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UNITED STATES f j' . .+ '' gn                NUCLEAR REGULATORY COMMISSION
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                    $ .g' / ,                   ADVISORY COMMITTEE ON REACTOR SAFEGUARDS                       ,
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS p
g                           WASHINGTON, D. C. 20555
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g WASHINGTON, D. C. 20555 o%g......f August 4, 1988 4
August 4, 1988 4
The Honorable Lando W. Zech, Jr.
The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission                                           '
Chairman U.S. Nuclear Regulatory Comission Washington, D.C. 20555
Washington, D.C. 20555


==Dear Chairman Zech:==
==Dear Chairman Zech:==
==SUBJECT:==
==SUBJECT:==
THREE HUNDRED AND THIRTY-NINTH MEETING OF THE ADVISORY' COMMITTEE ON REACTOR SAFEGUARDS, JULY 14-16, 1988 The Advisory Comittee on Reactor Safeguards held its 339th meeting in Washington, D.C., on July 14-16, 1988. A sumary of actions is present-       '
THREE HUNDRED AND THIRTY-NINTH MEETING OF THE ADVISORY' COMMITTEE ON REACTOR SAFEGUARDS, JULY 14-16, 1988 The Advisory Comittee on Reactor Safeguards held its 339th meeting in Washington, D.C., on July 14-16, 1988. A sumary of actions is present-ed below:
ed below:
ACRS Reoort on Key Licensing issues Associated with DOE Sponsored Reactor, Designs (Letter to Chairman Zech dated July 20, 1988)
ACRS Reoort on Key Licensing issues Associated with DOE Sponsored
[
;                                  Reactor , Designs (Letter to Chairman Zech dated July 20, 1988)             [
i Report on the Integration Plan for Closure of Severe Accident Issues (SECY-88-141)
i                                 Report on the Integration Plan for Closure of Severe Accident Issues (SECY-88-141)     (Letter to Chairman Zech dated July 20, 1988)
(Letter to Chairman Zech dated July 20, 1988)
Report on Proposed Revised Policy Statement on Nuclear Power Plant Staff     ,
Report on Proposed Revised Policy Statement on Nuclear Power Plant Staff Working Hours (letter to Chairman Zech dated July 20. 1988)
Working Hours     (letter to Chairman Zech dated July 20. 1988)             ,
Reports on the subjects noted above have been sent to you.
Reports on the subjects noted above have been sent to you.
Coments on the NRC Staff's Draf t Safety Evaluation of the Westinghouse
Coments on the NRC Staff's Draf t Safety Evaluation of the Westinghouse To~pical Report. WCAP-10924, "Westinghouse Large-Break LOCA Best-Estimate l
!                                To~pical Report. WCAP-10924, "Westinghouse Large-Break LOCA Best-Estimate   l
!!ethodology" (Letter to the Executive Director for Operations, dated TuTy 20,1988)
                                  !!ethodology" (Letter to the Executive Director for Operations, dated       !
[
TuTy 20,1988)                                                               [
r A copy of this letter has betn sent to you.
r A copy of this letter has betn sent to you.                                 !
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND RE0VF.STS f
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND RE0VF.STS                         f r
r i
i                                The Comittee was briefed by the NRC Staff on the integration plan for       !
The Comittee was briefed by the NRC Staff on the integration plan for closure of severe accident issues.
closure of severe accident issues.
The Committee met with the Commission to discuss ACRS recomendations on f
The Committee met with the Commission to discuss ACRS recomendations on     f the proposed generic letter on Individual Plant Examinations and the         i proposed integrated Safety Assessment Program.                               :
the proposed generic letter on Individual Plant Examinations and the i
The Comittee was briefed by the NRC Staff, consultants, and representa-     I
proposed integrated Safety Assessment Program.
,                                tives of Westinghouse Electric Corporation on an improved method for predicting the performance of the Emergency Core Cooling System (ECCS) i sL40340 PNV                                               N%           ;
The Comittee was briefed by the NRC Staff, consultants, and representa-I tives of Westinghouse Electric Corporation on an improved method for predicting the performance of the Emergency Core Cooling System (ECCS)
                                                                                                  \:\
PNV N%
                                                                                                    \         l
sL40340 i
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The Honorable Lando W. Zech, Jr.           2               August 4, 1988         '
The Honorable Lando W. Zech, Jr.
j during a large-break loss of coolant accident in two-loop PWRs of Westinghouse design.
2 August 4, 1988 j
The Comittee was briefed by NRC Staff and their consultants on the                 i l             Equipment Qualification-Risk Scoping Study.       The Comittee postponed the     l writing of a report until the next meeting in order to have additional time to study a set of peer review reports on the EQ-Risk Scoping Study that were received shortly before the meeting.
during a large-break loss of coolant accident in two-loop PWRs of Westinghouse design.
The Comittee was briefed by NRC Staff and a representative of DOE on the NRC Staff's proposed draf t SER for the modular high temperature gas           '
The Comittee was briefed by NRC Staff and their consultants on the i
cooled reactor conceptual design. The Comittee anticipates completing             ,
l Equipment Qualification-Risk Scoping Study.
;              its review during the 340th ACRS meeting.                                         ,
The Comittee postponed the l
The Comittee was briefed by NRC Staff on the laSalle 2 Nuclear Station
writing of a report until the next meeting in order to have additional time to study a set of peer review reports on the EQ-Risk Scoping Study that were received shortly before the meeting.
:              power oscillation event and AE00 recommendr,tions based on the event               -
The Comittee was briefed by NRC Staff and a representative of DOE on the NRC Staff's proposed draf t SER for the modular high temperature gas cooled reactor conceptual design.
4              study. Dr. Kerr assigned the LaSalle 2 tvent review (requested by j             Chairman Zech) to the joint Subcomitbes on Core Perfonnance and Thermal Hydraulic Phenomena.                                                       ,
The Comittee anticipates completing its review during the 340th ACRS meeting.
The Comittee was briefed by NRC Staff on operating events involving service water failures and degradation in LWRs from 1980 to 1987. The             l Comittee took no action.                                                           '
The Comittee was briefed by NRC Staff on the laSalle 2 Nuclear Station power oscillation event and AE00 recommendr,tions based on the event study.
AE00 also briefed the Comittee on the results of their study of nuclear i             power plant service water cooling systems.
Dr. Kerr assigned the LaSalle 2 tvent review (requested by 4
!                                                                                                !f
j Chairman Zech) to the joint Subcomitbes on Core Perfonnance and Thermal Hydraulic Phenomena.
!            The Comittee was briefed by the NRC Staff on their current schedule for
The Comittee was briefed by NRC Staff on operating events involving service water failures and degradation in LWRs from 1980 to 1987.
:            restart of the Pilgrim Nuclear Plant.         The Comittee received assurance       :
The l
I            that NRR will schedule the review so as to provide time for Comittee               i
Comittee took no action.
!            review of the plant restart.
AE00 also briefed the Comittee on the results of their study of nuclear i
l           The Comittee was briefed by the NRC Staff on the proposed policy                   !
power plant service water cooling systems.
;            staterocnt on nuclear power plant working hours.                                   l l           The Comittee discussed and approved the revision of the Memorandum of
The Comittee was briefed by the NRC Staff on their current schedule for f
;            Understanding between ACRS and NRC regarding procedures for dealing with
restart of the Pilgrim Nuclear Plant.
;            NRC Rules and Folicy Matters,                                                       !
The Comittee received assurance I
r Mr. C. Michelson suggested that the AE0D Staff review the Browns Ferry j           fire in an effort to determine if there are any generic lessons to be               .
that NRR will schedule the review so as to provide time for Comittee i
;            learned. The AE00 Staff agreed to this task.
review of the plant restart.
l The Comittee was briefed by the NRC Staff on the proposed policy staterocnt on nuclear power plant working hours.
l l
The Comittee discussed and approved the revision of the Memorandum of Understanding between ACRS and NRC regarding procedures for dealing with NRC Rules and Folicy Matters, r
Mr. C. Michelson suggested that the AE0D Staff review the Browns Ferry j
fire in an effort to determine if there are any generic lessons to be learned. The AE00 Staff agreed to this task.
[
[
Dr. W. Kerr reported on the reorganization of TVA and the recent re-               '
Dr. W. Kerr reported on the reorganization of TVA and the recent re-duction of personnel in TVA nuclear activities.
;            duction of personnel in TVA nuclear activities.                                     ;
i t
i t
!            Since the last report of ACRS activities, the following subcomittee                 t treetings have been held:
Since the last report of ACRS activities, the following subcomittee t
l                                                                                               [
treetings have been held:
:                                                                                                  1 1                                                                                               ,
l
[
1 1
l
l


