ML20217J026
| ML20217J026 | |
| Person / Time | |
|---|---|
| Issue date: | 03/14/1996 |
| From: | Kress T Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2999, NUDOCS 9708130396 | |
| Download: ML20217J026 (36) | |
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[D/3f//l[17 TABLE OF CONTENTS MINUTES OF THE 4287H ACRS MEETING FEBRUARY 8-10, 1996 Pace I. Chairman's ReDort (Open) 1 II. Adecuacy of Individual PlanL,_, Examinations (IPEst (Open) 1 III. Recirculation Sumo Strainer Cloccina Events (Open) 4 IV. Westinchouse COBRA / TRAC Best-Estimate Thermal Hydraulic Code (Open/ Closed) 6 V. Human Performance Procram Plan (Opent.
8 VI. Imolementation Guidance for License Renewal (Open) 9 VII. ProDosed Final Revision 2 to Reculatorv Guide-1.149. Nuclear Power Plant Simulatipn Facilities for Use in Ocerator License Examinations (Open) 12 X. Executive Session (Open) 13 A.
Reports, Letters, and Memoranda Procosed Final NRC Bulletin 96-XX. " Potential Pluccina of Emeroency Core Coolina Suction Strainers by Debris in Boilina Water Reactors" and an Associated Draf t Revision 2 of Reculatorv Guide 1. 82. " Water Sources for Lona-term Recirculation Coolina Followina a
Loss-of-Coolant Accident" (Report to The Honorable Shirley Ann Jackson, Chairman, NRC, f rom T.S.
Kress, Chairman, ACRS, dated February 26, 1996.)
Westinahouse Best-Estimate Loss-of-Coolant Accident Analysis Methodoloov (Report to The Honorable Shirley Ann Jackson, Chairman, NRC, f rom T.S. Kress, Chairman, ACRS, dated February 26, 1996.)
Revision 2 to Reculatorv Guide 1.149.
" Nuclear Power q/
Plant Simulation Facilities for Use in ODerator License Examinations" (Letter to Mr. James M. Taylor, Executive Director for Operations, NRC, from T.S. Kress, Chairman, ACRS, dated February 22, u 96.)
O
-pj Oj Letter to The Honorable Albert Gore, Jr.,
President of t
the United States Senate, and The Honorable Newt Ging-rich, Speaker g.the qnited States House of Representa-Kt 8 8
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..o._k 27, 1996, transmitting the ACRS Annual Report on the NRC Safety Research Program.
ProDosed Generic Letter 96-XX on Periodic Verification of Desian-Basis Caoability of Safetv-Related Motor-Operated Valves (Memorandum to James M. Taylor, Executive Director for Operations, f rom John T. Larkins, Executive Director, ACRS, dated February 22, 1996)
Consistent with the Committee's decision, Dr. Lt.rkins informed Mr. Taylor that the Committee decided not to review the subject proposed generic letter.
PronoDed Generic Communication Recardino Boraflex Dearadation in Scent Fuel Pool Storace Rackg (Memorandum to James M. Taylor, Executive Director for Operations, from John T.
Larkins, Executive Director, ACRS, datec February 22,1996) -Consistent with the Committee's deci-sion, Dr. Larkins informed Mr. Taylor that the Committee decided not to review the subject proposed generic communication.
Procosed Final Amendment to 10 CFR Part 50 Recardina Frecuency of Emercency Plannina Exercises at Nuclear Power Plants (Memorandum to James M.
Taylor. Executive Director for Operations, from John T. Larkins, Executive Director, ACRS, dated February 22, 1996)
Consistent with the Committee's decision, Dr. Larkins informed Mr.
Taylor that the Committee decided not to review the subject proposed final amendment.
B.
Reconciliation of ACRS Comments and Recommen-dations C.
Report on the Meeting of the Planning and Proce-dures Subcommittee Held on February 7, 1996 (Open)
D.
Future ACRS Activities E.
Future Meeting Agenda 11
h Al'FENDICES I.
Federal Register Notice II. Meeting Schedule and Outline III. Attendeca IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee VI. Minutes for Closed Session - Proprietary Information
[ APPENDIX VJ REMOVED. FOI A EX(b) (4))
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,... a 1 MINUTES OF THE FOUR HUNDRED TWENTY EIGHTH MEETING OF THE ADVISDRY COMMITTEE ON REACTOR SAFEGUARDS FEBRUARY 8-10, 1996 ROCKVILLE, MARYLAND The 428th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on February 8 10, 1996.
The purpose of this
{
meeting was to discuss and take appropriate action on the items listed in the attached agenda.
The meeting was open to public attendance, except for portions that were closed to protect the disclosure of proprietary information.
There were no written statements from members of the ?ublic regarding the meeting.
