ML20070C258

Provides Listed Comments Re Util 940425 License Change Request 94-07,requesting Elimination of 10CFR50,App J,Type C Leak Rate Testing for Certain Containment Isolation Valves

ML20070C258
Person / Time
Site:	Hope Creek
Issue date:	06/28/1994
From:	Tosch K NEW JERSEY, STATE OF
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9407050153
Download: ML20070C258 (2)

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State of New Jersey Department of Environmental Protection and Energy Robert C. Shinn, jr. Division of Environmental Safety, lloalth, Commissioner and Analytical Programa Radiation Protection Programs Bureau of Nuclear Engineering CN 415 Trenton, New Jersey 08625-0415 Tel (609) 987-2032 Fax (609) 987-6354 June 28, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Hope Crook Generating Station Docket No. 50-354 License Change Request LCR 94-07 Elimination of 10CFR50 Appendix J, Type C Test On April 25, 1994, Public Service Electric and Gas Company submitted the subject license change request to the Nuclear Regulatory Commincion (NRC). The proposed change would eliminate the 10CfR50 Appendix J, Type C leak rate testing for certain Containment Isolatioli Valvr>s ICIVs), which are located in lines that penetrate the Primary Containment and tnrminate below the minimum water level in the Torus.

The New Jersey Department of Environmental Protection and Energy's Bureau of Nuclear Engineering reviewed the above amendment )

in accordance with the requirements of 10CFR50.91(b), and has the following comments.

( PSE&G stated in their letter that "This request is based upon an Exemption issued by the NRC on October 30, 1986 for Georgia

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Power Company's !!atch Nuclear Plant." However, the note on page 1 of Attachment 1 says that this amendment request is not an exemption to 10CFR50 Appendix J, Type C Testing. They are proposing the substitution of ASME XI testing for the subject CIVs.

l Does it mean an Exemption from Type C testing was issued to Hatch and no substitution with an appropriate ASME test was required?

Also, shouldn't the details (CIVs and systems involved) of the Exemption, issued to liatch, be provided in the Justification Section of this amendment? The DNE believes that an appropriate ASME code case could have been considered for Hatch.

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/ j If you have any questions, please contact suren Singh at (609) 987-2039 or Rich Pinney at (609) 987-2086.

Sincerely, n -- ..

dfi  % dm Kent Tosch, Manager Bureau of Nuclear Engineering c: Acting Assistant Director McMahon Radiation Protection Programs N.J. DEPE J. Stone NRC Project Manager l

l D. Chawaga j NRC Region I State Liaison C. Marschall Artificial Island Senior Resident Inspector F. Thomson Manager, Licensing and Regulation PSE&G

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