ML19345A769

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Approves Proposed Change 75 to Tech Specs,Authorizing Frequency & Acceptance Limits for Periodic Testing of Individual Containment Penetratins & Integrated Leakage Rate Tests of Containment
ML19345A769
Person / Time
Site: Yankee Rowe
Issue date: 03/28/1967
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Coe R
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML19345A770 List:
References
NUDOCS 8011250116
Download: ML19345A769 (1)


Text

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Distribution:

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AEC Document Room

  1. " *e UNITED STATES 5

ATOMIC ENERGY COMMISSION DRL Reading

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WASHINGTON, D.C. 20545 R0B Reading e,

8 Orig: FENorian

%e MR 2 81967 C. Henderson H. Shapar IN REPLY REFER TO' L. Kornblith (2)

Docket No. 50-29 H. Dube (5)

J. Saltzman R. G. Pa6e D. Skovbolt N. D. Ksecn Yankee Atomic Electric Company bec:

H. J. McAlduff, ORO M1 Stuart Street E. Tremmel, IP Boston, Massachusetts 02116 R. Leith, OC Attention: Pa. Roger J. Coe Change No.ORNL W. B. Octtrell 75 Vice President Gentlemen:

This refers to your requect dated October 20, 1966, for AEC authorization of Proposed Change No. 75 in the Technical Specifications of Facility License No. DPR-3 for the Yankee reactor facility pursuant to the provicions of 10 CFR 50 59 The proposed enange would specify the frequency of and accept-ance limits for periodic testing of individual containment penetrations ani also integrated leakage rate tests of the containment.

We have reviewed the proposed change and have found that it does not present significant hazards considerations not described or implicit in the safety analysis report, ani that there is reasonable assurance that the health and safety of the public will not be eniangered.

l In view of the foregoing, Section D.2.J. is added to the Technical Specifications of Facility License No. DPR-3 as follows:

l D.2.J.

Containment Leakage Rate Retest Specifications "The specifications which define the minimum tests, l

acceptance criteria, corrective actions, and test l

frequency which shall govern the continued accept-l ability of the reactor containment structure are described in Appendix C attached bereto."

l A copy of our related safety evaluation ani Appendix C, " Containment Leakage l

Rate Retest Specifications for Yankee Atomic Electric Company, Rove, Massachusetts,"

are attached.

Sincerely yours, erla.iset signed br pee, s. merves l

l Peter A. Morris, D nector Division of Reactor Licensing

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DRLef D

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Enclosures:

As stated above PEHorian/1tj DJSkohlt PAM is

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