ML18100B178

Notice of Violation from Insp on 940328-0520.Violation Noted:Failure to Perform Written Safety Evaluation for Change to Plant

ML18100B178
Person / Time
Site:	Salem
Issue date:	06/29/1994
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18100B177	List: ML18100B178 ML18100B180
References
50-272-94-07, 50-272-94-7, 50-311-94-07, 50-311-94-7, NUDOCS 9407070083
Download: ML18100B178 (2)

Text

NLR-N94139 APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating Station Units 1 and 2 Docket Nos: 50-272 50-311 License Nos: DPR-70 DPR-75 During an NRC inspection conducted on March 28 through May 20, 1994, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix c, the violation is listed below:

Part 50 of Title 10 of the Code of Federal Regulations, Section 50.59{b) (1), requires that the licensee shall maintain records of changes in the facility and of changes in procedures made pursuant to this section, to the extent that these changes constitute changes in the facility, as described in the safety analysis report or to the extent that they constitute changes in procedures as described in the safety analysis report.

These records must include a written safety evaluation, which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed safety question.

Figure 8.3-4, "460V. Vital Buses One Line - Unit 1, 11 of the Salem Updated Final Safety Analysis Report (FSAR) identified that the "1A-460V Vital Bus Transformer" as rated at 11 1000 'KVA."

Contrary to the above, no written safety evaluation was performed for a change to the plant, as described in the UFSAR when, on or before May 18, 1994, the 1A-460V Vital Bus Transformer, rated at 1000 kVA, was replaced with a transformer rated at 1333 kVA.

This is a Severity Level IV violation {Supplement I).

NLR-N94139 ATTACHMENT I PSE&G RESPONSE PSE&G does not dispute the violation.

The root cause of this violation has been attributed to an improper interpretation of the administrative program for preparing 10CFR50.59 Safety Evaluations, resulting in a failure to follow procedures.

CORRECTIVE STEPS TAKEN

1.

A 10CFR50.59 Safety Evaluation has been prepared for the design modification in question and has determined that an Unreviewed Safety Question was not involved.

CORRECTIVE STEPS TAKEN TO PREVENT RECURRENCE

1.

A letter (STN-94-0167) was issued to all Nuclear Engineering managers and functional supervisors and to the station Technical Managers.

This letter, which was dated June 13, 1994, reiterated the requirement to perform a complete 10CFR50.59 Safety Evaluation for changes to UFSAR drawings, figures, or tables.

This requirement will be rolled down to all personnel charged with 10CFR50.59 review and Safety Evaluation preparation.

2.

The implications of this violation have been incorporated into the 10CFR50.59 lesson plan.

3.

The engineers involved in the preparation of the 10CFR50.59 Safety Evaluation have been counseled regarding the proper interpretation of the administrative program for preparing 10CFR50.59 Safety Evaluations.

DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED PSE&G believes that adequate controls are in place to preclude a similar violation.

PSE&G is in full compliance.

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