ML18086A890

Informs That,Based on New Info by Westinghouse Indicating That 75% Power Test Will Not Produce Significant Info or Measurable Carryover,Moisture Carryover Test Will Not Be Performed.Westinghouse Recommendation Encl

ML18086A890
Person / Time
Site:	Salem
Issue date:	08/19/1981
From:	MITTL R L Public Service Enterprise Group
To:	VARGA S A Office of Nuclear Reactor Regulation
References
NUDOCS 8108260096
Download: ML18086A890 (4)

Text

--' .* e Public Service Electric and Gas Company 80 Park Plaza, T16D Newark, N.J. 07101 201/430-8217 Robert L. Mitt! General Manager -Licensing and Environment August 19, 1981 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:

Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:

INITIAL TEST PROGRAM NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Section 13.4 of the Salem FSAR requires, in Table 13.4-1 Sheet 3, that testing for steam generator moisture carryover be performed at 75%, 90%, and 100% power level. New mation provided by Westinghouse, based on experience with other series 51 steam generators, indicates that the 75% power test will not produce any significant information or measurable carryover.

We therefore wish to inform you that, based upon this new information, the 75% and 90% power level steam generator moisture carryover test for Salem Unit #2 will not be formed. This test will be performed as specified in the attached Westinghouse letter. Section 2.C.(4) of Facility Operating License DPR-75 quires that PSE&G obtain prior NRC approval for modifying the post-fuel-loading initial test program, if a major fication is involved.

Based on telephone conversations with Mr. Gary Meyer of the NRC staff, it was determined that this test is not identified as essential in Chapter 13 of the FSAR and thereby does not represent a major modification of the initial test program requiring prior NRC approval, as defined in Section 2.3.(4) (a) of Facility Operating License DPR-75. --8108260096 a fr>a 19 '" PDR ADOCK 05000311*

P PDR The Energy People Director of Nuclear Reactor Regulation 8/19/81 Should you have any questions in this regard, do not tate to contact us. Very truly yours, CC: Mr. Leif Norrholm Senior Resident Inspector FA20 1/2 I ' * . .:. . £..=:.,{,*

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