ML20116L164
| ML20116L164 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/04/1992 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9211180193 | |
| Download: ML20116L164 (3) | |
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(r ke lker Cvinpay ig 3 7; a,r n Caub,%l ca G ro rs -, ninent yi, e l'ir nhnt W %vvJ 1%J p.atnyJ.);oi Ottu e M 5cNi5 pmufx61u DIJMC POWCH
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Noitelt Lor 4, 1992 U.
S. Nuclc6r Regulatoly Commission ATTH: Document Control Desk Washington, D.C.
20555
Subject:
Catawba Nuclear Station, Unit 1 Docket Nc: 50-413 Supplomont to TS Amendment Request CIC7 Re. cad M.
G.
Tuckman's letter dated April 13, 1992 submitted chances to the Catawba Unit 1 Technical Specifications which were required for cyclo 7 operation.
This amendmont request was supplemented on August 26, 1992 with revisions of an editti-lal nature. to the April 13, 1992 submittal cont ains the Catawba Unit 1 Cyclo 7 (C1C7)
Roload Report.
Section 7,
" Accident Analysis", of this Reload Report contains a description of the accidents which were avriluated for cycle 7 operation.
Section 7 indicates that, for tle events listed, a single not of generic analysis were performeo for these events, and that the results for Catawba woro the same as those submitted in the approved McGuiro 2 Cyclo 8 reload report.
Because of a leaking fuel assembly found during the End of Cycle 6 refueling outage, the CIC7 core was rodosigned, resulting in a r.oro severo core power distribution with resp'ct to Steam Lino Bree';
(SLB).
Steam Lino Break was reanalyzed with the more limiting power distribution using the methodology given in DPC-NE-3001-PA, " Multidimensional Reactor Transients and Safety Analysis Physics-Paramotors Methodology" with the minor modifications given in the approved McGuiro 2 Cycle 8 reload submittal (Cctawba 1 Cycle 7 Hoload Report, reference 17).
The system thermal hydraulic responon of the SLB event has not been roanlalyred, and the DNBR roanalysis calculates a decrease in the minimum DNBR due to the more severo power dintribution.
However, the calculated luinimum DN9R for the CIC7 SLB analyais is still greater than the limit value of 1.45 given in DPC-NE-3001-PA, which demonstrates that the 170002 1
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U, S. Nuclear Regulatory Commission 11ovember 4, 1992 Page 2 SLB ovent meets all acceptanco criteria.
The increase in the severity of the power distribution causes a 4.6% decrease in DNBR margin.
The roanalysis of the SLB event requires no Technical Specification changes and no FSAR charagos.
Very truly yours, Ik. b,
M.
S.
Tuckman Milll/ SLB. SUP
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U.
S.
Nuclear Regulatory Commission November 4, 1992 Pago 3 xc:
(w/ Attachment)
Mr.
S.
D.
Ebneter Regional Administrator, Region II Mr. Heywood Shoaly, Chief Bureau of Radiological Hoelth South Carolina Department of Health Mr. Robert E. Martin, Project Manager Mr. W. T. Orders HRC Senior Resident Inspector Americar Nuclear Insurers c/c Dottio Sherman, ANI Library Tho Exchange, Suito 245 270 Farmington Avenuo Farmingtor., CT 06032 M&M Nuclear Consultants 1221 Avenuo of the Americas New York, New York 10020 INPO Records Contor Suito 1500 1100 Circlo 75 Parkway Atlanta, Georgia 30339 l
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