ML20035A405

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Discusses Safety Insp Rept 50-219/93-80 on 930126-0202. Violation Noted But Not Cited.Temporary Procedure Change to Procedure 305 Inadequate & Resulted in Reactor Coolant Temp Increasing Above 212 F W/O Operator Knowledge of Heatup
ML20035A405
Person / Time
Site: Oyster Creek
Issue date: 03/17/1993
From: Hodges M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
References
EA-93-055, EA-93-55, NUDOCS 9303260014
Download: ML20035A405 (3)


See also: IR 05000219/1993080

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Docket No. 50-219

EA 93-055

Mr. John J. Barton

Vice President and Director

GPU Nuclear Corporation

Oyster Creek Nuclear Generating Station

P.O. Box 388

Forked River, New Jersey 08731

Dear Mr. Barton:

SUBJECT:

DEGRADED SHUTDOWN COOLING EVENT: APPARENT VIOLATION

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OF NRC REQUIREMENTS

(NRC INSPECTION REPORT 50-219/93-80)

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This letter refers to the special safety inspection conducted on January 26 - February 2,

1993, as detailed in NRC Augmented Inspection Team Repon No. 50-219/93-80. This

inspection team investigated the circumstances that led to the degradation of shutdown

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cooling at the Oyster Creek Nuclear Generating Station on January 25,1993. You reported

the event to the NRC in Licensee Event Report Number 93-002, dated February 26,1993.

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Based on the above inspection, it appears that certain of your actions were not in full

compliance with applicable NRC requirements. These actions are b.ang considered for

escalated enforcement in accordance with the " General Statement of Policy and Procedure for

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NRC Enforcement Actions" (Enforcement Policy),10 CFR Part 2, Appendix C (1992).

Accordingly, no Notice of Violation is being issued for the inspection findings at this time.

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Specifically, the temporary procedure change made to Oyster Creek Procedure Number 305,

" Shutdown Cooling," on January 22,1993, was apparently inadequate as it caused the

reactor coolant temperature to increase inadvertently above 212 degrees F without operator

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knowledge of the heatup, or completion of the required technical specification prerequisites

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for operation at the higher temperatures. This is contrary to 10 CFR 50, Appendix B,

Criterion V which requires that activities affecting quality be prescribed by documented

procedures of a type appropriate to the circumstances.

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OFFICIAL RECORD COPY G:OCLTR1.ENF

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9303260014 930317

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MAR 171993

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Mr. John J. Barton

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.An enforcement conference to discuss this apparent violation has been scheduled for

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April 2,1993. The purposes of this conference are to discuss the apparent violation, its

cause and safety significance; to provide you the opportunity to point out any errors in our

inspection report; and to provide an opportunity for you to discuss your proposed corrective

action (s). In pardcular, we expect you to address: (1) your practices and management

expectations with regard to temporary procedure changes and procedure changes which may

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constitute a change of " intent"; (2) the significance of operation during shutdown at

conditions outside the technical specification limits as described in the Licensee Event

Report; and (3) the commonality of the event described in the inspection report with previous

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violations related to annulus / core communication issues.

The conference is an opportunity for you to provide any information concerning your

perspective on the severity of the issue; the factors that the NRC considers when it

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determines the amount of a civil penalty that may be assessed in accordance with Section

V.B of the Enforcement Policy; and the possible basis for exercising discretion in accordance

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with Section V.G of the Enforcement Policy. You will be advised by separate

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correspondence of the results of our deliberations on this matter,

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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter

will be placed in the NRC Public Document Room.

Sincerely,

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Marvin W. Hodges, Director

Division of Reactor Safety

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cc-

M. Utggart, Manager, Corporate Licensing

P. Czaya, Acting Licensing Manager, Oyster Creek

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Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

State of New Jersey

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Mr. John J. Barton

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Region 1 Docket Room (with concurrences)

DRS/EB SALP Coordinator

J. Joyner, DRSS

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R. Blough, DRP

J. Rogge, DRP

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V. McCree, OEDO

A. Dromerick, NRR/PD 1-4

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F. Young, SRI, Three Mile Island

N. Dudley, SRI, Seabrook

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