05000219/LER-1981-032, Forwards LER 81-032/03L-0.Detailed Event Analysis Encl

Forwards LER 81-032/03L-0.Detailed Event Analysis Encl

ML20010C706
Person / Time
Site:	Oyster Creek
Issue date:	08/12/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010C707	List: 05000219/LER-1981-032, Forwards LER 81-032/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-032-03, /03L-0:on 810713,monthly Channel Check of Safety & Relief Valve Position Monitoring Sys Not Performed within Required Period.Caused by Lack of Administrative & Procedural Controls.Sys Tested
References
NUDOCS 8108200330
Download: ML20010C706 (3)

LER-1981-032, Forwards LER 81-032/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981032R00 - NRC Website

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OYSTER CREEK NUCLEAR GENERATING STATION

$7dM3',*',2'Cd7' (609)693-6000 P.O BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 w,wmm.s ;a.-

Atxr, t 12,1981

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• s Mr. Boyce H. Grier, Director

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Office of Inspection and Enforcement p%%'6 j g IS8lg Region I United States Nuclear Regulatory Ca: mission

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King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-32/3L This letter fm vards three copies of a Licensee Event Report to report Reportable Occurrcnce No. 50-219/81-32/3L in ccupliance with paragraph 6.9.2.b.3 of the 'Itchnical Specificadons.

Very truly yours, f

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/ v ' /] L Lit J. T. Carroll, Tr Acting Director ster Creek JIC:dh Enclosures cc: 0.irector (40 copies)

Offi of Inspection arxl Enfcrcarnt United States Nuclear Regulatory Ccrmission Washingtan, D.C.

20555 Director (3)

Office of Management Info 1mation gg and Program Control y

United States Nuclear Fegulatory Catmission

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Washington, D. C. 20555 j,//

NRC Resident Insier (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

8108200330 810812 PDR ADOCK 05000219 S

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. OYSTER CREEK NUCIEAR GENERATING STATION Forked River,!#N Jersey 08731 Licensee Event Report Reportable Occurrence No.- 50-219/81-32/3L Report Date i.

August 12, 1981 Occurrence Date July 13, 1981 Identification of Occu m.

%e nonthly channel check of the accident nonitorirg instranentation required by cection 4.13.A.1 of the Technical Specifications was not performed within the specification period.

Wis event is considered to be a reportable occurrence as defined in the Tedinical Specifications, paragraph 6.9.2.b.3.

Cbnditions Prior to Occurrence

% e plant was operating at steady state power.

Major Plant Parameters Power:

Reactor 1448 IWt Generator 395 M4e 4

Flow:

Recirculation 10.7 x 10 p Feedwater 4.54 x 106 lb/hr Description of Occurrence On May 13,1981,' the official controlled copy of Anendment #54 to the Technical

'. Specifications was received, and inclubd in the Amendment was section 4.13.

mis section mquires a channel check of r.se safety and relief valve position nonitoring systen once every 31 days. During this period, due to the physical movenent of our Document Chntrol Center fran one location to another, our procedures governing the icsuance of Technical Specification changes were un-s workable. Consequently, the distribution of the controlled copies of Ameht

1. 54 to bookhold3rs was delayed until June 28, 1981.

Since Amendment #54 was effective as of the date of issuance, May 8, the surveillance was required by June 15; however, due to tie delcy in the internal issuance of the Anendment, the required surveillance was not performed until July 13, 1981.

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- t Reprtable Occurrence Page 2 Report No. 50-219/81-32/3L Apparent Cause of Occurrence q

W e cause of the occurrence was attributed to lack of the proper administrative and procedural controls.

Analysis of Occurrence Were are two systens used to indicate the positions of the safety ard relief valves. %e primary system, which is the acoustic monitoring systan, uses -

acceleraneters to detect valve disc novanent. te secondary systen uses a tMmmple on the discharge side.of each valve, and any flow past the valve would be indicated by a nuch higher tarperature than usual.

%e acoustic monitoring systen is desigrtd to give a positive indication of the valve position. Se thermoa;1uples may not always give a positive indication of valve position (i'.e., a valve opens and then closes, but the discharge renains hot). Were are two alarms in the Control Iban associated with relief and safety valve position. One is part of the acoustic nonitoring systen and indicates that one of the safety or relief valves is not closed. W e other is only for the electrcmatic relief valves, and it indicates that the solenoid is energized (this is not a positive indication of valve position). We safety significance is minimized by the fact that the acoustic nonitoring systan was demonstruted to be operable.

Corrective Action

Inmediate corrective action was to conduct a channel check of1the acoustic ana tauperature nonitoring systems to serify cperability. Currently, Engineering is., developing procedures for the channel check and for the channel calibration.

These procedures will be incorporated into the Master Surveillance Schedule to insure the Technical Specifications testing frequency requirenents are met.

Since this event, an administrative assistant in the Licensing hpartment has been charged with the responsibility of distributing controlled distribution

- License Amendments which will prevent this type of occurrence in the future.

Additionally, under the reorganization plan, new procedures are currently being developed to provide guidance on timely. dissemination of' license changes and-l other regulatory documents.

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