The Honorable Lando W. Zech, Jr.         3               August 4, 1988 Reliability Assurance, June 14, 1988 - For a briefing on the final conclusions of the Equipment Qualification-Risk Scoping Study.
The Honorable Lando W. Zech, Jr.
3 August 4, 1988 Reliability Assurance, June 14, 1988 - For a briefing on the final conclusions of the Equipment Qualification-Risk Scoping Study.
Maintenance Practices and Procedures, June 15, 1988 - For a brief-ing by RES on the current status of the Maintenance Rule.
Maintenance Practices and Procedures, June 15, 1988 - For a brief-ing by RES on the current status of the Maintenance Rule.
Thermal Hydraulic Phenomena, June 21, 1988 - To review the status of the MIST Phase III and IV Programs and the proposed 0TSG Follow-On Program.
Thermal Hydraulic Phenomena, June 21, 1988 - To review the status of the MIST Phase III and IV Programs and the proposed 0TSG Follow-On Program.
Line 91: Line 97:
Severe Accidents, July 13, 1988 - To discuss the integration plan for closure of severe accident issues.
Severe Accidents, July 13, 1988 - To discuss the integration plan for closure of severe accident issues.
FUTURE ACTIVITIES The following items have been proposed for consideration during the ACRS meeting on August 11-13, 1988:
FUTURE ACTIVITIES The following items have been proposed for consideration during the ACRS meeting on August 11-13, 1988:
Hierarchical _ Structure for Safety-Pelated Items         - Discuss proposed hierarchical structure and related ACRS action regarding important safety-related issues identified by ACR$ members.
Hierarchical _ Structure for Safety-Pelated Items Discuss proposed hierarchical structure and related ACRS action regarding important safety-related issues identified by ACR$ members.
Meetino with Executive Director for Operations - Discuss status of and plans for completion and promulgation of NUREG-1150 (Final), Reactor Risk Reference Document.
Meetino with Executive Director for Operations - Discuss status of and plans for completion and promulgation of NUREG-1150 (Final), Reactor Risk Reference Document.
BWR Power OscillatioS - Briefing by invited expert regarding power oscillations in BWRs.
BWR Power OscillatioS - Briefing by invited expert regarding power oscillations in BWRs.
Decay Heat Removal Systems - Review and comm.ent bn proposed HRC resolu-tion of USI A-45 and GI-99.
Decay Heat Removal Systems - Review and comm.ent bn proposed HRC resolu-tion of USI A-45 and GI-99.
Standardization of Nuclear Power Plants - Briefing regarding Chapters 2, 3, 4, and 5 of EPRI document on standardization of improved nuclear power plants.
Standardization of Nuclear Power Plants - Briefing regarding Chapters 2, 3,
4, and 5 of EPRI document on standardization of improved nuclear power plants.
USI A-17,_"Systems Interactions" - Review and comment regarding proposed resolution of U5I A-17 USI A-47, Safety implications of Control Systems - Review and comment on proposed assumptions and instructions that the Staff intends to provide to ORNL for use in the Multiple System Response Program for evaluating outstanding issues associated with proposed resolution of USI A-47.
USI A-17,_"Systems Interactions" - Review and comment regarding proposed resolution of U5I A-17 USI A-47, Safety implications of Control Systems - Review and comment on proposed assumptions and instructions that the Staff intends to provide to ORNL for use in the Multiple System Response Program for evaluating outstanding issues associated with proposed resolution of USI A-47.
TVA Nuclear Power Plant Operations - Discuss the Staff's report on lessons   learned   from TVA       ranagement operations   and construction
TVA Nuclear Power Plant Operations - Discuss the Staff's report on lessons learned from TVA ranagement operations and construction


