ML20011D115
| ML20011D115 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1989 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| TASK-056, TASK-OR ACRS-SL-0363, NUDOCS 8911290336 | |
| Download: ML20011D115 (3) | |
Text
fllM!
M a
a
/f j
~
[
y
- [,p n,
K S
o
. UNITED STATES :
-/
t
.~ NUCLEAR REGULATORY COMMISSION
-44 1
f " 4.4
.[
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 4
- 0 WASHINGTON, D. C,20665 -
D November 6 -1989 s
n The Honorable Kenneth M. Carr
_ Chaiman -
U.S.: Nuclear Regulatory Commission Washington -D.C.
20555
Dear Chairma' Carr:
n
SUBJECT:
THREE HUNDRED FIFTY-FOURTH MEETING 0F THE ADVISORY COMMITTEE ON.
-REACTOR SAFEGUARDS, OCTOBER 5-6, 1989 q
ACRS REPORTS, LETTERS, AND MEMORANDA-l
- The-Comittee prepared:a report on the Proposed Revised Policy Statement on-
- the ' Maintenance of ' Nuclear Power' Plants. - (Report to Chairman Carr, dated '
l-s October 12,.1989)-
The Comittee prepared a report entitled ACRS' Co:ments on the Safety Goal L
Policy and Its Relationship to the Concept-of Adequate Protection.
(Report to j
f' -
Chaiman Carr, dated October 11, 1989)
The Committee' prepared a letter on'. Proposed-Resolution of Generic Issue 135,'
l
" Steam Generator and Steam Line Overf111 -Issues." (Letter to James M. Taylor, Acting Executive Director for-Operations, dated October. 11,1989)
' Copies of these reports have been provided to you.
.0THER ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS l
The' Committee discussed the NRC staff's proposed resolutions of Generic Issue j
B-56, " Diesel Generator Reliability," ~and Generic Issue 87, " Failure of HPCI j
Steam Line' Without Isolation,"'with representatives of the NRC staff._ The-j Comittee plans to continue its discussion of these issues during the November-4 16-18,'1989 ACRS meeting.
{
.The Comittee was briefed by E.- Beckjord, RES, regarding the impact of the budget' reductions imposed by the Congress on.the NRC Safety Research Program.
[1
,over recent: years and the manner in which these reductions had been distrib-The Committee discussed the-budget reductions that had been imposed on the NRC l
uted ' among' NRC. programs.
Members proposed this matter as an item to be discussed with the Comissioners during a future meeting.
(
-The : Committee decided not to review the proposed restart of the Calvert Cliffs plant when equipment and management deficiencies have been resolved.
O\\
C DESIGNATED ORIGINAL Certified By MM 891/29033(o XA au..
I
s j;p a.
m The Honorable Kenneth M. Carr November 6, 1989 The Committee discussed its plans for the review of NRC staff actions telated to license. extensions.
The first of the future applications for -license extensions is expected to be for the Yankee Rowe plant.
NRC staff review of this extension will be carried out in parallel with the development of the staff's generic guidance / requirements for licensees seeking license exten-sions.
The Comittee decided to review the Yankee Rowe application for a license extension as a separate item.
The Comittee discussed the qualifications of individuals being considered for
' nomination to the Comittee and agreed to send the names of three individuals to the Comission for consideration for appointment as new members.
(See R.
l F. Fraley memorandum to you dated October 13,1989.)
L Since:the last report of ACRS activities, the following subcommittee meetings have been held:
Containment Systems and Structural Engineering, September 12, 1989 - The Subcomittee discussed containment design criteria for future plants with invited speakers from industry and national' laboratories.
Severe Accidents and Probabilistic Risk Assessment, September 19, 1989 -
l The Subcomittee discussed the second draft of ' NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants."
Severe Accidents. - September 20, 1989 - The Subcomittee discussed the-proposed Generic Letter by NRR on accident management _ and the NRC re-J L
search program and NUMARC/EPRI activities in the accident management area.
1 i
- Safety Philoso)hy, Technology, and Criteria, September 26, 1989 - The i
u L
Subcommittee d'scussed the preparation of a joint paper by the ACRS and I
J the NRC which describes their respective positions on " adequate protec-tion."
The Subcomittee discussed the I
Human Factors, ' September 27, 1989 proposed Access Authorization Rule and the NRC staff's work on perform-ance indicators.
Advanced Pressur17ed Water Reactors, September 28, 1989 - The Subcommit-tee discussed the WAPWR (RESAR SP/90) design.
AC/DC-Power Systems Reliability, October 2, 1989 - The Subcommittee discussed. the proposed final resolution of Generic Issue B-56, " Diesel Generator Reliability" and proposed Revision 3 to Regulatory Guide 1.9,
" Selection. Design, Qualification, Testing, and Reliability of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power 1
Plants."
Mechanical Components, October 3,1989 - The Subcomittee discussed the NRC staff's proposed resolution for Generic Issue 87, " Failure of HPCI Steam Line Without Isolation."
.~.
.,:s The Honorable Kenneth M. Carr
-3 November 6, 1989
- Probabilistic Risk Assessment. October 3-4, 1989' - The Subcommittee discussed the uses of and the state of development of probabilistic risk assessment.
FUTURE AGENDA The. Committee agreed to the following tentative schedule for the 355th ACRS meeting, November 16-18,-1989:
Accident Management - Review and comment regarding proposed accident manage-
. ment strategies for consideration in Individual Plant Examinations.
Advanced Pressurized Water Reactors - Briefing by NRC staff members regarding the status of review of the proposed standardized advanced ~ pressurized water reactors.
TMI-2 Accident' Evaluation - Briefing regarding status of the TMI-2 post-accident evaluation effort.
. Nine Mile Point Unit 1 - Review and report on proposed restart of. this BWR plant.
Representatives of the NRC staff and licensee will participate as
- appropriate.
(,
_GE Advanced Boiling Water Reactors - Review and comment on Module I of this standardized advanced BWR design.
Nuclear Power Plant Access Authorization - Review and comment on proposed
-final rule regarding access authorization to controlled areas of nuclear power a
. plants.
Integration of the Regulatory Process Discuss proposed ACRS report-on proposed. integration of the NRC regulatory process.
. Generic Issue B-56, Diesel Reliability and Proposed Regulatory Guide 1.9, Revision 3--
Discuss proposed ACR5 report regarding NRC staff's proposed resolution of this generic issue.
Generic Issue 87, Failure of HPCI Steam Line Without Isolation - Discuss l
proposed ACR5 report regarding NRC staff's proposed resolution of this generic issue.
Sincere l
Forrest J. Remick Chairman l'
i
-