05000219/LER-1981-034, Forwards LER 81-034/03L-0.Detailed Event Analysis Encl

Forwards LER 81-034/03L-0.Detailed Event Analysis Encl

ML20037D699
Person / Time
Site:	Oyster Creek
Issue date:	08/21/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20037D700	List: 05000219/LER-1981-034, Forwards LER 81-034/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-034-03, /03L-0:on 810722,control Rod Configuration Resulted in Peaking Factor of 110% of Allowable Limit. Apparently Caused by Personnel Error & Procedural Inadequacy in Review of Control Rod Configuration Instructions
References
NUDOCS 8108310107
Download: ML20037D699 (3)

LER-1981-034, Forwards LER 81-034/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981034R00 - NRC Website

text

.

l.6A OYSTER CREEK NUCLEAR GENERATING STATION ihiwI

]

2 ^} '

(609)693-6000 P.O BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 August 21, 1981 gpjj.

Mr. Boyce H. Grier, Director f

' ~ a 1981

• Office of Inspection and Enforement

/.

o Region I United States Nuclear Regulatory Camission

• "cW"awxAtod 5#

631 Park Avenue t

King of Prussia, Pennsylvania 19406

{//

Dear Mr. Crier:

-/-

SUBJECT: Oyster Creek Nuclear Generating Statjon Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-34/3L This letter forwards three copies of a Licensee E s t Report to report Reportable Occurrence No. 50-219/81-34/3L in ca pliance with paragraph 6.9.2.b.3 of the Technical Specifications.

Very truly yours,

/

b

. T. Carroll, Jr.

Acting Director Oyz er Creek JIC:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforement United States Nuclear Regulatory Cm mission Washington, D.C.

20555 G' s,N Director (3)

Office of Management Information and Program Control

/

United States Nuclear Regulatory Cm mission

///

Washington, D. C. 20555 NRC Resident Inspector (1)

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

8108310107 810821 PPM ADOCK 05000219 G

PDR

9 OYSTER CPEEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-34/3L Report Date August 21. 1981 Occurrence Date July 22, 1981 Identification of Occurrence Violation of Technical Specifications in that an inadequacy in the implenentation of administrative controls led to operation in a mode which could lead to a reduction of the margin of safety provided in the fuel clar1rling integrity safety limit when the peaking factor was at 110% of its allowable limit.

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 plant was in steady state operation at 62 percent power.

Plant Parameters at the time of the occurrence are:

Power:

Core 107127t Electrical 280 MWe 4

Flow:

Recirculation 11.3 x 10 p Feedwater 3.81 x 106 lb/hr Description of Occurrence On July 22, during a load reduction after failure of Traveling Screens 1 and 2 and the renoval of Circulating Pmp 1-1 fran service, the control rod configura-tion resulted in a peaking factor that was 110% of its allowable limit. When this result became available fran the plant process cmputer, actions were already underway to return the control rod pattern to its steady state con-figuration.

Apparent Cause of Occurrence l

The apparent causes of this occurrence are attributed to personnel error and l

procedural inadequacy in the review of control rod configuration instructions l

for off-hours load maneuvers. The wrong group of control rods was specified for l

insertion.

l l

Reportable Occurrence Page 2 Report No. 50-219/81-34/3L Analysis of Occurrence g

Technical Specifications Section 2.1.A.2 specifies Safety Limits for combinations of core thermal power and recirculation flow for total peaking factor nultiplier greater than unity. Under conditions occurring during the event, the Safety Limit for core thermal power at the specified recirculation flow was approximately 1610IWt. 'Ihe peak core thermal power during the event was approximately 1059 IWt. The safety significance of this event is considered to be minimal since none of the limits on the thermal hpiraulic variables assuring integrity of the fuel cladding were approached. In nadition, tirse actions which subsequently increased core power, reduced the peaking factor to 66 percent of the allowable limit.

Corrective Action

A revision to Procedure 1001.22 has been initiated as a resul'

' this occurrence which requires that prior to issue, written instructions for control rod maneuvers be independently reviewed. This should reduce the possibility at this situation will recur.

Failure Data Not applicable.