ML20211C243

Proposed Tech Specs Re Decay Heat Removal Sys Leakage

ML20211C243
Person / Time
Site:	Three Mile Island
Issue date:	09/19/1997
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20211C227	List: ML20211C222 ML20211C243
References
NUDOCS 9709260151
Download: ML20211C243 (3)

Text

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ENCLOSUREl Three Mile Island Nuclear Station, Unit 1,(TMI 1)

Operating License No. DPR-30 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 266 Decay Heat Removal System Leakage Revised Page 4-45 1

9 9709260151 970919 PDR ADOCK 05000289 P PDR

45.4 DECAY HEAT REMOVAL SYSTEM LEAKAGE APPliGLbalit.y

. Applies to Decay Heat Removal System leakage.

Obiective To maintain a low leakage rate from the Decay Heat Removal System to prevent significant off-site exposures.

Specification 4.5.4.1 He maximum allowable leakage from the Decay Heat Removal System components as measured during refueling tests in Specification '4.5.4.2 shall not exceed 0.6 gallons per hour.*

4.5.4.2 During each refueling period the following tests of the Decay Heat Removal System shall be conducted to determine leakage:

a. He portion of the Decay Heat Removal System, except as specified in "b", that is outside containment shall be leak tested either by use in normal operation or by hydrostatically testing at 350 psig.

b. Piping from the Reactor Building Sump to the Decay Heat Removal System pump suction isolation valve shall be pressure tested at no less than 55 psig.

c. Visual inspection shall be made for leakage from components of the system.

Leakage shall be measured by collection and weighing or by another equivalent method.

• Note: GPUN Letter No. 6710-97 2425-1, dated September 19, 1997, commits to limiting the total leakage from the accident recirculation portions of the Decay lleat, Building Spray and Make-Up systems to the UFSAR 0.6 gph licensing basis value.

Basm Re leakage rate limit for the Decay Heat Removal System is a judgement value based on ensuring that its components can be expected to operate for an extended period (200 days or more) after a loss of coolant accident without significant leakage (Reference 1). The test pressure achieved either by normal system operation or by hydrostatic testing (350 psig) provides an adequate margin over the highest pressure within the system after a design basis accident. Similarly, the test pressure for the recirculation lines from the reactor budding sump to the decay heat system (65 psig)is the design pressure of the reactor building, RFLERENCES.

(I) UFS AR, Section 6.4.4 " Design Basis Leakage" and Table 6 4-3 " Leakage Quantities to the Auxiliary Building" (2) UFSAR, Section 14.2.2.5(d) " Effects of Engineered Safeguards Leakage During Maximum Hypothetical Accident" 4-45 Amendment No. M7 l

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN TIIE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR INC. LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of the Supplemental Information pertaining to the Technical Specification Change Request No. 266 Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londondeny Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as fcllows.

Mr. Darryl LeHew, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors cf Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg,PA 17120 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources Rachael Carson State Oflice Building P.O. Box 8469 Harrisburg, PA 17105-8469 Att: Mr Stan Maingi GPU NUCLEAR INC.

BY: / ttua ul tt '

Vidd President and Diryctpr, TMI J

DATE:

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