ML18093A757

Forwards Design Memo S-C-M200-NDM-0610-0 & Results of Review by Fire Area & Include Affected Cables & Shutdown Equipment as Well as Alternate Shutdown Options,In Response to Unresolved Item 50-311/87-29-08 Re App R Compliance

ML18093A757
Person / Time
Site:	Salem
Issue date:	03/18/1988
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18093A759	List: ML18093A757 ML18093A760
References
NLR-N88046, NUDOCS 8803300210
Download: ML18093A757 (3)

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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Vice President -

Nucle~r,Ope_rations MAR 1 B 1988 NLR-N88046 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

INSPECTION REPORT NO. 50-311/87-29 APPENDIX R COMPLIANCE SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Unresolved Item 50-311/87-29-08, contained in the subject Inspection Report required the submission of the conclusions of a study verifying the implications of the breaker relay configuration during the September 1987 inspection. The results of the PSE&G study (copy attached) documents the condition of Salem Unit 2 at the time of the NRC Appendix R Inspection 311/87-29 relative to breaker coordination as required by Appendix R.

This study is not representative of the current configuration of the plant. A number of modifications have been made as detailed in our submittals of October 16, 1987 and December 10, 1987.

PSE&G's evaluation was performed by identifying all safe shutdown and associated circuit power cables in a given fire area throughout the plant. Once the circuits for a fire area were identified, they were reviewed to determine the level of protection available as defined by Appendix R (coordination, wrap, separation, etc.). Where associated circuits were not protected, the shutdown model was reviewed to determine impact on the ability to shutdown the station in the event of a fire in the fire area. PSE&G Design Memo S-C-M200-NDM-0610-0 (Attachment 1) describes in further detail the methodology used in this study.

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Document Control Desk 2 MAR 18 1988 The tables in Attachment 2 summarize the results of this review by fire area and include affected cables and shutdown equipment as well as alternate shutdown options. The evaluation does identify areas where proper protection of circuits was not provided prior to September 1987. In those areas, the report defines the compensatory actions that the operators would take to mitigate the consequences of a fire and safely bring the plant to safe shutdown. As a result of breaker coordination, there was no instance where the plant could not be safely shutdown by restoring electrical equipment, or by using alternate equipment located outside the fire area.

In addition to the breaker coordination review and as a result of this study, fire area 1(2)FA-AB-84A is identified as an area where there is an impact on safe shutdown of the plant. This is due to a misrouted alternate shutdown cable discovered during this review. The alternate shutdown cable provides a source of control and field flashing power for the diesel generators when employing alternate shutdown. An hourly firewatch has been in this area since March 1987 for other reasons. The misrouted cable will be the subject of a future LER. This is a separation concern and is not related to breaker coordination.

As discussed at the Enforcement Conference on February 12, 1988, the enclosed report completes the information required to support your final actions, with respect to the Appendix R inspection.

Sincerely, Attachments

Document Control Desk 3

• ~ 18 1988 C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628