ML18092B194

Forwards Unit 1 Cycle 7 Core Loading Pattern Figure 1, Identifying Changes Made to Loading Pattern as Result of Damage to Fuel Assemblies H60 & H63

ML18092B194
Person / Time
Site:	Salem
Issue date:	06/13/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Varga S Office of Nuclear Reactor Regulation
References
NFU-86-175, NUDOCS 8606240400
Download: ML18092B194 (6)

Text

,.*

Public Service Electric and Gas Company Corbin A. McNeil!, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Vice President -

Nuclear NFU 86-175 June 13, 1986 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Gentlemen:

CYCLE 7 RELOAD REDESIGN FACILITY OPERATING LICENSE DPR70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 Salem Unit No. 1 completed its sixth cycle of operation on March 21, 1986. During the reload, damage of a grid strap on each of two fuel assemblies was observed when the assemblies were removed from the core. The ID' s of these assemblies are H60 and.H63.

They fell in symmetric positions in the cycle 7 design. Two partially burned bundles CID's are F23 and F49> from the spent fuel pool replaced the two damaged bundles. One assembly was moved to improve core symmetry. These changes are included in the Salem Unit 1 Cycle 7 Core Loading Pattern Figure 1. No other changes were made to the design.

PSE&G and Westinghouse made an evaluation of the loading pattern change for Cycle 7. PSE&G concurs with the Westinghouse con-clusion that the new reload design does not change the design/

safety evaluations or conclusiqns of the original RSE.

8606240400 860613 PDR ADOCK 05000272 P PDR .

Mr. Steven A. Varga 6-13-86 Therefore, as previously stated in Reference 1, there are no unreviewed safety questions as defined by 10CFR50. 59 associated with the redesign for Cycle 7, and that an application for amendment to the Salem 1 operating license is still not required.

Sincerely, Attachments

Reference:

1. NFU 86-070, Letter from C. A. McNeill to Steven A. Varga; Cycle 7 Reload Analysis, February 10, 1986.

2. NFUVTD-WW86005-01, Reload Safety Evaluation Salem Unit 1 Cycle 7 Revision 1; Westing-house; April, 1986.

C Mr. Donald C. Fischer Licensing Project Manager Tom Kenny Senior Resident Inspector

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Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Vice President -

Nuclear June 11, 1986 NLR-N86087 Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention: Mr. Steven A. Varga, Director PWR Project Directorate #3 Division of PWR Licensing A

Dear Mr. Varga:

ASME CODE CASE N-133-2 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to request, pursuant to the requirements of 10CFR50.55a(a)(3), that the NRC approve the use of ASME Code Case N-133-2 for use in the design and fabrication of replacement valves for the Salem Units 1 and 2 service water systems. The replacement valves currently being purchased are Jamesbury Model 815L-ll-14RLMT which utilize alternate bolting material for the four bolts closest to the shaft on either valve face. The use of alternate bolting material was approved in Code Case N-133-2 and represented the only change from Code Case N-133-1. The use of Code Case N-133-1 has been approved by the NRC.

The replacement valves are of a more reliable design in that the use of Aluminum Bronze Alloy 954, as approved by Code Case N-133, is more resistant to erosion. Maintenance of these valves is also easier to accomplish resulting in greater system availability. The alternate bolting material was fabricated from Monel Alloy 400 utilizing material specification SB-164. This material combines the mechanical and material properties necessary to assure structural integrity and limit galvanic corrosion. For these reasons, PSE&G believes that the requirements of 10 CFR 50.55a(a)(3) have been satisfied and that the use of ASME Code Case N-133-2 is acceptable.

r-9606180o78 8~006001 ~7'">

. PDR ADOCK o~ PDR"'"'

P* /JD'f1 tf o

Steven A. Varga 6-11-86 Should you have any questions regarding this information, we would be happy to discuss them with you. An expeditious response to this request would be greatly appreciated.

Sincerely, C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector

I 1 * ..,.

A. Kaplan who, being duly sworn, deposed and said that (1) he is Vice President, Nuclear Operations Division of The Cleveland Electric Illuminating Company, (2) he is duly authorized to execute and file this report on behalf of The Cleveland Electric Illuminating Company and as duly authorized agent for Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company and the Toledo Edison Company, and (3) the statements set forth therein are true and correct to the best of his knowledge, information and belief.

LJ A. Kaplan Sv;arn to and subscribed before me, this 19-R~ . - -&- - day of BETHANY J. REESE Notary 19ublic - STATE OF OHIO My Commission expires 3/11/88 (Recorded in Lake County)