ML19220B848

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Forwards Accident Analysis Branch Comments on TMI Tech Specs.Notes Tech Spec 0.13% Containment Leak Rate Is More Restrictive than 0.14% Value Found Acceptable in SER
ML19220B848
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/11/1977
From: Bunch D
Office of Nuclear Reactor Regulation
To: Silver H
Office of Nuclear Reactor Regulation
Shared Package
ML19220B849 List:
References
NUDOCS 7904270458
Download: ML19220B848 (1)


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f" GCT 111977 Occket No. 50-320 MEMORANDUM FOR:

H. Silver, Light Water Reactors Branch No. 4. DPM J. Wet : ore, Standard Technical Specifications Group, DOR FRCH:

D. F. Bunch, Chief, Accident Analysis Branch, DSE

SUBJECT:

THREE HILE ISLAND LMIT 1i0. 2 TECHMICAL SPECIFICATIONS Enclosed are the Accidcnt Analysis Branch's cocarents on the Tnree Mile Island Unit No. 2 Technical Specifications.

It should be noted that the Technical Specification containment leak rate of 0.13% is c' ore restrictive than the 0.14% value we found acceptable in the SER dose calculations.

This review was coordinated by C. Ferrell, Site Analyst, Section B, Accident Analysis Branch.

Crigmel sigr.ed by:

Detert F. Sunch D. F. Bunch, Chief Accident Analysis Branch Division of Site Safety and Envirara: ental Analysis

Enclosure:

Three Mile Island Unit No. 2 Distribution:

Technica~ Specification Changes Docket Files cc: w/ enclosure NRR Rdg. File OSE Rdg. File H. Denton AAB Rdg. File D. ?blier AAB Files R. Vollcer S. Yarga-J. McGough D. Bunch L. Soffer C. Ferrell i

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