ML20011F059
| ML20011F059 | |
| Person / Time | |
|---|---|
| Issue date: | 02/06/1990 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0366, ACRS-SL-366, NUDOCS 9002280043 | |
| Download: ML20011F059 (4) | |
Text
--~-
j ' '[/ sN8cg'of 8
bfph UNITED STATES 1
f B/3 g g2// g
![
'( g -
NUCLEAR REGULATORY COMMISSION--
1 --
4
- -a'
- ADVISORY COMMITTEE ON REACTOR SAFEOUARDS -
g[:
1,*g
.[
, WASHINGTON,0. C. 20896
. REVISED:
2/16/90 c
- a
- ...* ~
February 6, 1990 t
' The Honorable-Kenneth M. Carr Chairman U.S.
Nuclear Regulatory Commission W
Washington,-D.C.
20555
Dear Chairman Carr:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED FIFTY-SEVENTH MEETING OF THE ADVISORY COMMITTEE ON-REACTOR SAFEGUARDS,
' JANUARY 11-12, 1990 During its 357th meeting,. January 11-12,-
- 1990, the Advisory Committee on - Reactor Safeguards discussed several : matters and:
e completed the report, noted below, to the EDO.
A copy'of this-report, has -already been provided :to you.
A - summary of the-activities of:the Committee during this meeting is'given-below.
Letter to the EDO 4
o Resolution of the Interfacina Systems LOCA Issue (Report to
'J.
Taylor. EDO, dated January 18, 1990)
Meetina'with the Commissioners
-The Committee met with the. Commissioners on~ January 11, 1990 and
~ discussed'the following-items:
o' Status of ACRS-activities related to the _ development-of-containment design criteria for future' plants.
s o
-ACRS views on the NRC Safety Goal Policy.and its relationship to the concept of " adequate protection."
o Highlights of the November 1 and 2,1989 meeting with the AECB Advisory Committee on Nuclear Safety.
Other Actions. Aareements. Assianments, and Reauests o'
Pronosed Rule on Emeraency Prenaredness Relatina to 10 CFR Part 52. Licensina for Nuclear Power Plants (Memorandum from R.
F. Fraley, for W. Minners, dated January 23. 1990) y 3W#
DESIONATED ORIGINAL bf EE j
Cort 1fied Dy_
h 7,
PDR SL-0366-I
4
- g. :
s O
a
- The Honorable Kenneth M. Carr 2
L
' Consistent-with the: Committee's decision, Mr. Fraley has informed Mr. Minners, Director, Division of. Safety Issue Resolution, RES, that the Committee has deferred its decision regarding review of this proposed rule until after the public comlaents have been received.
o ProDosed._ACRS Report Recardina Coherence in the Reaulatory Process The Committee discussed a proposed report to the Commission regarding coherence in the NRC regulatory. process and concluded that additional discussian would be required during the February 8-10, 1990 ACRS meeting, o
Meetina with the AEOD Director The Committee met with Mr.
E. Jordan, Director of ~ AEOD, to discuss several items of mutual interest.
Owing to lack of time, the Committee was not able to discuss all the proposed' items.
The Committee suggested, and Mr. Jordan agreed, that the discussion of the remaining items be completed during the February 8-10,1990 ACRS meeting.
o Nuclear Power Plant Incidents and Events The NRC staff briefed the Committee;regarding the following incidents-and events:
Diesel Generator Failure at South Texas Station Unit 2, November.28, 1989.
RCS Leakage through RHR Suction Relief Valve at Braidwood Unit 1, December 1, 1989.
Inoperable HPCI Systems at Dresden Nuclear Station Units 2 and 3.
Precursor to an Interfacing Systems.LOCA Event at Arkansas Nuclear.One, Unit 2, June 26, 1989.
This briefing was for information and no Committee action was taken.
o Subcommittee Restructure i
E The Committee decided to restructure several existing Subcommittees to provide more focus on important issues, including several issues related to operating nuclear power plants.
