ML18101A288

Application for Amends to Licenses DPR-70 & DPR-75,changing LCO 3/4.4.4 by Adding Phrase Capable of Being Powered from Emergency Power Supply to LCO Statement

ML18101A288
Person / Time
Site:	Salem
Issue date:	10/11/1994
From:	Hagan J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LCR-93-28, NLR-N94149, NUDOCS 9410240065
Download: ML18101A288 (8)

Text

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Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations OCT 111994 NLR-N94149 LCR 93-28 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 The proposed request changes the Limiting Condition for Operation (LCO) 3/4.4.4 (for both units) by adding the phrase "capable of being powered from an emergency power supply" to the Limiting Condition for Operation statement. This request also proposes to change the frequency of surveillance requirement 4.4.4.2 (for both units) from 92 days to every refueling outage. As discussed in Attachment 1 to this letter, PSE&G's conclusion is that granting this request would not involve a significant hazards consideration. Attachment 2 contains the Technical Specifications marked up pages.

Upon NRC approval of this proposed change, PSE&G requests that the amendment be made effective on the date of issuance, and to be implemented within sixty (60) days to provide sufficient time for associated administrative activities.

Sincerely, 0 . .. n n ~'! r)

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OCT 11 7994 Document Control Desk 2 NLR-N94.149 Attachment (2)

C Mr. L. N. Olshan, Licensing Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. S. Marschall (S09)

USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Kent Tosch, Manager, VI New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

NLR-N94149 LCR 93-28 STATE OF NEW JERSEY SS.

COUNTY OF SALEM J. J. Hagan, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit No. 1, are true to the best of my knowledge, information and belief.

Subscribed and Sw o be~me this '7 da£ C'e- , 1994 j& j~_,,_ ~,N4 BARBARA A. POWELL NOTARY PUBLIC OF NEW JERSEY My Commission expires on ~~~~~~DlJ-llKWw=l~D~#~21~6~03~2~3~~~

My comission Expires Dec. 2, 1998

NLR-N94149 ATTACHMENT 1 LCR 93-'28 I. DESCRIPTION OF THE PROPOSED CHANGES IA Proposed change to Limiting Condition for Operation (LCO) 3/4.4.4 (for both units)

The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92% indicated level), and at least two groups of pressurizer heaters each having a capacity of 150 kw and capable of being powered from an emergency power supply.

IB Proposed change to surveillance requirement 4.4.4.2 (for both units)

The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once each refueling outage.

II. REASON FOR THE PROPOSED CHANGES IIA The proposed change to LCO 3/4.4.4, as described in section IA above, is intended to clarify all requirements needed to consider the Pressurizer operable. The proposed change is consistent with NUREG 1431, Standard Technical Specifications Westinghouse Plants, issued on September 1992.

IIB The proposed change to surveillance requirement 4.4.4.2 is consistent with guidance of NUREG 1366 (Improvements to Technical Specifications Surveillance Requirements, published December 1992), and Generic Letter 93-05 (Line-Item Technical Specifications improvements to Reduce Surveillance Requirements for Testing During Power Operation, issued on September 27, 1993)

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• NLR-N94149 ATTACHMENT 1 LCR 93-'28 III.JUSTIFICATION AND EVALUATION OF THE SAFETY SIGNIFICANCE AND POTENTIAL CONSEQUENCES OF THE REQUEST IIIA The proposed change clearly states that the required heater group must be capable of being powered from an emergency power supply.

As presently written, the LCO does not include this requirement as part of the LCO itself. Consequently, the Pressurizer could be considered operable without having the capability of powering the required heater group from an emergency power source, as intended by the basis of the Technical Specifications and clearly stated in LCO's Action statement. ACTION (a) partially states that with an inoperable emergency power supply, operation may only continue for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Therefore, the proposed change will correctly relocate the operability requirement to the LCO statement rather than in its action statement.

IIIB As stated in the NUREG 1366 (Improvements to Technical Specifications Surveillance Requirements, published December 1992), most pressurizer heaters are in constant use, both the variable and to some extent the back-up heaters. In additon, the pressurizer heaters have a history of being reliable, and the purpose of this surveillace requirement is to demonstrate that the capacity of the heaters has not degraded. Therefore, based on the heater reliability the 92 day surveillance frequency requirement seems to be excessive.

The Salem Station Pressurizer heaters are electric immersion heaters. The pressurizer has seventy eight (78) vertically mounted immersion heaters. The total heater capacity of 1800 KW is divided among the one (1) variable group (415KW) and two (2) backup groups {21/11 group - 415KW and 22/12 group - 969 KW).

Variable control heaters are used during steady state operations to compensate for ambient heat losses in the pressurizer and the continuous bypass spray flow. The backup group heaters are used during initial heatup (bubble drawing) coming from refueling outages and during reactor coolant system transients to aid the variable heaters. The design of the Salem Station Pressurizer heaters is identical to that described in the NUREG, and the extension of the surveillance requirement is a recognized enhancement and assurance to the continued reliability of the pressurizer heaters.

NLR-N94149 ATTACHMENT 1 LCR' 93-"28 IV. DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The discussion below applies to both proposed changes.

This proposed Amendment request:

1. Does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The request (both proposed changes) does not change any assumption or parameter assumed to function in any of the design/licensing basis analysis.

The proposed change as described in section IA merely relocates the requirement to supply emergency power to the required heater group from the action to the LCO statement.

The change as described in section IB does not eliminate the surveillance requirement, but extends its frequency from 92 days to once per refueling outage in accordance with NRC recommendation. The design of the Salem station Pressurizer heaters is identical to that described in the NUREG 1366 (Improvements to Technical Specifications Surveillance Requirements, published December 1992), and Generic Letter 93-05 (Line-Item Technical Specifications improvements to Reduce Surveillance Requirements for Testing During Power Operation, issued on September 27, 1993), and the extension of the surveillance requirement is a recognized enhancement and assurance to the continued reliability of the pressurizer heaters.

Based upon the above, PSE&G concludes that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes do not introduce any design or physical configuration changes to the facility which could create new accident scenarios.

NLR-N94149 LCR' 93-*28 ATTACHMENT 1

3. Does not involve a significant reduction in a margin of safety.

As stated in response to question number 1 above, the request does not change any assumption or parameter assumed to function in any of the design/licensing basis analysis. One change merely relocates a requirement from one section of the LCO to another, and the second change incorporates the recommendations and enhancements as stated in NUREG 1366 and GL 93-05.

Consequently, PSE&G concludes that the change does not involve a significant reduction in any margin of safety.

NLR-N94149 ATTACHMENT 2

,Lc~**93...:*2a Insert A The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92%

indicated level), and at least two groups of pressurizer heaters each having a capacity of 150 kw and capable of being powered from an emergency power supply.

Insert B The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once each refueling outage.