ML20059D662
| ML20059D662 | |
| Person / Time | |
|---|---|
| Issue date: | 08/06/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| TASK-1.D.3, TASK-TM ACRS-SL-0408, ACRS-SL-408, NUDOCS 9311020353 | |
| Download: ML20059D662 (7) | |
Text
r(
=
jaafog*
o UNITED STATES SL-0408 f
~,j NUCLEAR REGULATORY COMMISSION PDR!g/pg3 p
5
. r ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
- [
WASHINGTON. D. C. 20555 o
- .../
s, August 6, 1993 The Honorable Ivan Selin Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED AND NINETY-NINTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JULY 8-9, 1993, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 399th meeting, July 8-9, 1993, the Advisory Committee on Reactor Safeguards ( ACRS) discussed several matters and completed the following reports, memorandum, and letter:
Reports Regulatory Review Group Report (Report to the Honorable Ivan Selin, NRC Chairman, f rom J. Ernest Wilkins. Jr., ACRS Chairman, dated July 15, 1993)
P_ropAsed Draft Regulatory Guides. DG-1023. " Evaluation of Reactor Pressure Vessels with Charpy Upfer-Shelf Energy less Than 50 Ft-Lb." and DC-10l b
" Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence" (Report to James M. Taylor, Executive Director for Opera-tions, from J. Ernest Wilkins, Jr., ACRS Chairman, dated July 15, 1993)
Memorandum Proposed Resolution of Generic issue I.D.3.
" Safety System Status Monitorina" (Memorandum for Warren Minners, Director, Division of Safety issue Resolution, RES, from John T. Larkins, Executive Director, ACRS, dated July 16, 1993.)
Consistent with the Committee's decision, Dr.
Larkins informed Mr. Minners that the Committee had decided not to review the proposed resolution of Generic Issue 1.D.3.
Letter Process for Expediting the issuance of Information Notices (letter to Mr.
Steven Sholly, Senior Consultant, MHB Technical Associates, from John T.
Larkir Executive Director, ACRS, dated July 16, 1993.) Consistent with the Committee's decision, Dr. Larkins informed Mr. Sholly that the Committee forwarded his request for an investigation of the process for Pediting the issu nce f Inf rm ti n N tices t the NRC Executive 0*% @> Inector for Operations for consideration and disposition.
15.31 CW m ORI Gi ML9311020353 930806 7
% \\n
4
\\
i SL-0408 PDR p
Certined By_
g
~
(
.]
j i
399th ACRS Meeting 2
July 8-9, 1993 j
HIGHLIGHTS OF KEY ISSVES CONSIDERED BY THE COMMITTEE 1.
NRC Reaulatorv Review Group Report The Committee heard a briefing by and held discussions-with representa-tives of the NRC staff on the report prepared by the Regulatory Review l
Group for public cornment and the proposed rulemaking to implement its recommendations on 10 CFR 50.54.
.3 Conclusion The Committee provided a report on this matter, dated July '15,1993, to Chairman Selin.
2.
Report of the Planning and Procedures Subcommittee As a result of the Planning and Procedures Subcommittee meeting held on July 7, 1993, the following iten's were brought to the attention.of the Committee:
As follow on to Dr. Wilkins' meeting with the NRR Director, Dr.
i Thomas Murley, it was suggested that the ACRS Chairman meet with the NRC Office Directors (NRR, RES, and AE00) and the Deputy Executive Director for Nuclear Reactor Regulation to discuss the relationship between the Committee and the NRC staff. It was agreed that Messrs.
Carroll, Lindblad and Larkins also attend the proposed meeting.
This meeting will be scheduled at an appropriate time in the future.
The members discussed the t.echnical papers to be presented during the Second Quadripartite Meeting of the Advisory Committees on October 11-15, 1993.
At the suggestion of the French particpants, Mr. Carroll will change the subject of his paper from Indi_vidual Plant Examinations to the EPRI titility Requirement Documents.
[0n July 21, 1993, Dr. Wilkins and several members met with Dr. Birkh-ofer, German RSK, to discuss the details of the Quadripartite Meeting.]
3.
Application of Probabilistic Risk Assessment Methods for Rankino Motor-Operated Valves (MOV)
The Committee heard a briefing by and held discussions with represen-tatives of the NRC staff on the preliminary results from an NRC-sponsored research program designed to determine whether MOVs can be ranked ' on a risk importance basis using existing methods.
