ML20151D427
| ML20151D427 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Calvert Cliffs, Peach Bottom, Nine Mile Point, Indian Point, Sequoyah, Limerick, North Anna, Diablo Canyon, Callaway, 05000000, 05000314 |
| Issue date: | 03/24/1988 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 ACRS-SL-0344, ACRS-SL-344, NUDOCS 8804140215 | |
| Download: ML20151D427 (4) | |
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WASHINGTON, D. C. 20555 March 24, 1988 The Honorable Lando W. Zech, Jr.
Chaiman l>.S. Nuclear Regulatory Comission Washington, D.C.
20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED AND THIRTY-FIFTH MEETING OF THE ADVISORY COMMIT-TEE ON REACTOR SAFEGUARDS, MARCH 10-12, 1988 The Advisory Comittee on Reactor Safeguards held its 335th meeting in Washington, D.C. on March 10-12, 1988. A sumary of actions is present-ed below:
ACRS REPORTS / RECOMMENDATIONS The Comittee prepared a report on the Restart of the Sequoyah Nuclear Plant.
(Letter to Chaiman Zech dated March 15, 1988)
The Comittee prepared coments on the Need for Greater Coherence Among New Regulatory Policies.
(Letter to Chairman Iech dated March 15, 1988)
The Committee prepared connents on Embrittlement of Structural Steel.
(letter to Chairman Zech dated March 15, 1988)
Reports on the subjects noted above have been sent to you.
The Comittee prepared coments on Regulatory Guide 1.99, Revision 2, "Radiatio.. Embrittlement of Reactor Vessel Materials," Dated March 1988.
(Letter to the Executive Director for Operations dated March 15, 1988)
A copy of this letter has been sent to you.
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND RE0 VESTS Dr. Neville Moray, Chaiman of the Panel on Human Factors Research Needs in Nuclear Regulatory Research, National Research Council, discussed the Panel's recomendations and conclusions.
The Comittee was briefed by representatives of AEOD on recent operating events and incidents.
In particular, the events at Indian Point-2 (steam generator dryout), at Nine Mile Point-2 (reactor scram and vessel overfill), and the annunciator cabinet fires at Beaver Valley-2, Calvert Cliffs-2 and Rancho Seco were described.
8804140215 000324
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The Honorable Lando W. Zech, Jr.
2 March 24,1988 The Comittee was briefed by the NRC Staff on the planned restart of Rancho Seco.
The Comittee agreed that it would not write a letter at this time but would review this matter during its April meeting.
Representatives of DOE briefed the Comittee on the DOE Advanced Reactor Severe Accident Program ( ARSAP).
Representatives of the NRC Staff and TVA briefed the Comittee on the resolution of concerns and issues regarding the restart of the Sequoyah Nuclear Plant. The Comittee agreed that some remaining fire protection issues identified as part of the Sequoyah review should be considered by the Subcomittee on Auxiliary Systems as a generic matter.
Representatives from the NRC Staff briefed the Comittee on Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials."
Representatives from the NRC Staff briefed the Comittee on the NRC Staff efforts to resolve the uncertainties associated with radiation embrittlement of reactor pressure vessel supports.
The Committee discussed concerns associated with the implementation of the safety goal.
The Comittee agreed to continue this discussion during its April meeting.
The Comittee continued its discussien of proposed hierarchical struc-ture for important safety-related issues identified by ACRS members.
This discussion will be continued during the April meeting.
The Comittee decided not to review the requested power level increase from 3411 MWt to 3565 MWt for the Callaway Plant, Unit 1.
- However, attention was directed to the need for consideration of steam generator perfomance at this increased power level in light of experience at the North Anna Power Station.
The Comittee agreed that the Subcomittee on Limerick-2 should proceed with review of the application for an operating license but should not do so until the problem at Peach Bottom is resolved.
The Comittee agreed that a meeting with the Comissioners should be scheduled to discuss the recently approved NRC Maintenance Policy Statement.
The Comittee agreed that the Subcomittee on TVA Organizational Issues should take the lead in the Comittee's independent review of the NRC Staff's report on TVA lessons learned.
Since the lart report of ACRS activities, the following subcomittee 1
meetings have been held-
a The Honorable Lando W Zech, Jr.
3 March 24, 1988 Metal Components, February 18, 1988 - To review Regulatory Guide 1.99, Revision 2,
"Radiation Embrittlement of Reactor Vessel Material."
Joint Scram Systems Reliability and Core Performance, February 19, 1988 - To review the current status of LWR plant operations as they may influence core reactivity control, ' perational limits, and ex-isting ATWS analyses.
Diablo Canyon, February 23 and 24,1988 - To review the status of the Diablo Canyon Long-Tenn Seismic Program.
Reliability Assurance, March 7 and 8, 1988 - To discuss valve reliability.
Auxiliary Systems, March 9,1988 - To discuss the results of the Fire Risk Scoping Study.
FUTURE AGENDA The following items have been proposed for consideration during the ACRS meeting on April 7-9, 1988:
Rancho Seco Nuclear Power Plant - Briefing and discussion regarding proposed restart of the Rancho Seco Nuclear Power Plant.
IAEA General Principles for Reactor Safety - Briefing by Dr. H. J.
Kouts regarding proposed IAEA General Principles for Reactor Safety.
Generic issues Discuss proposed ACRS connents/recomendation regarding the effectiveness of the NRC Staff process to deal with generic issues and unresolved safety issues.
Fitness for Duty (Tentative) - Discuss proposed NRC Fitness for Duty Rule.
Technical Training and Qualification Program for NRC Technical Personnel - Briefi ng by AEOD/PER5 representatives regarding pro-posed changes in NRC training and qualification program for techni-cal personnel.
Human Factors Research Program (Tentative) - ACRS coments request-ed regarding proposed research program.
Meeting with Director, NRR (0 pen) - Discuss items of mutual inter-i est.
l
.h The Honorable Lando W. Zech, Jr.
4 March 24, 1988 I
Training and Qualification of Reactor Operators - ACRS consnents requested on proposed policy statement regarding nuclear power plant operators.
Advanced Reactors - Review proposed key design features for ad-vanced gas cooled and liquid metal cooled nuclear power plants.
Sincerely, W. Kerr Chaiman f
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