ML19290A164
| ML19290A164 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/05/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0239, ACRS-SL-239, NUDOCS 7910170469 | |
| Download: ML19290A164 (3) | |
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0 July 5, 1979 Honorable Joseph M. Hendrie Chairman U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
WO-HUNDRED-THIRTIETH MEETIIG OF THE ADVISORY COMMITTEE CN REACIOR SAFEGUARDS, JUNE 14-16, 1979 in WASHIN3 TON, DC
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 230th meeting in Wash-
- ington, D.C.
on June 14-16, 1979.
Items considered at this meeting are summarized below:
Three Mile Island Nuclear Station Unit 2 Accident and its Implications The Committee continued its review of the accident at Three Mile Island Nuclear Station Unit 2 (MI-2) and the implications of this accident for other nuclear power plants.
The Committee met with representatives of the NRC Staff, the Metropoli-tan Edison Company, and the Babcock and Wilcox Company to discuss the current status of the MI-2 plant; evaluation of responses to NRC/IE Bulletins, NRC Orders, and ACRS recommendations emanating from con-sideration of the TMI-2 accident; and consideration of proposed im-provements to equipnent and procedures.
The Comittee set up a new Subcommittee to consider the responses of vendors / utilities to IE Bulletins and NRC Orders resulting frcm the MI-2 accident.
Further evaluation of the accident and its implications are planned.
Projects me Committee deferred further action on its review of the application for an Operating License for the Seouoyah Nuclear Power Plant Units 1 and 2 until the NRC Staff informs the ACRS of its plans regarding changes to the plant design and/or operations that have been developed following the investigation of the mI-2 accident.
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N Honorable Joseph M. Hendrie The Comittee also deferred further action on its review of the appli-cation for a Construction Permit for the Palo Verde Nuclear Generating Station Units 4 and 5 until the NRC Staff informs the ACRS of its plans regarding changes to the plant design that have been developed follow-ing the investigation of the 'IMI-2 accident.
The Comittee has informed the Executive Director for Operations that the ACRS does not object to the NRC Staff's licensing the Millstone Nu-clear Power Station IJnit 2 to be operated at a power level of 2700 MWt.
The Committee noted the matter regarding alleged erroneous information provided to the Committee during its operating License review of the Zimmer Nuclear Station and has requested that the NRC Staff report to the Committee regarding the resolution of this matter.
Miscellaneou_s The Committee prepared a reply to Commissioner Gilinsky's inquiry re-garding a comparison of the merits of stainless steel vs. zircaloy for nuclear fuel cladding. A copy has been sent to you and the other Com-missioners.
The Committee requested that the NRC Staff inform the Committee regard-ing additional requirements resulting frcm evaluation of the 'IMI-2 accident that the NRC will impose on those facilities for which the Committee has written favorable Operating License reports, but for which Operating Licenses have not been issued.
The Committee concurred in the proposed revision (Revision 2) of Regu--
latory Guide 1.9, Selection, Design and Qualification of Diesel-Genera-tor Units Used as Standby (Onsite) Electric Power Systems at Nuclear Power Plants.
Since the last report of ACRS activities, the following subcommittee meetings and site visits have been held:
Safeguards and Security, in Washington, D.C., on May 23, 1979 Evaluation of Licensee Event Reports, in Washington, D.C., on May 24-25, 1979 TMI-2 Implications, in Washington, D.C. on May 31-June 1,1979 Reliability and Probabilistic Assessment, in Washington, D.C., on June 2, 1979 2223 344
s Honorable Joseph M. Hendrie TMI-2, in Middletown, PA, on June 6-7, 1979 Reactor Fuel, in Washington, D.C., on June 11-12, 1979 Operating Reactors, in Washington, D.C., on June 13, 1979 Regulatory Activities, in Washington, D.C., on June 13, 1979 Two members of the Committee met on May 21-25, 1979, in Japan, with repre-sentatives of Japanese regulatory agencies, including the Committee on the Examination of Reactor Safety to discuss reactor safety policy and practice, and the cooperative emergency core cooling systems (ECCS) program.
In addition to the above, representatives of the Committee visited the Bab-cock and Wilcox simulator at Lynchburg, VA on June 8,1979, to observe simu-lator training.
The 231st meeting of the ACRS will be held in Washington, D.C., on July 12-14, 1979.
The following matters are tentatively scheduled for discussion:
Three Mile Island Nuclear Station Unit 2 - stat.us and implications Bailly Generating Station - design of pilings S neerely yo Max W. Carbon Chairman e
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