ML19341C971
| ML19341C971 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/26/1981 |
| From: | Rodriquez R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| IEB-79-14, RO-81-010, RO-81-10, NUDOCS 8103040637 | |
| Download: ML19341C971 (2) | |
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, S..'.~ U ~.~.1 SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street. Box 15430, Sacramento, California 95813; (916) 452-3211 February 26, 1981
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Mr. R. H. Engelken, Director U
Region V Office of Inspection & Enforcement 9
1990 North California Boulevard g y W.
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Docker No. 50 -312
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Reportable Occurrence 81-10
Dear Mr. Engelken:
In accordance with Technical Specifications Section 6.9.4. l(1) and Regulatory Guide 1.16, Revision 4, Section C.2.a(9), the Sacramento Municipal Utility District reports the following Licensee Event Report Number 81-10.
NRC Bulletin 79-14 required pipe stress analysis on nuclear "as built" configurations.
One unique configuration was noted which did not conform to the technique used in the pipe stress analysis. A new technique code was developed to analyze this configuration by Bechtel Corporation. The initial data for this unique configuraticn indicated that the point would be overstressed at design conditions.
The point in question is the fitting at the coo.~.er bypass connection of the Decay Heat System A.
Bechtel has indicated that the connection is not overstressed at the present condition of refueling shutdown.
Presently core cooling is on Decay Heat System "B".
A complete report will be submitted to your office within fourteen days.
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Manager Nuclqa. Operations RJR:RUC:rm 9
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U. S. NUCLEAR REGULATORY COMMISSION NRC FORM 166 (7-77)
UCENSEE EVENT REPORT
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