ML18093B456

Revised Application for Amends to Licenses DPR-70 & DPR-75, Changing Changing Tech Spec 3.6.3 Re Containment Isolation Valves & Associated Limiting Condition for Operation

ML18093B456
Person / Time
Site:	Salem
Issue date:	02/15/1989
From:	MILTENBERGER S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18093B457	List: ML18093B456 ML18093B458
References
NLR-N89011, NUDOCS 8902230022
Download: ML18093B456 (2)

Text

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 and Chief Nuclear Officer FEB 1 5: 1989 NLR-N89011 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SUPPLEMENT TO REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES DPR-70 AND DPR-75 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 On November 27, 1985, Public Service Electric and Gas Company (PSE&G) submitted a license change request (LCR 84-22) to change Appendix A to Facility Operating License Nos. DPR-70 and DPR-75 to amend Technical Specification 3.6.3, Containment Isolation Valves, for Salem Units 1 and 2. The LCR consisted of a modification of the wording in the Limiting Condition for Operation (LCO) as well as changes in the containment isolation valve table (Tech. Spec. Table 3.6-1). After an extended review, the NRC staff reviewers concluded in 1987 that the LCO wording change was unacceptable.

The reviewers also concluded that the containment isolation valve table modification was acceptable with one exception.

PSE&G had included two containment outboard series isolation valves in the table (CC117 and CC118, Component Cooling to the Reactor Coolant Pumps) with the intention of using either one or the other of these outboard valves as the isolation valve for a particular containment penetration.

The NRC staff reviewers stated that only the valve which is closest to the containment (CC118) should be included in Tech. Spec. Table 3.6-1. In order to gain approval of this license change request, PSE&G is resubmitting the requested change as a change only to the containment isolation valve table. Valve CC117 has been removed from Tech Spec Table 3.6-1 for both Salem Units 1 and 2. The modified Table 3.6-1 is attached to this letter in its entirety.

This change is more conservative than that originally submitted and should not require additional staff review for its implementation.

The staff has indicated tpat this LCR would be approved if the aforementioned changes are made.

Document Control Desk 2 FEB 1 5 1989 PSE&G requests expedited approval of this modified LCR so that another change to Tech Spec 3.6.3 may be submitted for staff review in the near future. This future license change will involve the addition of an LCO action statement which will address containment penetrations with only one isolation valve. The need for this change was prompted by the NRC Senior Resident Inspector for the Salem units and is being tracked as an NRC Unresolved Item (272/311/88-14-01) until its resolution.

Pursuant to 10CFR170.21, a check in the amount of $150.00 was enclosed with the original submittal of LCR 84-22 on November 27, 1985. In accordance with lOCFR50.91(b)

(1) a copy of this amendment request supplement has been sent to the State of New Jersey. Your cooperation in this matter is appreciated.

Should you have any further questions with regard to this submittal, please do not hesitate to contact us. Attachment c Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Sincerely, Mr. w. T. Russell, Administrator Region I Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 NLR-N89011