IR 05000219/1992002

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/92-02 on 920225

ML20198D641
Person / Time
Site:	Oyster Creek
Issue date:	05/18/1992
From:	Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 9205210099
Download: ML20198D641 (2)

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Docket No. 50-219 License No. DPR-16 Mr. John 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: INSPECTION NO. 50-219/92-02 This refers to your letter dated April 24,1992, in response to our letter dated February 25,1992. '

Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.

Your cooperation with us is appreciated.

Sincerely, Lee H. Bettenhausen, Chief Operations Branch Division of Reactor Safety cc:

M. Laggart, Manager, Corporate Licensing G. Busch, Licensing Manager, Oyster Creek Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

i K. Abraham, PAO (2) (w/ copy of letter dtd April 24, 1992)

L NRC Resident Inspector (w/ copy of letter dtd April 24,1992)

State of New Jersey (w/ copy of letter dtd April 24,1992)

OFFICIAL RECORD COPY G:CSOC9202 9205210099 920518 PDR ADOCK 05000219 h\ ' I)

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hir. John tec:

Region 1 Docket Room (with concurrences)

- hianagement Assistant, DRhf A (w/o encl)

L. Bettenhausen, DRS '

J. Joyner, DRSS E. Wenzinger, DRP R. Conte, DRS Section Chief 4B, DRP R. Lobel, OEDO -

A. Dromerick, NRR/PD l-4 F. Yciang, SRI, Three hiite Island L. Rossbach, SRI, Beaver Valley C. Sisco, DRS DRS Files (2) (w/ copy of letter dtd April 24,1992) ,

RI:DRS RI:DRS RI:DRS Sisco/dmg C nte Bettenhausen tea 05/04/92

05/4 /92 peo0515/92 OFFICIAL RECORD COPY G:CSOC9202

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l Route 9 South l Forked Rwer. New Jersey 087310388 609 971-4000 Writer's D rect D.at Number.

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April 24, 1992 i C321 92-2122 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Dear Sir:

Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 Inspection Report 92-02 Response to Unresolved Items The purpose of this letter is to respond to the unresolved items identified in inspection Report 92-02 as requestcJ by the letter transmitting the report dated February 25, 1992. Our response is attached.

If you should have any questions or require further information, please contact Brenda DeMerchant, OC Licensing Engineer at (609) 971-4642.  ;

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I ton Vi e Pre ' dent & Director ster C eek JJB/BbEM:je cc: Administrator, Region 1 /!

Senior NRC Resident Inspector .'

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Oyster Creek NRC Project Manager

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GPU Nuclear Corporation is a suoscary of General Pubhc Ut:ltties Corporaton

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AttachmenL1 Unresolved item 92-02-01_1

"There is a programmatic weakness in the implemmtation of the systems 4pproach to training indicated by the failure to develop and implement a forma' program for 0JT for nonlicensed operators and the failure to develop and ;mplement a formal E0P training for nonlicensed operators despite adequa+; job and task analysis information to support the development. These failu.es are Unresolved Item 50-219/92-02-01."

Response:

A formal continuing program description entitled "0yster Creek Non-Licensed Operator On-The-Job Training (0JT) Program" has been developed and implemented.

The . purpose of this progri.m is to ensure that non-licensed plant operating personnel possess the required job related knowledge and skills. OJT supplements non-licensed requalification training in order to broaden operator knowledge and enhance their abilities to perform assigne6 duties in a manner that promotes safe and reliable plant operations.

GPUN wishes to emphasize that an OJT effort has been a part of the non-licensed operator initial and continuing training programs since 1996, including qualification standards for adequate performance assessment of initial candidates. Formal documentation of the continuing training effort via a stand alone program description was only recently accomplished in February 1992.

Emergency operating procedure (EOP) training for the non-licensed opc ator (NLO)

continuing training program has recently been enhanced. The uNrade of the NLO job task analysis identified specific E0P tasks for inclusion into the training program. These tasks have been included in the continuing OJT program and where appropriate in combined classroom lessons with the licensed operator program.

Tnerefore, E0P training for NL0s using a systems approach to training has been developed and implemenb 1.

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Unresolved item 92-02-021 I

"The inspectora determined the prog ammatic approach the licensee has taken to develop, implement, and maintain h;gh quality E0Ps and support procedures is weak. This weakness is Unresolved Item 50-219/92-02-02."

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P_eignse:

i Subsequent to the subject inspection, an E0P committee was formed with the full

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support of inanage eat, to oversee and coordinate the various requirements associated with the plant ECPs. This committee will be responsible for ensuring that the quality of the E0?s is maintained, both in a technical senst a.4 from the aspect of oparator usability.

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The five primary groups represented include:

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Plant Engineering, Operations, Plant Training, Safety Analysis / Plant Control and Human Engineering. Some of the l functions that this committee will be tasked with include:

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C321-92-2122 Attachment 1 Page 2

• Technical review / approval of all proposed changes to the E0Ps.

• Verification that all changes to tha E0Ps are in accordance with the BWROG Emergency Procedure Guidelines and the plant Writers Guide for E0Ps.

• Validation of the E0Ps and any changes to the E0Ps, both on the simulator and by walkthrough: in the plant, to assure usability.

• Maintenance of tha techn h., ' ,1s for the E0Ps.

Thit committee has met twice and is planning to meet once or twice a month as needed. We are pleased and encouraged by the results of the meetings which demonstrate the advantages of a " team approach" to the problems and concerns generated by the E0Ps. It is also expected that ".e groups represented will f acilitate the transition V operator training on the procedures to our new simulator.

The following is our anticipated schtduie for implementing our E0P support program.

The E0P control document (Procedure 107.4) which will contain our validation and verification program. criteria on evaluating if plant modifications impact the E0Ps, and a description of the E0P committee identified above is expected to be finaitzed by the end of November 1992.

• The flow chart writers guide is expected to be finalized by the end of the second quarter 1992.

• Validation of the E0P flowcharts and support procecu"es is expected

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to begin by_ the end of November 1992, and will continue after arrival of the simulator on site. The compl- 'on date of this process ir dependent upon the date the simu. .;r is ready for training.

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