ML19270G460

Forwards LER 79-024/01T-0

ML19270G460
Person / Time
Site:	Peach Bottom
Issue date:	06/01/1979
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19270G461	List: ML19270G460 ML19270G462
References
NUDOCS 7906080287
Download: ML19270G460 (2)

Text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 121518414000 June 1, 1979

r . Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

SUBJECT:

Licensee Event Report Narrative Descrietion The following occurrence was reported to "r. Greennan, Region I, Office of Inspection and Enforcement on *: a y 17, 197-).

Reference:

Docket Number 50-277 50-273 Report No: LER 2-79-24/lT-0 Raport Date: June 1, 1979 Occurrence Date: May'17, 1979 Facility: Peach Bottom Atomic Pocar Station Units 2 and 3 R.D. 1, Delta, PA 17314 Technical Snecification 2eference:

Technical Specification 6 9 2a(9) requires reporting

" Performance of structures, systems, or components that require remedial action or corrective measures to prevent operatian in a

.u n n e r less conservative than assumed in the accident analyses n the safety analysis report or technical specification basea; or  ;

discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition."

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, .. s Mr. Boyce 11 . Grier Page 2

.~ June 1, 1979

• LER 79-24/lT-0

. Description of the Event:

During the investigation of Bulletin 79-04, the outboard CRD return line for each unit was found not to be seismically qualified.

Consequences of Event:

The control rod drive system has been operated at Peach Bottom with the return line to the reactor isolated for the last 2 operating cycles and is therefore inactive. The CRD system is fully operational in this mode. The CRD return line piping inside containment is seismically qualified. The inboard containment isolation check valve in the CRD return line is closed in the present mode of operation. This check valve, as well as the outer check valve, was satisfactorily leak tested during the cost recent refueling outage. Because the inboard valve is leak tight, presently closed, and located in piping which is seismically qualified, the inadequate seismic support of the outboard piping and check valve has minimal safety significance. _

Cause of Event:

A seismic analysis of the ouboard CR0 return piping in response to IE Sulletin 79-04 indicated that the piping supports were unsatisfactory. A seismic analysis for the outboard piping apparently was not performed for initial installation due to an interface problem between the Architect Engineer and a Nuclear Steam System Supplier sub-contractor.

Corrective Action:

Seismically qualified pipe support designs have beer completed f or both units. The required modifications have been completed on Unit 2. The modifications on Unit 3 will be completed by the end of a one week outage scheduled to begin on June 1, 1979. 1 Yours truly, M. J. Cooney S perintendant Generation Division-Nuclear Attachment cc: Director, NRC - Office of Inspection and Enforcement Mr. Norman M. Haller, NRC - Office of Management &

Program Analysis 9

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