ML17256A426

Forwards Reactor Containment Bldg Integrated Leak Rate Test,May 1982. Facility within Tech Spec Limits

ML17256A426
Person / Time
Site:	Ginna
Issue date:	12/15/1982
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17256A427	List: ML17256A426 ML17256A428
References
NUDOCS 8212210456
Download: ML17256A426 (4)

Text

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<<Electric Corpg IRE REC rCRUT Operating Reac,tors Branch 5 SUBJ/OI: Forwards",Reactor containment 8<<dg Integrated Leak Rate Test/May 1982,," Faci i ty wi thin Tech Spec imi;ts.

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/III/ri'/lILl'i//rr STASE ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAILER TELEPHONE Vice President AliEA COOE 716 546-2700 December 15, 1982 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Integrated Leak Rate Test R. E. Ginna Nuclear Power Plant Unit No. 1 Docket No. 50-244

Dear Mr. Crutchfield:

An integrated leak rate test was performed in May 1982 which demonstrated that leakage from the reactor containment building at the R. E. Ginna Nuclear Power Plant was within the limit specified in our Technical Specifications. Enclosed are fifteen (15) copies of the report of that test titled "Reactor Containment Building Integrated Leak Rate Test". This report is submitted in accordance with the requirements of Appendix J to 10 CFR Part 50 and contains an analysis and interpretation of the Type A test results and a summary analysis of Type B and Type C tests performed since the last Type A test in 1978.

Very,truly yours, Jo n E. Maier o l'7 5

/rS 82i22i0456 82i2i5 PDR ADOCK 05000244 P PDR

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