i e
i e
The Honorabic'Lando W. Zech, Jr.       4               August 4, 1988 problems. Prepare coments to the NRC Commissioners per SRM request dated March 2,1988 [SECY 87-211] (September 1,1988 suspense date)       -
The Honorabic'Lando W. Zech, Jr.
NRC Rulemaking Activities on Nuclear Plant Maintenance - Discuss NRC       ,
4 August 4, 1988 problems.
activities for developing requirements for maintenance programs.           j Modular liigh Temperature Gas-Cooled Reactors - Review and coment on standardizec design for the DOE proposed Modular HTGR.                     i The following items have been proposed for consideration during the ACRS reeting on September 8-10, 1988:
Prepare coments to the NRC Commissioners per SRM request dated March 2,1988 [SECY 87-211] (September 1,1988 suspense date)
NRC Rulemaking Activities on Nuclear Plant Maintenance - Discuss NRC activities for developing requirements for maintenance programs.
j Modular liigh Temperature Gas-Cooled Reactors - Review and coment on standardizec design for the DOE proposed Modular HTGR.
i The following items have been proposed for consideration during the ACRS reeting on September 8-10, 1988:
Diagnostic Evaluation Program - Briefing by AE00 regarding diagnostic assessment of McGuire and Dresden Stations.
Diagnostic Evaluation Program - Briefing by AE00 regarding diagnostic assessment of McGuire and Dresden Stations.
lJSI A-48, Hydrogen Control Requirements - Briefing regarding proposed resolution of hydrogen control requirements for Mark III and ice con-denser containment types.
lJSI A-48, Hydrogen Control Requirements - Briefing regarding proposed resolution of hydrogen control requirements for Mark III and ice con-denser containment types.
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Thermal-Hydraulic Phenomena - Status of the MIST and OTSG follow-on research programs.
Thermal-Hydraulic Phenomena - Status of the MIST and OTSG follow-on research programs.
Emergency Planning - Briefing regarding full Federal Emergency Prepared-ness Exercise at Zion Station.
Emergency Planning - Briefing regarding full Federal Emergency Prepared-ness Exercise at Zion Station.
Irolications of Chernobyl Accident - Briefing regarding status of NUlEG-1251, "Implications of Chernobyl," and review of the staff's program at BNL to address severe reactivity transients.         Comittee coments have been requested regarding the BNL program.
Irolications of Chernobyl Accident Briefing regarding status of NUlEG-1251, "Implications of Chernobyl," and review of the staff's program at BNL to address severe reactivity transients.
License Renewal - ACRS comments requested regaroing NUREG-1317. "Regu-latory Consideratior.s Pertaining to Nuclear Power Plant License Renewal, Status Report to the ACRS" provided 6/15/88 RESAR SP/00 (WAPR) - ACRS coments requested for preliminary design IIpproval of the standardized Westinghouse Nuclear Power Plant. NRC Staff evaluation expected by August 1988.
Comittee coments have been requested regarding the BNL program.
License Renewal - ACRS comments requested regaroing NUREG-1317. "Regu-latory Consideratior.s Pertaining to Nuclear Power Plant License Renewal, Status Report to the ACRS" provided 6/15/88 RESAR SP/00 (WAPR) - ACRS coments requested for preliminary design IIpproval of the standardized Westinghouse Nuclear Power Plant.
NRC Staff evaluation expected by August 1988.
0?erating Procedures for Severe Accidents - Briefing by NRR regarding tie status of operating procedures for severe accidents.
0?erating Procedures for Severe Accidents - Briefing by NRR regarding tie status of operating procedures for severe accidents.
Pilgrim Nuclear Plant - ACRS review of plans for restart of the shut-down reactor.
Pilgrim Nuclear Plant - ACRS review of plans for restart of the shut-down reactor.
Peach Gotton Nuclear Power Plant - ACRS review regarding restart of the currently shut-down reactor.       NRC Staff evaluatiun expected by late August.
Peach Gotton Nuclear Power Plant - ACRS review regarding restart of the currently shut-down reactor.
NRC Staff evaluatiun expected by late August.


