ML18107A533

Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2

ML18107A533
Person / Time
Site:	Salem
Issue date:	09/13/1999
From:	Salamon G Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N000420, NUDOCS 9909210280
Download: ML18107A533 (4)

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Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 131999 LR-N990420 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NOTIFICATION OF INTENT TO UTILIZE ASME CODE CASE N481 SALEM GENERATING STATION, UNITS 1AND2 DOCKET NOS. 50-272 AND 50-311 This letter provides notification of Public Service Electric and Gas Company's (PSE&G's) intent to utilize ASME Code Case N-481 (see attached) during the second inservice inspection interval at the Salem Generating Station, Unit Nos. 1 and 2. ASME Code Case N-481, "Alternative Examination Requirements for Cast Austenitic Pump Casing,Section XI, Division 1" was accepted for use by the NRC in Regulatory Guide 1.147, Revision 12, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1."

PSE&G contracted with Westinghouse to provide a plant specific report, "A.

I Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of the Salem Generating Station Units 1 and 2", WCAP 14583.

This plant specific report, in concert with the Westinghouse Generic Basis contained in WCAP 13045, provides the basis for use of Code Case N-481 at the Salem Generating Station. PSE&G has reviewed and accepted these Westinghouse reports.

In a letter dated April 13, 1993, the NRC specified that, for a plant to implement Code Case N-481, the licensee should inform the NRC of the intent to invoke the code case and retain the analysis required by the code case on site for NRC audit. The Westinghouse reports are available onsite for NRC review and audit.

Should you have any questions regarding this request, please contact Mr. C. E.

Manges, Jr. at 856-339-3234.

Sincerely, G. Salamon Manager - Licensing Attachment

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-PDR ADOCK*05000272 G PDR.

The power is in your hands.

95-2168 REV. 6/94

Document Control9sk SEP.131999 LR-N990420 C Mr. H. J. Miller, Administrator - Region I

• U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 8B1 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector- Salem (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. 0. Box 415 Trenton, NJ 08625

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Attachment Code Case N481

CASE N-481 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: March 5, 1990 See Numerical Index for expiration and any reaffirmation dates.

Case N-481 (c) Perform a VT-3 visual examination of the in-Alternative Examination Requirements for Cast ternal surfaces whenever a pump is disassembled for Austenitic Pump Casings maintenance.

Section XI, Division 1 (d) Perform an evaluation to demonstrate the safe-ty and serviceability of the pump casing. The evalu-Inquiry: When conducting examination of cast aus- ation shall include the following; tenitic pump casings in accordance with Section XI, (1) evaluating material properties, including Division 1, what examinations may be performed in fracture toughness values; lieu of the volumetric examinations specified in Ta- (2) performing a stress analysis of the pump cas-

!lle IWB-2500-1, Examination Category B-L-1, Item ing; B12.10? (3) reviewing the operating history of the pump; (4) selecting locations for postulating flaws; Reply: It is the opinion of the Committee that the (5) postulating one-quarter thickness refere~ce following requirements shall be met in lieu of per- flaw with a length six times its depth; forming the volumetric examination specified in Ta- (6) establishing the stability of the selected flaw ble IWB-2500-1, Examination Category B-L-1, Item under the governing stress conditions; B12.10: (7) considering thermal aging embrittlement (a) Perform a Vf-2 visual examination of the ex- and any other processes that may degrade the pro-terior of all pumps during the hydrostatic pressure perties of the pump casing during service.

test required by Table IWB-2500-1, Category B-P. (e) A report of this evaluation shall be submitted (b) Perform a Vf-1 visual examination of the ex- to the regulatory and enforcement authorities having ternal surfaces of the weld of one pump casing. jurisdiction at the plant site for review.

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