This research program'is also designed to identify weaknesses with existing methods that could i
result in risk-significant MOVs not being identified.
Conclusion This briefing was for information only.
No action was taken by the Committee.
1
-~
. 399th ACRS Meeting 3
July 8-9, 1993 4.
. Reconciliation of ACRS Comments and Recommendations j
The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
EDO letter dated May 19, 1993, responding to the ACRS report dated April 26, 1993 (revised June 24, 1993), concerning implementation guidance for the Maintenance Rule.
Conclusion The above EDO letter satisfactorily addressed the Committee's l
comments.
EDO letter dated June 8, 1993, responding to the ACRS report dated April 23, 1993, concerning the prioritization of Generic issue 152,
" Design Basis for Valves that Might be Subjected to Significant Blowdown loads."
Conclusion The Committee did not raise any objections to the ED0's response.
However, Mr. Michelson believes that there are some questions that still need to be discussed with the staff during the Mechanical Components Subcommittee meeting scheduled for August 17, 1993.
If these questions are not adequately resolved, Mr. Michelson will i
advise the Committee as to what additional actions should be taken.
E00 letter dated June 15, 1993, responding to the ACRS report dated
=
May 20, 1993, concernirg Proposed Resolution of Generic Issue 105,
" Interfacing Systems LOCA in LWRs."
f Conclusion The above EDO letter satisfactorily addressed the Committee's comments.
EDO letter dated June 28, 1993, responding to the ACRS report dated May 26, ' '13 (revised June 16, 1993), concerning the staff approach for asse.3ing the consistency of the present regulations with respect to De Commission's Safety Goal Policy.
Conclusion The above ED0 letter satisfactorily addressed the Committee's comments.
tr 1
i I
e
. 399th ACRS Meeting 4
July 8-9, 1993 ED0 letter dated June 30, 1993, responding to the ACRS report dated-
=
June 18, 1993, concerning i_nformation relevant to a number - of international meetings on digital instrumentation and control in which the NRC staff members were participants.
Conclusion The Committee noted that the material provided did not seem to address the NRC staff's lessons learned from these meetings.
Dr.
Lewis suggested that the members would learn more from Mr. Russell, Associate Director, NRR, who offered to appear before the Committee to discuss the information on digital instrumentation and control issues that was acquired during these meetings.
EDO letter dated July 6, 1993, responding to the ACRS report dated May 20, 1993, concerning Draft Report of the PRA Working Group.
Conclusion The above EDO letter satisfactorily addressed the Committee's comments.
5.
Plans for Completina the ACRS Review of the Advanced Boilina Water Reactor (ABWR) Standard Safety Analysis Report (SSAR)
Mr. Michelson summarized the discussions that took place during a site visit and meeting of the Subcommittee on Advanced Boiling Water-Reactors in San Jose, California, on June 1S-17, 1993.
Mr. Douglas Coe, ACRS staf f, briefly summarized what is currently known with regard to the Quad Cities Nuclear Power Plant HPCI rupture event that occurred on June 9, 1993.
Mr. Coe noted that the NRr
' "' had not yet issued its inspection report, and thai. the cause of fai mr.
.till under investigation.
Mr. Michelson discussed the lessons learned from this event that would be applied to the review of the ABWR design.
Mr. Mark Stella, ACRS Senior Fellow, briefed the Committee on the ABWR -
+
reactor water cleanup system evaluation and the outstanding issues that General Electric Corporation will be addressing.
During the discussion of the schedule for completing the ACRS review of the GE ABWR design, it was noted that the ACRS review schedule is based on the assumption that GE will provide the final SSAP by July 31, 1993.
If ACRS does not receive the SSAR by this date, the review schedule may be adversely impacted.
Also, the Committee decided to review the security i
aspects of the ABWR design, but not the technical specifications and SAMDA issues.
P
,my-9 y
-y---yy c-
-=-v-erv v ya r
,e+
-w
=
=
_ ______.~_
t t
399th ACRS Meeting 5
July 8-9, 1993 6.
Draf t Reaulatory Guides DG-1025. " Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence" and DG-1023. " Evaluation of Reactor Pressure Vessels with Charry udder-Shelf Enerav Less Than 50 Ft-lb."
