05000278/LER-1983-005, Forwards LER 83-005/01T-0.Detailed Event Analysis Submitted

Forwards LER 83-005/01T-0.Detailed Event Analysis Submitted

ML20072V292
Person / Time
Site:	Peach Bottom
Issue date:	03/25/1983
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20072V295	List: 05000278/LER-1983-005, Forwards LER 83-005/01T-0.Detailed Event Analysis Submitted
References
NUDOCS 8304110551
Download: ML20072V292 (2)

LER-2083-005, Forwards LER 83-005/01T-0.Detailed Event Analysis Submitted

Event date:
Report date:
2782083005R00 - NRC Website

text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (215)841 4000 March 25, 1983 Mr. R. C. Haynes, Administrator US Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

Licensing Event Report Narrative Description

Dear Mr. Haynes:

The.following occurrence was reported to Mr. A. R. Blough of Region I, US NRC on March 14, 1983.

Reference:

Docket No. 50-278 Report No: 3-83-05/1T-0 Report Date: March 25, 1983 Event Date: March 12, 1983 Facility: . Peach Bottom Atomic Power Staticn RDl, Delta, PA 17314 Technical Specification Reference Technical Specification 3.10.A.1 states "The reactor mode twitch shall be locked in the " Refuel" position during core alterations and the refueling interlocks shall be operable except....."

Description of Event Repairs were made to the refueling bridge interlock control cable on 3/13/83. Several conductors in this cable had been cevered the previous day during routine refueling operations.

The post maintenance surveillance test indicated that the ref:mling interlocks associated with bridge travel across the reactor were inoperable. The interlocks were repaired and cuccessfully tested. Later on 3/14/83, the computer alarm typer printouts since the last surveillance test, revealed that these interlocks had been inoperable during the movement of four fuel bundles from the core to the spent fuel pool.

8304110551 830325 PDR ADOCK 05000278 p"

h-9 s eor 4

Mr. R. C. Haynss Paga 2 Possible Consequence of the Event A misaligned refueling bridge interlock switch prevented operLtion of the refueling interlocks when the refueling bridge wa's moved over the reactor. Four fuel bundles had been moved during the time the interlock was. inoperable. The four bundles of fuel were removed ' from the reactor to the spent fuel pool, therefore, no reactivity increase occurred as a result of these fuel moves. The safety significance is considered minimal as no fuel loading occurred during this time.

Cause of the Event The cause of the inoperability .is believed to be rotation of the switch arm on the switch shaft.

Corrective Action The refueling bridge position switch was properly adjusted and the interlocks successfully tested. The fuel handling procedure has been revised to require the reactor operator.to monitor the operability of the refueling interlocks using the rod withdrawal permissive indicating light whenover fuel-movements occur over the reactor.

Very truly yours, J. Cooney uperintendent Nuclear Generation Division Attachment cc: Mr. A. R. Blough - NRC Site Inspector Document Control Desk - NRC

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