The Honorable Lando W. Zech, Jr.       5               August 4, 1988 Regulatory Guide 1.106, Rev. 2, Thermal Overload Protection for Motor ,
The Honorable Lando W. Zech, Jr.
Operated Valves for Nuclear Power Plants       -
5 August 4, 1988 Regulatory Guide 1.106, Rev. 2, Thermal Overload Protection for Motor,
Subcommittee Chairman's report regarding proposed revision cf this Regulatory Guide.
Operated Valves for Nuclear Power Plants Subcommittee Chairman's report regarding proposed revision cf this Regulatory Guide.
Advanced DOE Liquid Metal Cooled Reactor     -
Advanced DOE Liquid Metal Cooled Reactor ACRS conrnents requested regarding approval of design concept for this standardized liquid metal cooled reactor. NRC Staff evaluation package expected by August 1988.
ACRS conrnents requested regarding approval of design concept for this standardized liquid metal cooled reactor. NRC Staff evaluation package expected by August 1988.
Sincerely, b
Sincerely, b
II. Kerr Chairman
II. Kerr Chairman


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      +*pe neo                             UNITED STATES
NUCLEA6 HEGULATORY COMMISSION
    !            n'             NUCLEA6 HEGULATORY COMMISSION f
^
^
B                       ' ADVISORY COMMITTEE ON REACTOR S -         UARDS ft g           f     .                  WASHINGTON, D. C. 20666 November 9, 1988 MEMORANDUM FOR: Jim McKnight Document Control Systems                                                     .
B ft
L           '
' ADVISORY COMMITTEE ON REACTOR S -
FROM:             Ethel Barnard Advisory Comi tee o R ctor Safeguards
UARDS f
                                                                                                                \
g f
WASHINGTON, D. C. 20666 November 9, 1988 MEMORANDUM FOR: Jim McKnight Document Control Systems L
FROM:
Ethel Barnard Advisory Comi tee o R ctor Safeguards
\\
lhe attached ACRS Documents are being provided to you for listing on the accessions list, Please forward to the Public Document Room.
lhe attached ACRS Documents are being provided to you for listing on the accessions list, Please forward to the Public Document Room.
Attachments:
Attachments:
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l l
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                                                                              \f0
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                                                        )
)
ACRS MINUTES AND CCNSULTANT REPORTS (PDR 110988)
ACRS MINUTES AND CCNSULTANT REPORTS (PDR 110988) 1.
: 1.               CT-1934 Schrock ltr 7/6/88 to Ward re Resolution of UPI Model Concerns Through W use of WCOBRA/ TRAC as Best Estimate Tool Under ProvisTons of SECY83-472
CT-1934 Schrock ltr 7/6/88 to Ward re Resolution of UPI Model Concerns Through W use of WCOBRA/ TRAC as Best Estimate Tool Under ProvisTons of SECY83-472 2.
: 2.               CT-1935 Catton remo 7/10/88 to Boehnert re Technical Program Group (TPG) Meating - Code Scaling Applicability and Uncertainty (CSAU) Methodology, San Jose, CA, 6/9-10/88
CT-1935 Catton remo 7/10/88 to Boehnert re Technical Program Group (TPG) Meating - Code Scaling Applicability and Uncertainty (CSAU) Methodology, San Jose, CA, 6/9-10/88 3.
: 3.               CT-1936 Barton memo 7/25/88 to Wylie re 7/22/88 Meeting of ACRS TVA Organizational Issues Subete, Review of Staff's TVA Lessons Learned Effoti                                                                                                                               l
CT-1936 Barton memo 7/25/88 to Wylie re 7/22/88 Meeting of ACRS TVA Organizational Issues Subete, Review of Staff's TVA l
: 4.               CT-1937 Sullivan ltr 8/4/88 to Ward re 7/21/88 Thermal-Hydraulic                                                                                             l Subete Meeting on Systen Effects Test Programs and OTSG Follow-on Program Results                                                                                                                           ,
Lessons Learned Effoti 4.
: 5.               CT-1938 Lee ltr 8/5/88 to El-Zeftawy re Advanced Reactor Designs Subete Meeting 8/3/88 on MHTGR Concept
CT-1937 Sullivan ltr 8/4/88 to Ward re 7/21/88 Thermal-Hydraulic l
: 6.               CT-1939 Tien ltr 8/8/88 to Boehnert re Thermal-Hydraulic Phenomena Subete Meeting 7/21/88 on MIST Program and 0TSG Follow-on Program
Subete Meeting on Systen Effects Test Programs and OTSG Follow-on Program Results 5.
: 7.               CT-1940 Avery ltr 10/26/88 to Ward re Advanced Reactor Designs Subete Meeting 10/5/88 en PRISM SER Oraft Report
CT-1938 Lee ltr 8/5/88 to El-Zeftawy re Advanced Reactor Designs Subete Meeting 8/3/88 on MHTGR Concept 6.
: 8.               ACRS-2545 Advanced Reactor Designs Subete Meeting, January 6, 1988
CT-1939 Tien ltr 8/8/88 to Boehnert re Thermal-Hydraulic Phenomena Subete Meeting 7/21/88 on MIST Program and 0TSG Follow-on Program 7.
: 9.               ACRS-2575 S&W Reactor Plants Subete Meeting, May 3-4, 1988
CT-1940 Avery ltr 10/26/88 to Ward re Advanced Reactor Designs Subete Meeting 10/5/88 en PRISM SER Oraft Report 8.
: 10. ACRS-2577 337th ACRS Meeting, May 5-7, 1988                                                                                                                                 '
ACRS-2545 Advanced Reactor Designs Subete Meeting, January 6, 1988 9.
!              11. ACRS-2582 Improved Light Water Reactors Subete Meeting, May 31, 1988 f
ACRS-2575 S&W Reactor Plants Subete Meeting, May 3-4, 1988
: 10. ACRS-2577 337th ACRS Meeting, May 5-7, 1988
: 11. ACRS-2582 Improved Light Water Reactors Subete Meeting, May 31, 1988 f
: 12. ACRS-2583 Advanced Boiling Water Reactor Subetc Meeting, June 1, 1988
: 12. ACRS-2583 Advanced Boiling Water Reactor Subetc Meeting, June 1, 1988
: 13. ACRS-2584 338th ACRS Meeting, June 2-4, 1988
: 13. ACRS-2584 338th ACRS Meeting, June 2-4, 1988
Line 156: Line 173:
: 15. ACRS-2580 Maintenance Practicas & Procedures Subete Meeting, June 15, 1988 (continued)
: 15. ACRS-2580 Maintenance Practicas & Procedures Subete Meeting, June 15, 1988 (continued)


