ML20086R768
| ML20086R768 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/17/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8403010140 | |
| Download: ML20086R768 (2) | |
Text
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DUKE POWEll GOMPANY P.O. HO X O Olf.JD CIIAMLOTTE, N.C. 28242 "t":."2*"
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984 ruar Mr. James P. O'Reilly, Regional Administrator U.. S. Nuclear Regulatory Commission Region II 101.Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Re: Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414
Dear Mr,
O'Reilly:
Pursuant to 10 CFR 50.55(e), please find attached Significant Deficiency Report SD 413-414/84-02.
Very truly yours, et be Hal B. Tucker LTP/php Attachment Ecc: Director INP0 Records Center Office of Inspection & Enforcement Suite 1500~
U. S. Nuclear. Regulatory Lcmmission 1100 Circle 75 Parkway Washington, D. C. 2M55 Atlanta, Georgia 30339 NRC Resident Inspector Mr. Robert Guild, Esq.
Catawba Nuclear Station Attorney-at-Law P. O. Box l?097
-Palmetto Alliance Charleston, South Carolina 29412 21351 Devine Street Columbia, South Carolina 29205
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Duke, Power Company Catawba Nuclear Station
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~ REPORT L NUMBER:1 SD.413-414/84-02 :
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, REPORT DATEi February ~17, 1984~
FACILITY: 1. Catawba Nuclear Station, Units-1 and 2 m
- IDENTIFICATION OF DEFICIENCY
- Unconsidered effects of superheated steam l generated by steam generator for'Hain Steam Line (1reak analysis could result
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.in: Increased lower containment temperatures. This could possibly preclude
. safety related-components from performing their intended safety function. The ipotential def.iciency was identified December 20, 1983 lNITIAL' REPORT: 10n; January 19.-'1984', V. Brownlee,-NRC Region ll, Atlanta, GA
.was notified of the subject deficiency: by W. 0. Henry,1. K. Berry and M.'. L. ChiIders of Duke Power: Company, Charlotte, NC 28242.
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COMPOWENT AND/OR: SUPPLIER: Westinghouse. Water: Reactor Division is responsible e
, for the Main Steam-Line Break analysis.
JDESCRIPTION OF DEFICIENCY: The' original. Westinghouse Main Steam Line Break
- Analysis did
- not: consider ef fects of superheated. steam generated during steam
?generatorjblowdown..Superheat consideration could result in increased lower Jcontainment temperatures.cl Westinghouse letter Catawba-3474 dated' December 20,.1983 i
J advised 'that res'ults from initial reanalysis ' indicate lower containment temperature--
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icould possibly_. increase: to:383oF, which.is ; higher than temperature for 'which
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. J, containment components'have been generally qualified.
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ANALYSIS 0F SAFETY IMPLICATIONS:. Subjecting ' safety; related components to
- temperatures. higher.than indicated in the. original analysis could possible-fpreclude components from performing their Intended safety functions.
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SM CORRECTIVELACTION: Westinghouse will not complete their Main Steam Line Break--
((MSLB): reanalysis until March I','1984..Westingh'use has rec;uested that Duke o
(schedule a? meeting 1with.NRC'approximately? March 12, 1984, so that'results of g j:, y sthisfreanalysis-may be; presented.'
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