Text

Forwards Response to Request for Addl Info Re NRC Bulletin 88-002, Rapid Propagating Cracks in Steam Generator Tubes.
	ML18094B256
Person / Time
Site:	Salem
Issue date:	01/19/1990
From:	Labruna S; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	IEB-88-002, IEB-88-2, NLR-N90019, NUDOCS 9001310521
	Download: ML18094B256 (8)
	v • d • e

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Public Service Electric and Gas

Company

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Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609-339-4800 Vice President - Nuclear Operations JAN 1 9 1990 NLR-N90019 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR ADDITIONAL INFORMATION (RAI)

BULLETIN aa~o2, RAPID PROPAGATING CRACKS IN S/G TUBES SALEM GENERATING STATION, UNITS 1 & 2 DOCKETS NO. 50-272 & 50-311 Public Service Electric and Gas Company (PSE&G) hereby provides the attached response to your letter dated November 17, 1990.

Your letter transmitted the subject RAI concerning our letters dated April 5, and July 29, 1989 which transmitted detailed analyses for steam generator tube vibration fatigue.

Westinghouse has been consulted regarding this matter and has helped with the preparation of this response.

Your -letter requested a response within sixty days and this transmittal satisfies that request. Sho~ld you have any questions regarding this response, please do not hesitate to contact us.

Sincerely, Attachment 9001310521 900119 fC/3 PDR ADOCK 05000272 C:: F**:cic: 'I 1

Document Control Desk 2

NLR-N90019 JAN 1 g 1990 c Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RAPID PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES NRC BULLETIN 88-02: SALEM UNITS 1 & 2 Salem Unit 1, S/G 2 Tube R9C60 In response to a request for additional information regarding the evaluation of tube R9C60 in Salem Unit 1 SG2: Westinghouse has performed a detailed re-evaluation of the AVB positioning used as the basis for the flow peaking model of that tube.

As a result of the re-evaluation a n~-.;;--t.est ge~metry, now identified as configuration 8L, has been developed. This configuration is shown in Figure 1, which is attached. The resultant flow peaking factor with th'is geometry has been determined to be 1.48: as compared to ~n allowable value of 1.37. Based _on this information, PSE&G agrees that at the next scheduled outage, this tube will be stabilized and plugged with conventional plugs.

Salem Unit 2 The WCAP 12090 for Unit 2was compiled using "final" text material (January '89 review date), but the AVB maps printed as Figures 6-2 through 6-5 were a preliminary version (November '88 review date). As a result, some of the AYE plots do not match the descriptions in the text.

In order to correct th is discrepancy, WCAP 12090 should be revised by removing Figures 6-2 through 6-5: and replacing them with the enclosed figures.

Staff's questiohs on Salem Unit 2 S/G 1 tube R9C35 and S/G 2 tubes RllC45, RllC46 & RllC50 should be resolved if the new AVB maps provided here are utilized.

The flow peaking factors for Unit 2 S/G2 tube RllC17 and S/G 4

, tube R9C35 were also among those questioned by the NRC.

Westinghouse has reviewed the evaluation performed in developing the peaking factors for these particular tubes, and can confirm that tests have been performed modeling these specific geometrics, and that the stated peaking factors are believed to be correct.

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ML18094B256

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