ACRS MINUTES AND CONSULTANT REPORTS                       (PDR 110988)
ACRS MINUTES AND CONSULTANT REPORTS (PDR 110988)
: 16. ACRS-2588 Advanced Reactor Designs Subete Meeting, June 22, 1988
: 16. ACRS-2588 Advanced Reactor Designs Subete Meeting, June 22, 1988
: 17. ACRS-2589 Severe Accidents Subete Meeting. .'uly 13, 1988
: 17. ACRS-2589 Severe Accidents Subete Meeting..'uly 13, 1988
: 18. ACRS-2590 339th ACRS Meeting, July 14-16, 1988
: 18. ACRS-2590 339th ACRS Meeting, July 14-16, 1988
: 19. ACRS-2591 Thennal Hydraulic Phenomena Subete Meeting (Status of MIST Phase III & IV Programs & Proposed 0TSG Follow-on),
: 19. ACRS-2591 Thennal Hydraulic Phenomena Subete Meeting (Status of MIST Phase III & IV Programs & Proposed 0TSG Follow-on),
July 21, 1988
July 21, 1988
: 20. ACRS-2592 TVA Organizational Issues Subete Meeting, July 22, 1988
: 20. ACRS-2592 TVA Organizational Issues Subete Meeting, July 22, 1988
: 21. ACRS-2593 Decay Heat Removal Systems Subete Meeting (Resolution of US! A-45/ Status of Resolution of GI 99), July 27,1988   ,
: 21. ACRS-2593 Decay Heat Removal Systems Subete Meeting (Resolution of US! A-45/ Status of Resolution of GI 99), July 27,1988
: 22. ACRS-2594 Advanced Peactors Designs Subcte Meeting, August 3, 1988
: 22. ACRS-2594 Advanced Peactors Designs Subcte Meeting, August 3, 1988
: 23. ACRS-2595 Safety Philosophy, Tec5nclogy & Criteria Subete Meeting, August 4, 1988
: 23. ACRS-2595 Safety Philosophy, Tec5nclogy & Criteria Subete Meeting, August 4, 1988
Line 174: Line 191:
: 29. ACRS-2002 Maintenance Pre Sices & Procedures Subete Meeting, September 7, 1>LB
: 29. ACRS-2002 Maintenance Pre Sices & Procedures Subete Meeting, September 7, 1>LB
: 30. ACRS-2604 Mechanical Components Subete Meeting October 4, 1988
: 30. ACRS-2604 Mechanical Components Subete Meeting October 4, 1988
: 31. SL-0348     Kerr ACRS ltr 8/4/88 to Zech NRC, Three Hundred and Thirty-Ninth Meeting of the ACR$, July 14-16, 1988 l
: 31. SL-0348 Kerr ACRS ltr 8/4/88 to Zech NRC, Three Hundred and Thirty-Ninth Meeting of the ACR$, July 14-16, 1988 l
: 32. SL-0349     Kerr ACRS itr 9/6/88 to Zech NRC, Three Hundred Fortieth Meeting of the ACRS, August 11-13, 1988
32.
: 33. SL-0350     Kerr ACRS lte 10/3/88 to Zech NRC Three Hundred Forty-First Meeting of the ACRS. Septcmber 8-10, 1988   i 34   SL-0351     Kerr ACRS ltr 10/25/88 to Zech NRC. Three Hundred Forty-Second Meeting of the ACRS, October 6-7, 1988}}
SL-0349 Kerr ACRS itr 9/6/88 to Zech NRC, Three Hundred Fortieth Meeting of the ACRS, August 11-13, 1988
: 33. SL-0350 Kerr ACRS lte 10/3/88 to Zech NRC Three Hundred Forty-First Meeting of the ACRS. Septcmber 8-10, 1988 i
34 SL-0351 Kerr ACRS ltr 10/25/88 to Zech NRC. Three Hundred Forty-Second Meeting of the ACRS, October 6-7, 1988}}