The Committee was briefed by and held discussions with representatives of the NRC staff regarding draft regulatory guides on the methodology for determining pressure vessel neutron fluence and on the evaluation of reactor pressure vessels with Charpy upper-shelf energy less than 50 ft-lb.
Conclusion In its report dated July 15, 1993, on Draft Regulatory Guides DG-1025,
" Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" and DG-1023, " Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb," the Committee stated that it would review the proposed final versions of these guides after the public comments have been reconciled and before they are published in final form.
7.
Debris Pluaaina of Emeraency Core Coolina Suction Line Strainers The Committee heard a briefing by and held discussionc with representa-tives of the NRC staff on the potential for debris plugging of emergency core cooling suction line strainers. The NRC staff provided an update on its activities to evaluate the need for action by U. S. licensees to address this issue as a result of the lessons learned from the events at i
the Barseback Nuclear Power Plant Unit 2 in Sweden and at the Perry Nuclear Power Plant.
Conclusion The NRC staff will continue to keep the Committee informed regarding the outcome of its reevaluation of the containment emergency sump blockage issue and the decision regarding the need for additional regul atory action.
8.
Reactor Operatina Experience The Committee heard a briefing by and held discussions with represen-tatives of the NRC staff on the March 1, 1993, event at Sequoyah Nuclear Power Plant Unit 2 that involved a rupture of an extraction steam header line. The Committee also discussed the NRC generic communications related to erosion / corrosion problems.
Conclusion This briefing was for information only, No Committee action was taken.
~
4 i
t l
"399th ACRS Meeting 6
July 8-9, 1993 i
i 9.
Subcommittee Meetinas During the period from June 10 to July 7,1993, the following Subcommittee meetings were held:
r Advanced Boilina Water Reactors - June-15-17, 1993 (San Jose.
1
+
The Subcommittee visited the General Electric Nuclear Energy (GE) facility and held a subcommittee meeting during which it reviewed matters related to the GE Standard Safety Analysis Report for the Advanced Boiling Water Reactor design.
Materials and Metallurav - June 29, 1993 The Subcommittee reviewed draft Regul atory Guides, DG-1023,
" Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb,"
and DG-1025,
" Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."
Requlatory Policies and Practices - July 7, 1993
=
The Subcommittee reviewed the report of the NRC Regulatory Review Group.
Plannina and Procedures - July 7, 1993 The Subcommittee discussed proposed activities, practices, and procedures relating to ACRS and related matters.
10.
f_uture ACRS Activities The Committee agreed to consider the following during the 400th ACRS Meeting, August 5-7, 1993, Bethesda, Maryland:
Remainina Policy Issues for Passive Plant Desians Review and comment on the draf t Commission paper on the remaining policy issues related to the passive plant designs and outstanding issues related to the ED0's responses to ACRS concerns.
Representatives of the NRC staff and the industry will participate.
Proposed Resolution of Generic Safety issue 57.
" Effects of Fire Protection System Ac_tuation on Safety-Related Eauipment." and the lessons Learned from the la Salle Fire PRA - Review and comment on the proposed resolution of Generic Safety Issue 57 and the lessons Learned from the La Salle Fire PRA.
Representatives of the NRC staff will participate.
Representatives of the industry will participate, as appropriate.
5 1
399th ACRS Fteting July 8-9,~1993 7
Proposed Resolution of Generic Issue 143. " Availability of Chilled Water Systems and Room Coolina" Review and comment on the NRC staff's proposed resolution of Generic Issue 143.
Representatives of the NRC staff will participate.
Advanced Licht Water Reactor Policy Issue on Emeroency Plannina - Review and cyament on a draf t Commission paper related to emergency planning for advanced light water reactors.
Representatives of the NRC staff will participate.
Resolation of ACRS Comment s and Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
Report of the Planning and Procedures Subcommittee -
Hear a report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business.
ACRS Subcommittee Activities Hear reports and hold discussions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena and Advanced Boiling Water Reactors.
Future Activities Discuss anticipated and proposed Committee activities, and organizational matters, as appropriate.
Also, discuss matters and specific issues that were not completed during previous meetings as time and availability of information permit.
Sincerely, f
k J. Ernest Wilkins, Jr.
Chairman i