4 4
I r
1 j
p" i
j The Honorable Kenneth~M. Carr' 3
1 o
ProDosed" Revision to Reculatory Guide 1.53 In view of the-f act. that the ' staff is ' reconsidering its intention to issue the proposed-revision to Regulatory Guide 1.33,
" Quality Assurance Program Requirements (Operations) " -
to incorporate the resolution of Generic' Issue 75, " Generic Implications of ATWS Events. on Salem QA,"
the Committee decided not to review this proposed revision at this time, j
o ODeratina Events The Committee agreed that the staff brief - the ACRS on the 1
following events during.the February 8-10, 1990 meeting.
125V DC system circuit breaker' design problem at Point Beach Units 1 and 2, November 7, 1989.
1 Potential LPCI. swing bus undervoltage failure (generic to BWRs), October 12, 1989.
Inadequate NPSH of Auxiliary feedwater. pump at Robinson Unit 2, August 16, 1989..
(NOTE:
This item has been deferred to the March ACRS meeting).
' )
Selbcommittee Meetinas E
' l b
Since the last summary report of ACRS activities, the following Subcommittee meetings have been held:
o Advanced Pressurized Water Reactors, January 10, 1990 - The Subcommittee continued its review of the Westinghouse Evolutionary Light Water Reactor design, WAPWR SP/90.
j o
Joint Severe Accidents and Probabilistic Risk Assessment, January 23-24, 1990 - The Subcommittees continued their review
. of NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S. Nuclear-Power Plants."
l'
. o Structural Encineerina, January 24-25, 1990 - The Subcommittee li discussed the structural integrity issues related to various containment configurations and seismic category I structures.
l.
L o
Systematic Assessment of Exoerience, February 6, 1990 - The t
Subcommittee reviewed the proposed power level increase for l
Indian' Point Nuclear Station Unit 2.
L o
Containment Syntems, February 6,
1990 The Subcommittee discussed the proposed Supplement to Generic Letter 88-20 related to containment performance improvement program (all containment types except BWR Mark I).
+w r
4 m.
---m
PI l
4
. +
cThe Honorable Kenneth M., Cart 4
i Schedule for the 358th.Meetina t
The Committee agreed to the following tentative schedule for the 358th ACRS-meeting, February 8-10, 1990:
o geherence in the Reculatory Process-(Onen) - Discuss L
proposed ACRS report to NRC regarding coherence in the l
regulatory process.
l o-Generic Issue B-56. Diesel Generator Reliability and i
E Associated Reculatory Guide 1.9.
Revision 3 (Onen) - Review and report on. proposed resolution of this generic issue.
l o
Reactor Operatina Exoerience (ODen/ Closed) - Briefing and discussion of recent reactor operating events and incidents.
(NOTE:
This item has been deferred to the March meeting.)
L o
Reactor Safety Research (Ocen) - Discuss proposed-ACRS I
report to the U.S. Congress regarding the NRC safety research program.
o Indian Point Nuclear Station Unit 2 (Ocen) - Review and report on proposed power level increase for the Indian-Point L
Nuclear Station Unit 2.
o Trainina and Oualification Procram for NRC Emolovees (ODAD1
-Briefing and discussion regarding the facilities and courses available for NRC employees at the NRC Technical Training Center at Chattanooga, TN.
o Meetine with AEOD Director (Ocen/ Closed) - Briefing and discussion regarding activities of the NRC Office for i
Analysis and Evaluation of' Operational Data (AEOD) and other items of mutual interest.
o ACRS Subcommittee Activities (ODen)
Reports and discussion l
of ongoing ACRS subcommittee activities in assigned-areas.
o Accointment of ACRS Members (Ocen/ Closed) - Discuss the qualifications of candidates for appointment as ACRS members and the needs of the committee for balanced membership.
o Future Activities (Ocen) - Discuss anticipated ACRS L
subcommittee activities and items proposed for consideration L
by the full Committee.
o Contaihment Performance Imorovement Procram (tentative)
Review and report on proposed NRC staff program for (Ocen) containment types other than Mark I type containment.
Sincerely, l
14MA Carlyle Michelson Chairman l-11
__