Latest revision as of 02:26, 7 December 2024

Summarizes ACRS 339th Meeting on 880714-16 in Washington,Dc to Discuss ACRS Rept on Key Licensing Issues Re DOE- Sponsored Reactor Designs & SECY-88-147.E Barnard 881109 Memo Encl
ML20206B342
Person / Time
Issue date: 08/04/1988
From: Kerr W
Advisory Committee on Reactor Safeguards
To: Zech L
NRC COMMISSION (OCM)
References
ACRS-SL-0348, ACRS-SL-348, NUDOCS 8811150418
Download: ML20206B342 (8)
v • d • e


Text

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UNITED STATES f j'..+ g NUCLEAR REGULATORY COMMISSION n

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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS p

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The Honorable Lando W. Zech, Jr.

Chairman U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Dear Chairman Zech:

SUBJECT:

THREE HUNDRED AND THIRTY-NINTH MEETING OF THE ADVISORY' COMMITTEE ON REACTOR SAFEGUARDS, JULY 14-16, 1988 The Advisory Comittee on Reactor Safeguards held its 339th meeting in Washington, D.C., on July 14-16, 1988. A sumary of actions is present-ed below:

ACRS Reoort on Key Licensing issues Associated with DOE Sponsored Reactor, Designs (Letter to Chairman Zech dated July 20, 1988)

[

i Report on the Integration Plan for Closure of Severe Accident Issues (SECY-88-141)

(Letter to Chairman Zech dated July 20, 1988)

Report on Proposed Revised Policy Statement on Nuclear Power Plant Staff Working Hours (letter to Chairman Zech dated July 20. 1988)

Reports on the subjects noted above have been sent to you.

Coments on the NRC Staff's Draf t Safety Evaluation of the Westinghouse To~pical Report. WCAP-10924, "Westinghouse Large-Break LOCA Best-Estimate l

!!ethodology" (Letter to the Executive Director for Operations, dated TuTy 20,1988)

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r A copy of this letter has betn sent to you.

OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND RE0VF.STS f

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The Comittee was briefed by the NRC Staff on the integration plan for closure of severe accident issues.

The Committee met with the Commission to discuss ACRS recomendations on f

the proposed generic letter on Individual Plant Examinations and the i

proposed integrated Safety Assessment Program.

The Comittee was briefed by the NRC Staff, consultants, and representa-I tives of Westinghouse Electric Corporation on an improved method for predicting the performance of the Emergency Core Cooling System (ECCS)

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The Honorable Lando W. Zech, Jr.

2 August 4, 1988 j

during a large-break loss of coolant accident in two-loop PWRs of Westinghouse design.

The Comittee was briefed by NRC Staff and their consultants on the i

l Equipment Qualification-Risk Scoping Study.

The Comittee postponed the l

writing of a report until the next meeting in order to have additional time to study a set of peer review reports on the EQ-Risk Scoping Study that were received shortly before the meeting.

The Comittee was briefed by NRC Staff and a representative of DOE on the NRC Staff's proposed draf t SER for the modular high temperature gas cooled reactor conceptual design.

The Comittee anticipates completing its review during the 340th ACRS meeting.

The Comittee was briefed by NRC Staff on the laSalle 2 Nuclear Station power oscillation event and AE00 recommendr,tions based on the event study.

Dr. Kerr assigned the LaSalle 2 tvent review (requested by 4

j Chairman Zech) to the joint Subcomitbes on Core Perfonnance and Thermal Hydraulic Phenomena.

The Comittee was briefed by NRC Staff on operating events involving service water failures and degradation in LWRs from 1980 to 1987.

The l

Comittee took no action.

AE00 also briefed the Comittee on the results of their study of nuclear i

power plant service water cooling systems.

The Comittee was briefed by the NRC Staff on their current schedule for f

restart of the Pilgrim Nuclear Plant.

