with 17x17 Westinghouse Fuel. The codes (methodoloby) and the status of the codes to be used in the analysis to support the reload are shown in Enclosure 2.
The outline of the infomation to be provided is shown in Enclosure 3.
The licensee 4
indicated that in their application they will supply only the large break LOCA analysis. The small break analysis will be provided as l
part of the Tf!I items.
l Sumary The licensee provided a schedule (Enclosure 4) for submission of their license amendment request, the data necessary to support the request and i
the f!RC approval dates necessary to support the November 19f?2 startup j
schedule following the next Unit 2 reload. We noted that some of the ENC topical reports on Evaluation fiodels had not' been liubmitted for NRC review.
The schedule for their submittals allows only two to four months for their approval by the NRC. We indicated that with the current scheduled NRC workload this is a very tight schedule for approval of topicals required to support a Safety Evaluation to be completed in time for Unit No. 2 startup.
Sydner Miner, project Manager Operating Reactors Branch #1 4
Division of Licensing
Enclosures:
As stated cc w/ enclosures:
See next page i
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ItEETING
SUMMARY
OPERATING REACTORS BRANCH NO. 1 DIVISION OF LICEf1 SING DISTRIBUTION Docket File NRC PDR Local PDR ORB No.1 Rdg File J. Olshinski J. Heltemes, AE0D B. Grimes (Emergency Preparedness)
S. Varga Project Manager OELD OI&E (3)
C. Parrish ACRS (10)
NRC Participant NSIC TERA cc:
Licensee with short cc list O
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Mr. John Dolan Indiana and liichigan Electric Company
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11r. Robert W. Jurgensen j
Chief Nuclear Engineer i
American Electric Power Service Corporation 2 Broadway
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.A, Gerald Charnoff, Esquire
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Washington, D. C.
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4 50011arket Street
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Mr. D. Shaller, Plant Manager f
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Doaald C. Cook Nuclear Plant J ",
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The Honorable Tom Corcoran
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ENCLOSURE 1 N
-1AEP MEETING O. C. COOK !! NIT 1 & 2 i
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AEP ' Nuclear Engineering j
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' AE.7C " Nuclear Engineering i
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'AEP,%. Nuclear Engineering jg Gerald Owsley Exxcn Nuclear
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s ENCLOSURE 2 i'
D. C. COOK UNIT 2 f'
CYCLE 4 RELOAD AND STRETCH POWER LICENSING l
METHODOLOGY LICENSING STATUS i
. NEUTRONICS ANALYSIS METHODS APPROVED POWER DISTRIBUTION' CONTROL BASIC APPROVED: OPTION UNDER REVIEW
. THERMAL HYDRAULICS THERMAL HYDRAULIC CONDITIONS APPROVED DNBR CORRELATION BEING REVISED PRESSURE DROP TESTING RESULTS INCORPORATED ROD BOW EFFECT UNDER REVIEW
. MECHANICAL DESIGN DESIGN CRITERIA & BASIC DESIGN APPROVED FOR SPECIFIC PREVIOUS APPLICATIONS DESIGN ANALYSIS - R0DEX2 UNDER REVIEW 12/8-1
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ENCLOSURE 2 (cont'd) 2
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METHODCLOGY (CorlT.)
LICENSING STATUS
. PLAflT TRANSIENTS PTS /PWR2 APPROVED FOR SPECIFIC PREVIOUS APPLICATI0t1S
. R0D EJECTION ACCIDENT XTRAN APPROVED GEtlERIC AtlALYSIS APPROVED FOR SPECIFIC PREVIOUS APPLICATI0tJS
. ECCS RELAP4-EM APPROVED REFLEX, T00DEE2 Belt 4G REVISED RODEX2 UNDER REVIEW O
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ENCLOSURE 3
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RELOAD APPLICATION FOR l
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D. C. COOK UNIT 2 AT 3425 MWT
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j MECHANICAL DESIGN ENC TOPICAL REPORT REFERENCED (TOPICAL REPORT TO BE SUBMITTED)
THERMAL-HYDRAULIC DESIGN i
NEUTRONIC/ CYCLE DESIGN I
PLANT TRANSIENT ANALYSIS SEPARATE REPORT LIMITING TRANSIENTS WILL BE IDENTIFIED.
ABOUT 7 WILL NEED TO BE ANALYZED.
ECCS ANALYSIS I
LARGE BREAK SEPARATE REPORT SMALL BREAK REFERENCE FSAR R0D EJECTION REFERENCE ENC TOPICAL REPORT j
TECHNICAL SPECIFICATION CHANGES 1
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ENCLOSURE 4 LICENSING SCHEDULE l
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ACTION 1
ITEM DATE ORGANIZATION
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TOPICAL REPORT - FUEL R0D THERMAL-MECHAtJICAL i
RESP 0ftSE EVALUATION MODEL 8/81 ENC TOPICAL REPORT - JUSTIFICATION FOR INCREASED FUEL EXPOSURE - (RESPONSE TO NRC LETTER TO ENC DATED 8/17/81) 1/82 ENC TOPICAL REPORT - MODIFIED ECCS EVALUATION MODEL (ENC INITIATED ACTION TO MODIFY ITS ECCS j
EVALUATION MODEL IN MID-1981; ENC LETTER TO 1
NRC DATED 9/21/81) 1/82 ENC TOPICAL REPORT - MODIFIED DNBR CORRELATION FOR PWR'S WHICH INCORPORATES 17X17 FUEL AND APPRO-PRIATE METHODOLOGY FOR APPLYING THE MODEL 2/82 ENC TOPICAL REPORT - MECHANICAL DESCRIPTION OF 17X17 FUEL DESIGN 3/82 ENC APPLICATION FOR D. C. COOK UNIT N0. 2 OPERATION WITH ENC FUEL AT A REACTOR THERMAL POWER LEVEL h/82 OF 3425 MWT IMECO l
APPROVAL OF MODIFIED ECCS EVALUATION MODEL 4/82 NRC APPROVAL OF RODEX2 FUEL PERFORMANCE CODE 6/82 NRC APPROVAL OF DNBR CORRELATION 6/82' NRC FUELPOOLLIMIT N
- i APPROVAL OF D. C. COOK UNIT 2 APPLICATION 10/82 NRC 4
D. C. COOK UNIT 2 STARTUP - CYCLE 4 11/82 IMECO i
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