ML19253B362

LER 79-057/01T-0:on 790927,as Result of Pipe Stress Reanalysis,Plant Was Notified That Five Pipe Supports Were Considered Inoperable.Caused by Piping Overstress.All Mods & Analyses Performed within Tech Spec Framework

ML19253B362
Person / Time
Site:	FitzPatrick
Issue date:	10/10/1979
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19253B361	List: ML19253B360 ML19253B362
References
LER-79-057-01T, LER-79-57-1T, NUDOCS 7910150445
Download: ML19253B362 (2)

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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-057/01T-0 Page 1 of 1 During normal operation, as the result of the Pipe Stress Reanalysis being conducted by the Architect Engineer, the plant staff was notified that five pipe supports were considered inoperable; two were associated wi th Service Water return to the lake (H46-280 and H46-281) one was associated with Core Spray (H14-46) and two were associated wit! cre RHR System (H10-503 ind PFSK-503). As set forth in the August 14, 1979 letter lif ting the Show Cause Order of March 13, 1979, analysis was performed to determine the effect of these overstressed supports upon system operability. From this analysis it was determined that two supports, H14-46 on the "B" Core Spray System and H46-281 on the Service Water System caused piping overstress.

The modifications to H14-46 were completed within the seven (7) day time frame required by the Technical Specifications and the August 14, 1979 letter. Surveillance testing of safety systems equired by tae Technical Specifications was satisfactorily accomplished during the pei iod in which "B" Core Spray System was considered in-operable. The support is now fully acceptable.

The Service Water Sy, stem is not addressed in the Technie=1 Specifications.

Modifications to H46-281 were accomplished within the seven . ) day time f rame requi red by the ALgust 14, 1979 letter. The support is now fully acceptable.

As set forth in Paragraph IV.4 of the August 14, 1979 letter, analysis was performed which proved the RHR System remained operable with H10-503 and PFSK-956 removed . Modi fications to H10-503 have been completed. This support is now con-sidered fully acceptable. Modification to PFSK-956 are in progress. The affected portion of the RHR system,' the supply piping to the Fuel Pool Cooling System is isolated from the remainder of the system during power operations.

Analysis by the Architect Engineer showed that with H46-280 removed from the Service Water System no piping overstress would occur which would result in system inoperability. Modifications to this support are currently being designed. These will be pursued in an expeditious manner.

As noted above, all modifi cation and analysis were performed within the time frames set forth in the Augt 14, 1979 letter and the Technical Specifications.

All supports causing system inoperability have been upgraded such that the systems are fclly operable. Modifications to those supports which, although inoperable, do not result in system inoperability,are being pursued in an expeditious manner.

The re fore , the event did result in a significant safety hazard to the public health and safety.

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