The Comittee received assurance I

that NRR will schedule the review so as to provide time for Comittee i

review of the plant restart.

l The Comittee was briefed by the NRC Staff on the proposed policy staterocnt on nuclear power plant working hours.

l l

The Comittee discussed and approved the revision of the Memorandum of Understanding between ACRS and NRC regarding procedures for dealing with NRC Rules and Folicy Matters, r

Mr. C. Michelson suggested that the AE0D Staff review the Browns Ferry j

fire in an effort to determine if there are any generic lessons to be learned. The AE00 Staff agreed to this task.

[

Dr. W. Kerr reported on the reorganization of TVA and the recent re-duction of personnel in TVA nuclear activities.

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Since the last report of ACRS activities, the following subcomittee t

treetings have been held:

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1 1

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The Honorable Lando W. Zech, Jr.

3 August 4, 1988 Reliability Assurance, June 14, 1988 - For a briefing on the final conclusions of the Equipment Qualification-Risk Scoping Study.

Maintenance Practices and Procedures, June 15, 1988 - For a brief-ing by RES on the current status of the Maintenance Rule.

Thermal Hydraulic Phenomena, June 21, 1988 - To review the status of the MIST Phase III and IV Programs and the proposed 0TSG Follow-On Program.

Advanced Reactor Designs, June 22, 1988 - To review the draf t SER of the Modular HTGR conceptual design.

Severe Accidents, July 13, 1988 - To discuss the integration plan for closure of severe accident issues.

FUTURE ACTIVITIES The following items have been proposed for consideration during the ACRS meeting on August 11-13, 1988:

Hierarchical _ Structure for Safety-Pelated Items Discuss proposed hierarchical structure and related ACRS action regarding important safety-related issues identified by ACR$ members.

Meetino with Executive Director for Operations - Discuss status of and plans for completion and promulgation of NUREG-1150 (Final), Reactor Risk Reference Document.

BWR Power OscillatioS - Briefing by invited expert regarding power oscillations in BWRs.

Decay Heat Removal Systems - Review and comm.ent bn proposed HRC resolu-tion of USI A-45 and GI-99.

Standardization of Nuclear Power Plants - Briefing regarding Chapters 2, 3,

4, and 5 of EPRI document on standardization of improved nuclear power plants.

USI A-17,_"Systems Interactions" - Review and comment regarding proposed resolution of U5I A-17 USI A-47, Safety implications of Control Systems - Review and comment on proposed assumptions and instructions that the Staff intends to provide to ORNL for use in the Multiple System Response Program for evaluating outstanding issues associated with proposed resolution of USI A-47.

TVA Nuclear Power Plant Operations - Discuss the Staff's report on lessons learned from TVA ranagement operations and construction

i e

The Honorabic'Lando W. Zech, Jr.

4 August 4, 1988 problems.

Prepare coments to the NRC Commissioners per SRM request dated March 2,1988 [SECY 87-211] (September 1,1988 suspense date)

NRC Rulemaking Activities on Nuclear Plant Maintenance - Discuss NRC activities for developing requirements for maintenance programs.

j Modular liigh Temperature Gas-Cooled Reactors - Review and coment on standardizec design for the DOE proposed Modular HTGR.

i The following items have been proposed for consideration during the ACRS reeting on September 8-10, 1988:

Diagnostic Evaluation Program - Briefing by AE00 regarding diagnostic assessment of McGuire and Dresden Stations.

lJSI A-48, Hydrogen Control Requirements - Briefing regarding proposed resolution of hydrogen control requirements for Mark III and ice con-denser containment types.

Valve Testing - Briefing regarding proposed resolution of in-situ MOV testing.

Thermal-Hydraulic Phenomena - Status of the MIST and OTSG follow-on research programs.

Emergency Planning - Briefing regarding full Federal Emergency Prepared-ness Exercise at Zion Station.

Irolications of Chernobyl Accident Briefing regarding status of NUlEG-1251, "Implications of Chernobyl," and review of the staff's program at BNL to address severe reactivity transients.

Comittee coments have been requested regarding the BNL program.

License Renewal - ACRS comments requested regaroing NUREG-1317. "Regu-latory Consideratior.s Pertaining to Nuclear Power Plant License Renewal, Status Report to the ACRS" provided 6/15/88 RESAR SP/00 (WAPR) - ACRS coments requested for preliminary design IIpproval of the standardized Westinghouse Nuclear Power Plant.

NRC Staff evaluation expected by August 1988.

0?erating Procedures for Severe Accidents - Briefing by NRR regarding tie status of operating procedures for severe accidents.

Pilgrim Nuclear Plant - ACRS review of plans for restart of the shut-down reactor.

Peach Gotton Nuclear Power Plant - ACRS review regarding restart of the currently shut-down reactor.

NRC Staff evaluatiun expected by late August.

The Honorable Lando W. Zech, Jr.

5 August 4, 1988 Regulatory Guide 1.106, Rev. 2, Thermal Overload Protection for Motor,

Operated Valves for Nuclear Power Plants Subcommittee Chairman's report regarding proposed revision cf this Regulatory Guide.

Advanced DOE Liquid Metal Cooled Reactor ACRS conrnents requested regarding approval of design concept for this standardized liquid metal cooled reactor. NRC Staff evaluation package expected by August 1988.

