ML20009B352
| ML20009B352 | |
| Person / Time | |
|---|---|
| Issue date: | 06/15/1981 |
| From: | Mark J Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0263, ACRS-SL-263, NUDOCS 8107150310 | |
| Download: ML20009B352 (3) | |
Text
_.
_[
]o
~
UNITED STATES
.n
!~
NUCLEAR REGULATORY COMMISSION i
e
/
{,
E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS kb
/
[(/
o g
WASHINGTON, D. C. 20555 June 15,1981 I
(
\\$
I
,97 e,
{
4 JUN 1919815 O Honorable Joseph M. Hendrie y ( u % @" j11 Chairman n'}.
e.=s
/
U. S. Nuclear Regulatory Commission Washington, DC 20555 W>.
)
l s
Subject:
TWO-HUNDRE3-FIFTY-FOURTH MEETING OF THE ADVISORY C0KMITTEE ON REACTOR SAFEGUARDS, JUNE 4-6, 1981
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 254th rdeting in Washington, DC on June 4-6, 1981.
Items considered at this meeting a.e summarized below.
254th ACRS Meeting The Committee completed its response to questions from Senator Alan K. Simpson, U. S. Senate Subcommittee on Nuclear Regulation, regarding the NRC Safety Research Program.
The Committee provided comments to the Executive Director for Operations regard-ing proposed requirements and schedules for installation of reactor core coolant level instrumentation.
Copies of the correspondence noted above have been provided to you.
The Cornittee discussed its report to the Commission, pending development of additional information, regarding the NRC Safety Research Program Budget for FY-1983. Additional work is scheduled to compiate this report during the 255th ACRS Meeting.
The Committee met with members of +'e NRC Staff to discuss the status of the interim NRC rule on Control of Hydrogen and Certain Degraded Core Conditions, and the consideration of Class-9 Accidents, particularly work needed to improve the MARCH code.
The Committee was briefed by representatives of the Office of Technology Assessment regarding its study entitled Nuclear Power Plant Standardization:
j.jftWaterReactors.
The Members completed their review of candidates nominated to fill the existing vacancy on the Committee. A recommendation regarding an appropriate candidate has been sent to you.
8107150310 810615 PDR ACRS SL-0263 PDR
.., - _.. - - -. - ~
Honorable Joseph M. Hendrie June 15,1981 The Committee met with members of the NRC Staff to discuss proposed changes in pipe failure criteria. The Committee plans to review the NRC Staff's safety evaluation reports on WCAP-9558, Mechanistic Fracture Evaluation of Reactor Coolant Pipe Containing a Postulated Circumferential Through-Wall Crack, and WCAP-9787, Tensile and Toughness Properties of Primary Piping Welu Metal for Use in Mechanistic Fractt e Evaluation wher. these reports are available.
The Committee met with members of the NRC Staff to discuss proposed requirements for the seismic qualification of nuclear power plant equipment in operating plants.
The Committee was briefed by representatives of the Department of Energy (DOE) i regarding safety assessments of DOE reactors taking into account lessons learned from the lNI-2 accident.
ACRS Subcomittee Activity Since the last report of ACRS activities the following subcommittee meetings have been held:
Metal Components, in Washington, DC on May 19, 1981 Transportation of Radioactive Materials, in Washington, DC on May 20, 1981 Class-9 Accidents, in Washington, DC on May 21-22, 1981 Reactor Radiological Effects, in Toronto, Ontario on May 26-27, 198'.
Electrical Systems, in Washingtor., DC on May 28, 1981 NRC Safety Research Programs, in Washington, DC on June 3,1981 Reliability and Probabilistic Assessment, in Washington, DC on June 3,1981 Future Schedule The following items are tentatively scheduled for consideration during the 255th ACRS Meeting, July 9-11, 1981:
NRC Safety Research Program Budget for FY-83 -- Report to NRC Pilgrim Nuclear Power Station Unit 2 -- TMI issues Three Mile Island Nuclear Station Unit 1 -- Resumption of operations l
_m
-.m
N
- o-Honorable Joseph M. Hendrie June 15,1981 Improved Plant Safety Features -- Report en improved safety features at sites with high population densities Decay Heat Removal Systems -- NRC Action Plan Improved safety features for future nuclear plants -- ACRS recomendations Sincerely yours, J. Carson Mark Chaiman
=-
1
_.._.....-,_..m_.,.-
~,,,,,