05000277/LER-1981-010, Forwards LER 81-010/03L-0

Forwards LER 81-010/03L-0

ML20008E954
Person / Time
Site:	Peach Bottom
Issue date:	03/02/1981
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20008E955	List: 05000277/LER-1981-010, Forwards LER 81-010/03L-0 05000277/LER-1981-010-03, /03L-0:on 810127,drywell Radiation Monitor Found Out of Svc During Full Operation.Caused by No Sample Flow Through Sys Due to Manual Sample/Purge Valve Dislodged from Normal Sample Position.Valve Returned to Position
References
NUDOCS 8103100623
Download: ML20008E954 (2)

LER-1981-010, Forwards LER 81-010/03L-0

Event date:
Report date:
2771981010R00 - NRC Website

text

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PHILAD ELPHIA ELECTRIC COM PANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 1215) 841 4o00 March 2, 1901 sg;-

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Mr. Bo yce H. Grier, Director Of fice of Inspection and En fo 2ement 3

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M y,,,3, S,a.e ll g ( # Oj Region I US.'luclear Regulatory Commission M

'N j.,;;ff' 631 Park Avenue King of Prussia, PA 19uoS

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Dear Mr. Grier:

SUBJECT:

LICENSEE EVENT REPORT MARRATIVE DESCRIPTION

Reference:

Docket No. 50-277 Report No. :

2-81-1073L Report Date:

March 2, 1931 Occurrence Date:

January 27, 1981 Facility:

Peach Bottom-Atomic Power Station RD #1, Delta, PA 17314

.i Technical Specification Reference:

Technical Specification 3.6.C.2 states in part that "Both

- the sump and air samplinS systems shall be operable during reactor power operation."

'Descriotion of the Event During surveillance testin3 with the unit at po wer, two drywell. sample line isolation valves (SV-2571A and-SV-2979C) were found to not close fully, as reported in LER 2-31-03/3L..Two additional sample isolation-valves (SV-2978D and SV-2978E) were fo und to have. failed. closed due to open circuits in the coils.

Valves SV-2978C, SV-2973D, and SV-297AE are isolation valves in the three lines from. which the drywell radioactive gas monitor

- normally obtains sample flow. 'Since flow was not' maintained to 3

81081004,23

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Page 2 the radioactive gas monitor ' rom these lines, the alternate f

source of drywell radioactive gas monitor sample flow (the drywell containment atmospheric dilution (CAD) system) was placed in service.

However, no sample flow was obtained when this system was placed in serv ice.

Subsequent investigation revealed that a manual sample / purge valve on the drywell radiation monitor sample line was in mid-position, thereby preventing radiation monitcr' flow.

Probable Consecuence of the Occurrence Drywell leakage is monitored by two separate means; the drywell floor ' drain and equipment drain sump pump out system, and the drywell radiation monitor.

The sump pump out system remained operable during the period.when the rad monitor was out of serv ice, and no increase in leakage was observed during this period.

Cause of the Event

The cause of the. event was determined to have been accidental movement of the sample / purge valve by the person pe r fo rm ing the surveillance test.

The throw valve handle was brushed against while the person was reaching beyond the valve to operate another valve.

Corrective Actions!

The sample / purge valve was inmediately repositioned to-the normal position to provide sample flow using the CAD' system.

The surveillance test during which the valve was accidentally moved is being revised to verify the position of the manual sample / purge valve upon completion of the appropriate section of the test.

Very truly yours,

h0 M.

J.

Cooney Superintendent Generation Division --Nuclear At tac hm en t ec: Director, NRC - Office of Inspection and Enforcement Mr. Norman M.

Haller, URC Of fice of Management ?.

Program Analysis V

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