ML19323A204
| ML19323A204 | |
| Person / Time | |
|---|---|
| Issue date: | 02/22/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0247, ACRS-SL-247, NUDOCS 8004180074 | |
| Download: ML19323A204 (2) | |
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UNITED STATES b ( k/L/pg NUCLEAR REGULATORY COMMISSION J " ),,
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ADVISORY COMMITTEE ON REACTCR SAFEGUARDS f
W ASWNGTON. D. C. 20555 o
7 February 22, 1980 Honorable John F. Ahearne Chairman U. S. Nuclear Regulatory Comission Washington, DC 20555
Subject:
'IWO-HUNDRED-THIRTY-EIGHTH MEETING OF 1HE ADVISORY CCNMITTEE ON REACIOR SAFEUUARDS, FEBRUARY 7-9, 1980
Dear Dr. Ahearne:
The Advisory Comittee on Reactor Safeguards held its 238th meeting in I
Washington, DC on February 7-9, 1980. Itsas considered at this meeting are sumarized below:
We Comittee completed its review of NUREG-0625, Siting Policy Task Force Report and prepared a report to NRC on this subject.
We Comittee prepared a letter regarding the Commission's actions relating to NUREG-0660 Draft 2, Action Plans for Implementing Recomendations of the I
President's Commission and other Studies of the TMI-2 Accident.
We Cemittee completed its review of the proposed NRC Acceptance Criteria for the Mark I Containment Long Term Program and prepared a report to NRC on this subject.
We comittee completed its annual report to the Congress on the NRC's Safety Research Program. Copies of this report have been sent to you.
l We Comittee prepared a letter to the Comissioners regarding the Qualifi-cations of Radioactive Waste System Operating Personnel for nuclear power plants.
W e Committee prepared a response to Representative Morris K. Udall's ques-tions relating to the consistency of actual component failure experience with that projected in WASH-1400 and probabilistic analysis of selected n,
incidents at the Davis-Besse and Rancho Seco nuclear stations.
We Committee prepared a memorandtml to the Acting Executive Director for
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Operations noting reports of cracks in Westinghouse low-pressure turbine disk assemblies, and requesting that the NRC Staff reevaluate the probabil-ity of failure and consequences from turbine missiles.
We Committee met with members of the NRC Lteff ts discuss the implementa-l tion of the 1MI-2 Bulletins and orders. Additional review of this matter is to be continued during the 239th ACRS meeting.
8004180o99
J Honorable John F. Ahearne February 22, 1980 o
he Comittee met with menbers of the NRC Staff and representatives of the licensee to discuss the proposed restart of Three Mile Island Nuclear Station Unit 1.
Additional work will be required before resolution of this matter.
Since the last report of ACRS activities, the following subcommittee meetirxJs have been held:
Surry Power Station Unit 2, in Washington, DC, on January 23, 1980 Metal Components, in Washington, DC on January 23-24, 1980 Anticipated Transients Without Scram, in Washington, DC, on January 25, 1980 W ree Mile Island Nuclear Station Unit 1, in Middletown, PA on January 31 - February 1, 1980 Reliability and Probabilistic Assessment, in Washington, DC on February 6, 1980 Procedures and Administration, in Washington, DC on February 6, 1980 The following items are tentatively scheduled for consideration at the 239th ACRS Meeting, March 6-8, 1980:
Indian Point Nuclear Generating Station Units 2 and 3/ Zion Station Units 1 and 2 - consideration of proposed additions to engineered safety features NRC Action Plans Draft 3 - ACRS comments -
Proposed changes to 10 CFR 50, Appendix K - fuel elenent clad ballooning model ACRS Report on the Pause in Licensing - clarification Floating Nuclear Plant - core ladle design NRC Bulletins and Orders Resulting from 'IMI-2 Accident - proposed implementation Sincerely yours, Milton S. Plesset Chairman 1