ML19290A169
| ML19290A169 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/21/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0241, ACRS-SL-241, NUDOCS 7910170481 | |
| Download: ML19290A169 (3) | |
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
[M E 1 ? J f,,8 W ASHINGToN, D. C. 20555
%w August 21, 1979 Honorable Joseph M. Hendrie Chairman U. S. Nuclear Regulatory Comission Washington, DC 20555
Subject:
TWO-HUNDRED"I'HIRTY-52CCND MEETING OF EE ADWSGY CmMITTEE W REACTOR SAF"'EARDS, AUGUST 9-11, 1979 IN WAS.1INGrm, DC
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 232nd meeting in Washington, DC on August 9-11, 1979.
Items considered at this meeting are summarized below.
Projects The Committee continued its evaluation of the March 28, 1979 ceci-dent at Three Mile Island Nuclear Station Unit 2 (TMI-2) and the implications of this accident for other operating nuclear plants and those plants for which near-term Operating Licenses are pend-ing. his included discussion with the NRC Staff's Lessons Learned Task Force to discuss the Task Force's recommendations regarding short-term lessons learned from the TMI-2 accident.
The Committee concluded that it had no objection to iscuing Operating Licenses for Salem Nuclear Generating Station Unit 2 and North Anna Powr Station Unit 2 provided that the same Task Force recommendations are applied to these plants as are aFplied to plants that have already been issued Operating Licenses.
Other plants awaiting near-term Operating Licenses will require further ACRS action.
Tne Executive Director for Operations has been informed of this conclusion.
In addition, a rernrt has been provided to you re-garding the short-term recomuendations of the TMI-2 Lessons
- Learned Task F6rce WURD3-0578).
ha Committee concluded that proble-a regarding fuel elenent per-formance in the Lacrosse Boiling i.a.tr Reactor appear to have been afeguately addressed and do not warrant Committee action, d
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s Honorable Joseph M. Hendrie August 21, 1979 Miscellaneous he Comittee prepared a response to Congressman Marris K. Udall regarding his recent request for failure rate data in connection with the ACRS Review of Licensee Event Reports (LERs) and an an-alysis of incidents at the Rancho Seco Nuclear Generating Station and the Davis-Besse Nuclear Power Station Unit 1.
The Comittee considered the problen of Pioe Cracking in Light Water Reactors ind has provided a separate report to you regard-ing this matter.
We Committee has also provided to you a report regarding Steiles to Improve Reactor Safety.
We Committee prepared a memorandum to Commissioner Ahearne regard-ing the assignment of the ACRS Subcomittee on Reliability and Probabilistic Assessment to formulate recommendations regarding the establishment of quantitative safety goals within approxi-mately 12 months.
We Committee continued its evaluation of LERs received during the years 197# throtqh 1978.
mis matter will reqaire further work and has been scheduled for consideration durire the forth-coming ACRS meetire.
The Comittee discussed underlying causes in the regulatory pro-cess which may have centributed to the TMI-2 accident.
This matter will require additional work and futher discussion has been scheduled.
The Committee met with members of the NRC Staff to discuss their proposed plans for the resolution of Anticioated Transients Without Scram as applied to boiling water reactors.
The Committee met with members of the NRC Staff to discuss their proposed plans for implementation of NURB3-0396, Basis for Develop-ment of Emergency Resoonse Plans by State and Local Governments in Succort of Light Water Reactors.
Since the last report of ACRS activities, the following subcommittee meet-ings have been held:
Evaluation of LERs, in Washington, DC, on July 18-19, 1979 MI-2 Accident Implications, in Washington, DC, on July 26-27, 1979 Advanced Reactors, in Washington, DC, on August 7,1979 mI-2 Accident Implications, in Washington, DC, on Aogust 8,1979 Regulatory Activities, in Washirston, DC, on August 8,1979 2223 350
Honorable Joseph M. Hendrie August 21, 1979 The following items are tentatively scheduled far consideration at the 233rd ACRS meeting, September 6-8, 1979:
'IMI-2 Accident Implications - Underlying Causes TMI-2 Accident Implications - Long-Term Les/ sons Learned Evaluation of Licensee Event Reports - Period 1976-1978 Anticipated Transients Without Scram - Resolution for BWT.'s Review of Generic Items - Proposed Plan for Resolution Risk Acceptance Criteria - Quantitative Criteria Seismic Design of Nuclear Power Plant Piping - Combination of Dynamic Loads Sincerely yours, W
Max W.
rbon Chairman S
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