ML20205K795
| ML20205K795 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/1987 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-124, REF-GTECI-NI, TASK-124, TASK-OR ACRS-SL-0330, ACRS-SL-330, NUDOCS 8704020040 | |
| Download: ML20205K795 (3) | |
Text
.__
_. ~
S/20Nb PDASMWM f
!,,,, o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
{
,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20555 January 21, 1987 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED AND TWENTY FIRST MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JANUARY 8-10, 1987 The Advisory Comittee on Reactor Safeguards held its 321st meeting in Washington, D.C. on January 8-10, 1987.
Items considered during this meeting are sumarized below:
321ST ACRS MEETING The Comittee completed its preparation of Recomendations on Improved Safety for Future Light Water Reactor Plant Design.
The Comittee prepared coments on the Implications of the Accident at the Chernobyl Nuclear Station Unit 4 Reports on the subjects noted above have been sent to you.
The Comittee prepared coments on the Draft NRC Staff Report on the Implications of the Accident at Chernobyl Nuclear Station Unit 4.
The Committee's coments on this subject have been provided to the Executive Director for Operations. A copy has been sent to you.
The Committee met with the Director of NRR and was briefed on the NRC Staff's efforts regarding the implications of the Chernobyl accident, the development of NRC strategic plans and the resolution of Generic Issue 124, " Auxiliary Feedwater System Reliability".
The Comittee met with the Executive Director for Operations and was briefed on the plan for reorganization of the NRC Staff and its current status.
The Comittee completed consideration of additional candidates for appointment to the Comittee. Two additional nominees have been recommended in a separate memorandum to you.
/
870402004o 870121 DESIGNATED ORIGINAL PDR, J,
, epw PDR Certified By
.am ma
Honorable Lando W. Zech, Jr.
2 January 21, 1987 9
The Comittee was briefed regarding the forthcoming review of the General Electric Advanced Boiling Water Reactor. The Comittee heard presentations from representatives from General Electric and the NRC Staff regarding the proposed Licensing Basis Agreement for this project. Discussion of this matter is expected to continue.
The Comittee identified its report Recomendations on Improved Safety for i
Future Light Water Reactor Plant Design as a suitable topic for future discussion with the Comissioners. The Comittee agreed that it would take at least two more meetings before it will have developed a Comittee position on implementation of NRC Safety Goal policy and that a discussion of this matter with the Commissioners would best be, scheduled after that.
Since the last report of ACRS activities, the following subcomittee meetings have been held:
Instrumentation and Control Systems, in Washington, DC, on December 18, 1986 to discuss the effects of adverse conditions such as high tempera-ture on solid-state components in nuclear power plants.
Severe Accidents, in Washington DC, on December 19, 1986 to discuss the NRR Implementation Plan for the NRC Severe Accident Policy Statement regarding Individual Plant Examinations for Existing Plants.
Joint meeting of the Subcomittees on General Electric Reactors and Safety Philosophy, Technolocy and Criteria, on January 7,1987 to explore the status of the Acvanced Boiling Water Reactor project and to be briefed on licensing basis agreement between General Electric and the NRC for review of this project. The Subcomittee on Safety Philosophy, Technology and Criteria also considered the status of NRC Staff's work on the Safety Goal Policy and on USI A-17 " Systems Interactions on Nuclear Power Plants."
Future Agenda The following items are tentatively scheduled for consideration during the ACRS meeting, February 5-7, 1987:
Quantitative Safety Goals - Discuss proposed NRC Staff plan for imple-mentation of the NRC Safety Goal Policy statement.
Standard Plant Improvements - Discuss proposed ACRS coments regarding improvements in standardized nuclear power plants.
Naval Reactors Training Facility (Closed) - Review proposed naval reactor training facility.
NRC Safety Research Program - Discuss proposed ACRS report to the U.S.
Congress regarding the proposed NRC research program for FY 1988.
1
Honorable Lando W. Zich, Jr.
3 January 21, 1987 t
Performance of Dynamic Containments - Discuss proposed NRC Staff resolu-tion of concerns regarding the potential for bypassing of the sup-pression pool condensing function.
Recent Events at Operating Nuclear _ Plants - Hear' reports and discuss -
recent operating events at nuclear power plants.
l Advanced Reactor Designs - Report and discussion regarding the scope and status of the NRC Staff review of proposed DOE advanced non-water reactors.
GE Advanced Boiling Water Reactor - Discuss major issues applicable to the licensing basis agreement for the regulatory review and licensing of this standard plant design.
NRC Augmented Inspection Team Reports - Hear and discuss the reports of NRC AIT's for the Surry Nuclear Station and the E.I. Hatch Nuclear Power Plant.
Sincerely, William Kerr, l
Chairman i
e. _... _ _ _., _ _ _... - _ _ _. _ _ _. _
.. -.. -