ML20205F116
| ML20205F116 | |
| Person / Time | |
|---|---|
| Issue date: | 02/21/1985 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0307, ACRS-SL-307, NUDOCS 8511040470 | |
| Download: ML20205F116 (3) | |
Text
8/- 8@ 7
/
'o,,
UNITED STATES
[88 N 8
NUCLEAR REGULATORY COMMISSION o
[
B
,I ADVISORY CdMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20556 g
February 21, 1985 Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Comission Washington, D. C.
20555
Dear Dr. Palladino:
~~
SUBJECT:
TWO-HUNDRED NINETY-EIGHTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, FEBRUARY 7-9, 1985
. 298th ACRS Meeting The Committee met with representatives of the NRC Staff and the Comon-wealth Edison Company (the Applicant) to review the application for an operating license for the Braidwood Station, Units 1 and 2.
The Ccmmittee discussed the major reductions that have been proposed in the funding and staffing of activities of the Advisory Committee on Reactor Safeguards during the remainder of FY 1985 and in FY 1986.
Reports on the subjects noted above have been sent to you.
The Comittee met with representatives of the NRC Staff to continue its review of the proposed revision of the NRC rule (10 CFR 50.109) on backfitting of nuclear power plants and a new Manual Chapter (0514) to implement that rule.
Additional discussion is needed regarding this matter and is scheduled for the Committee's 299th meeting on March 7-9, 1985.
The Committee met with representatives of the NRC Staff to consider Mr.
D. L. Basdekas' technical opinion concerning the proposed final rule on pressurized thermal shock.
The Comittee's comments on this subject have been provided to the Executive Director for Operations. A copy has been sent to you.
The Comittee discussed the proposed NRC Safety Research Program and Budget for Fiscal Years 1986 and 1987 and the related ACRS report to the U. S. Congress.
Final copies are being prepared and will be provided to you shortly.
The Comittee met with representatives of the NRC Staff regarding the report of the NRC Task Force on Fire Protection.
The Comittee met with the Comissioners to discuss the use of the
" check-operator" concept for requalification of nuclear power plant j
operators, requirements regarding experience levels required for nuclear i
i L
G 8511040470 850221 PDR ACRS SL-0307 PDR Coctified Dy 3.- /
w's
/
J
Y Honorable Nunzio J. Palladino February 21,1985 power plant operators, and the proposed NRC rule to revise backfitting requirements for nuclear plants and the associated draft NRC Manual Chapter 0514.
1 Subcommittee Activitiec Since the last report of ACRS activities, the following Subcommittee meetings have been held:
Waste Management, in Washington, D. C. on January 18-19,1985 to review:
(1) the criteria and methodology. to be used by DOE in selecting the three sites, plus two alternate sites in their high-level waste environmental assessment of nine potential sites, and (2) the NRC/WM Standard Review Plan for Environmental Assess-ments of sites selected for characterization Decay Heat Removal Systems, in Albuquerque, NM on January 22, 1985 to continue the review of the USI A-45, Shutdown Decay Heat Removal t
Requirements, resolution effort i
Class 9 Accidents, in Washington, D. C. on January 25.1985 to review the redirection of the severe accident research program as a result of'the budget changes Braidwood Station, Units 1 and 2, in Washington, D. C. on January 29, 1985 to review the Commonwealth Edison Company's application for an operating license for the Braidwood Station Fire Protection, in Washington, D. C. on February 5,1985 to be I
briefed on the following:
(1) the status of Appendix R implementa-
- tion, (2) Duke and Calvert Cliffs compliance with Appendix R, and (3) the status of fire protection research at Sandia National Laboratory
)
Advanced Reactors, in Washington, D. C. on February 5,1985 to i
discuss the DOE's redirected programs for LMRs and to review the j-relevant NRC research programs in the areas of LMRs and HTGRs i
j Regulatory Policies and Practices, in Washington, D. C. on February 6, 1985 to review the Commission's proposed NRC backfitting rule j
(10 CFR 50.109) and the related NRC Manual Chapter (0514) l Future Agenda The following items are tentatively scheduled for consideration during the 299th ACRS meeting, March 7-9, 1985:
i.
i Nine Mile Point Nuclear Plant, Unit 2 -- OL review
[
Recent Events at Operating Reactors -- Briefing regarding recent events and incidents at nuclear power plants
o I/
Honorable Nunzio J. Palladino February 21, 1985 NTSB-type Board for Nuclear Accidents -- Report of ACRS Subcommit-tee on the Brookhaven report regarding establishment of such a board and the role of the ACRS in evaluating nuclear accidents Steam Generator Overfill -- ACRS Subcommittee report regarding proposed action to resolve this issue Emergency Core Cooling Systems -
Proposed amendments of 10 CFR 50.46 to revise Appendix K, ECCS Evaluation Models, and deletion of upper head injection in the McGuire Nuclear Station GESSAR II Standard Plant Design Briefing -- Description and identi-fication of safety issues Meeting with Director, AE0D -- Briefing regarding AE0D activities of interest / concern Systematic Review of Nuclear Power Plants -- proposed ACRS action to clarify its report of July 18, 1984 Backfitting of Nuclear Power Plants - ACRS comments regarding proposed rule (10 CFR 50.109) change and revision of NRC Manual Chapter 0514 Sincerel,
David A. Ward Chairman
,