Sincerely, b

II. Kerr Chairman

+*pe neo uq UNITED STATES n'

NUCLEA6 HEGULATORY COMMISSION

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' ADVISORY COMMITTEE ON REACTOR S -

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WASHINGTON, D. C. 20666 November 9, 1988 MEMORANDUM FOR: Jim McKnight Document Control Systems L

FROM:

Ethel Barnard Advisory Comi tee o R ctor Safeguards

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lhe attached ACRS Documents are being provided to you for listing on the accessions list, Please forward to the Public Document Room.

Attachments:

As Stated l

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ACRS MINUTES AND CCNSULTANT REPORTS (PDR 110988) 1.

CT-1934 Schrock ltr 7/6/88 to Ward re Resolution of UPI Model Concerns Through W use of WCOBRA/ TRAC as Best Estimate Tool Under ProvisTons of SECY83-472 2.

CT-1935 Catton remo 7/10/88 to Boehnert re Technical Program Group (TPG) Meating - Code Scaling Applicability and Uncertainty (CSAU) Methodology, San Jose, CA, 6/9-10/88 3.

CT-1936 Barton memo 7/25/88 to Wylie re 7/22/88 Meeting of ACRS TVA Organizational Issues Subete, Review of Staff's TVA l

Lessons Learned Effoti 4.

CT-1937 Sullivan ltr 8/4/88 to Ward re 7/21/88 Thermal-Hydraulic l

Subete Meeting on Systen Effects Test Programs and OTSG Follow-on Program Results 5.

CT-1938 Lee ltr 8/5/88 to El-Zeftawy re Advanced Reactor Designs Subete Meeting 8/3/88 on MHTGR Concept 6.

CT-1939 Tien ltr 8/8/88 to Boehnert re Thermal-Hydraulic Phenomena Subete Meeting 7/21/88 on MIST Program and 0TSG Follow-on Program 7.

CT-1940 Avery ltr 10/26/88 to Ward re Advanced Reactor Designs Subete Meeting 10/5/88 en PRISM SER Oraft Report 8.

ACRS-2545 Advanced Reactor Designs Subete Meeting, January 6, 1988 9.

ACRS-2575 S&W Reactor Plants Subete Meeting, May 3-4, 1988

10. ACRS-2577 337th ACRS Meeting, May 5-7, 1988
11. ACRS-2582 Improved Light Water Reactors Subete Meeting, May 31, 1988 f
12. ACRS-2583 Advanced Boiling Water Reactor Subetc Meeting, June 1, 1988
13. ACRS-2584 338th ACRS Meeting, June 2-4, 1988
14. ACPS-2585 keliabilityAssurance(EQ-RiskScopingStudy;A-46 Update) Subcte Meeting, June 14, 1988
15. ACRS-2580 Maintenance Practicas & Procedures Subete Meeting, June 15, 1988 (continued)

ACRS MINUTES AND CONSULTANT REPORTS (PDR 110988)

16. ACRS-2588 Advanced Reactor Designs Subete Meeting, June 22, 1988
17. ACRS-2589 Severe Accidents Subete Meeting..'uly 13, 1988
18. ACRS-2590 339th ACRS Meeting, July 14-16, 1988
19. ACRS-2591 Thennal Hydraulic Phenomena Subete Meeting (Status of MIST Phase III & IV Programs & Proposed 0TSG Follow-on),

July 21, 1988

20. ACRS-2592 TVA Organizational Issues Subete Meeting, July 22, 1988
21. ACRS-2593 Decay Heat Removal Systems Subete Meeting (Resolution of US! A-45/ Status of Resolution of GI 99), July 27,1988
22. ACRS-2594 Advanced Peactors Designs Subcte Meeting, August 3, 1988
23. ACRS-2595 Safety Philosophy, Tec5nclogy & Criteria Subete Meeting, August 4, 1988
24. ACRS-2596 Improved Light Water Reactors Subete Meeting, August 9, 1988
25. ACRS-2597 Auxiliary Systems Subete Meeting, August 10, 1988
26. ACRS-2598 Regulatory Policies and Practices Subete Meeting.

August 10, 1988

27. ACRS-2600 Pilgrim Restart Subete Meeting, August 26, 1988
28. ACRS-2601 Safety Philosophy, Technology & Criteria Subete Meeting, September 1, 198d
29. ACRS-2002 Maintenance Pre Sices & Procedures Subete Meeting, September 7, 1>LB
30. ACRS-2604 Mechanical Components Subete Meeting October 4, 1988
31. SL-0348 Kerr ACRS ltr 8/4/88 to Zech NRC, Three Hundred and Thirty-Ninth Meeting of the ACR$, July 14-16, 1988 l

32.

SL-0349 Kerr ACRS itr 9/6/88 to Zech NRC, Three Hundred Fortieth Meeting of the ACRS, August 11-13, 1988

33. SL-0350 Kerr ACRS lte 10/3/88 to Zech NRC Three Hundred Forty-First Meeting of the ACRS. Septcmber 8-10, 1988 i

34 SL-0351 Kerr ACRS ltr 10/25/88 to Zech NRC. Three Hundred Forty-Second Meeting of the ACRS, October 6-7, 1988

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