05000219/LER-1981-059, Forwards LER 81-059/03L-0.Detailed Event Analysis Encl

Forwards LER 81-059/03L-0.Detailed Event Analysis Encl

ML20039C293
Person / Time
Site:	Oyster Creek
Issue date:	12/17/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20039C294	List: 05000219/LER-1981-059, Forwards LER 81-059/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-059-03, /03L-0:on 811116,APLHGR Not Checked for Type Iiif Fuel During Daily Core Checks.Caused by Engineer Failure to Assign Alternate Core Location to Take Traveling in-core Probe Truce After Problems Arose at Current Location
References
NUDOCS 8112290187
Download: ML20039C293 (3)

LER-1981-059, Forwards LER 81-059/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981059R00 - NRC Website

text

,

GYSTER CREEK

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NUCLEAR GENERATING STATION mmu

.; ' ;j *'; 7,f, (609) 693-1951 P O. BOX 388

• FORKED HIVER

• NEW JERSEY

• 08731 Deccxnber 17, 1981 r,

s Mr. Bonald Haynes, Director 1

Office of Inspection and Enforcamnt RECEIVED 6]

N a m M amuttaengs E O Nb U

States Nuclear Regulatory C M ssion 631 Park Avenue King of Prussia, Pennsylvania 19406 m "e" g

Dear Mr. Haynes:

y SURTELT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-59/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-59/3L in canpliance with paragraph 6.9.2.b. (3) of the Technical Specifications.

Very truly yours,

/

lb&l/fl J. T. Carroll, J Acting Director ster Creek JIC:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcerent United States Nuclear Regulatory Ccrimission Washington, D.C.

20555 Director (3) s Office of Managanent Infonnation and Program Control United States Nuclear Regulatory Camlission Washington, D. C. 20555 NRC Resident Inspector (1)

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

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lc 8112290187 811217 pIl PDR ADOCK 05000219 S

PDR j

OYSTER CREEK NUCLEAR GENERATING STATICN Forked River, New Jersey 08731

' Licensee Event Report Reportable Occurrence No. 50-219/81-59/3L Report Date Occurrence Date Novenber 16, 1981 Identification of Occ e ce Violation of technical specification 4.10A, the Average Planar Linear IIeat -

Generation Rate (APLHGR) for type IIIF fuel was not checked.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b. (3).

Conditions Prior to Occurrence The p'. ant was in a stabilized operating condition with less than 1.0% change in-power level frcm the previous day. Reactor parameters at the time of the occurrence were:

Core Thennal Power: 1914.0 Mit Recirculation Flow: 151,539 gpn Reactor Pressure:

1034.8 psia Description of Occurrence During a review of the anily core check documentation on Novenber 17, 1981, as required by managenent control systen, it was dLscovered-that the APLHGR for type IIIF fuel was not checked on Novenber 16, 1981.

Apparent Cause of Occurrence hhile preparing to perfonn the daily check of the APLIIGR for type IIIF fuel, mechanical problens were encountered in attenpting to run the Traversing-In-Core-Probe detector (TlP) into location 28-49. An alternate core location was to be detennined by the responsible engineer. However, in the process of checking the thermal limits of the other fuel types, the alternate core location to check type IIIF fuel was overlooked. The cause of the occurrence is, there-fore, personnel error.

Peportable Occurrence Page 2 Report No. 50-219/81-59/3L Analysis of Occurrence Type IIIF fuel is relatively low energy fuel located at the core periphery. A review of daily core check documentation for the cmplete present operating cycle indicated that the APHIGR for type IIIF fuel has never exceeded 50% at -

steady state operations or 65% of.its limiting value during startup operations.

In addition, an analysAs, utilizing TIP data fran Novenber 15, 1981 and LPIN values fran Novenber 16, 1981, concludes that the APUlGR for type IIIF fuel on Novenber 16, 1981 was less than 50% of its limiting value. The event is, there-fore, considered minimal..

Corrective Action

The event has been reviewed with the Core Engineering group.

In aMition, a detailed review of the procedure and docmentation associated with the daily core check of thermal limits will be scheduled in the Operator Requalification Training Program.

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