There was one request for time to mace an oral statement.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W.,
Washington, D.C.
(Copies of the transcript are available for purchase from Neal R. Gross and Co.,
Inc., 1323 Rhode Island Avenue, N.W., Washington, D.C.
20005.)
ATTENDEES ACRS Members:
Dr. Thomas S. Kress (Chairman), Dr. Robert L. Seale (Vice-Chairman), Dr. George Apostolakis, Mr. James C. Carroll, Dr.
Ivan Catton, Dr. Mario H. Fontana. Mr. William J. Lindblad, Dr. Don W.
- Miller, Dr. Dana A.
Powers, Dr. William J.
- Shack, and Mr.
Charles J. Wylie.
(For a list of other attendees, see Appendix III.)
I.
CHAIRMAN'S REPORT (Open)
(Note:
Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.)
Dr. Thomas S. Kress, committee Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting.
He introduced Mr. Amarjit Singh, a new Senior Staff Engineer, and announced that Ms. Greta Dieus would be sworn in as NRC Commissioner on February 15th, and that the annual Conference on Regulatory Issues would be held on April 9-10, 1996.
II.
Adecuaev of Individual Plant Examinations (IPEs)
(Open)
Note:
Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.)
IntroductiQn Dr. George Apostolakis, ACRS, stated that the IPE Subcommittee met on January 26, 1996 with the NRC staff and its contractors to
L-428th ACRS Meeting 2
February 8-10, 1995 discuss the IPE review process and findings.
In a Staff Require-ments Memorandum dated December 27, 1995, the Commission requested:
"the ACRS views on the extent to which the current spectrum of IPEs can be used in the regulatory process."
NRC Staff Presentation Dr. Mark Cunningham, RES, outlined the staff IPE review process as follows:
The staff is issuing evaluation reports to licensees on each IPE submittal
- review, focusing on whether the licensee met the intent of the objectives of Generic Letter 88-20.
e The staf f has completed preliminary review of all IPE submittals (with issuance of 45 Staf f Evaluation Reports (SERs)) and estimates issuance of all SERs by June 1996.
The utilities performed Level 1 PRAs, developed in-house staff PRA capabilities, and generally indicated their intention to maintain and update IPE/PRA. Some utilities also performed Level 2 PRAr,.
In addition, the utilities have identified plant improvements as a result of IPE.
The staff indicated that five licensee IPE submittals do not meet the intent of Generic Letter 88-20, primarily due to inadequate human reliability analysis (HRA).
Dr. Cunningham stated that the staff is Assuing a Commission paper on preliminary IPE insights by the end of February 1996, and is planning to complete a preliminary draf t NUREG on 11 sights by summer of 1996.
The review of IPEs for insights looks beyond the intent of the Generic Letter (e.g. how IPEs compare to a state-of-the-art PRA).
Ms. Mary Drouin, RES, stated that the primary purpose of GL 88-20 is for the licensees to identify vulnerabilities to severe accidents and cost-effect safety improvements to reduce or eliminate those vulnerabilities.
Specific GL objectives for licensees are:
1.
Develop an appreciation of severe accider.t behavior.
2.
Understand the most likely severe accident sequences that could occur at the plant.
3.
Gain a moro quantitative understanding of the probability of core damage and fission product releases.
J>g.
428th ACRS Meeting 3
February 8-10, 1995 4.
If necessary, reduce the probabilities by modif yir.g hardware and procedures.
Ms. Drouin indicated that the NRC IPE review scope focused. on completeness and reasonableness that included core damage frequency (CDF) review, co7tainment performance review, and HRA.
The scope included internal events (including internal flooding) only at full power.
CDF and containment performance perspectives were provided by plant class.
For example, the IPEs indicate that BWR 3/4s have relatively low CDFs (less than 10" per reactor-year); and station blackout and transient accidents dominate the core damage frequen-cy.
Dominant contributors vary because of plant specific design differences.
Numerous plant improvements were identified (e.g, increased load shedding, firewater usage as injections, increased training on depressurization).
The IPEs indicated that Mark I containments have relatively high conditional containment failure probabilities.
In addition, contribution f rom both early ccatain-ment failure and late containment failure is relatively high with containment bypass relatively low.
The definition of severe accident vulnerabilities varies; however, most licensees used NUMARC guidelines, or the dRC subsidiary safety goal of a CDF objective of 10" per reactor-year and a large release of 104 per reactor-year. Many of the plant improvements identified by the licensees are " generic" in nature, with the majority being procedure / operation and design / hardware
- changes, and few are related to maintenance.
Preliminary findings indicate that all licensees have performed a Level 1 PRA.
The majority (approximately 70%) of licensees appear to have appropriately modeled initiating events and system dependencies, adequately considered common-cause
- failures, addressed both pre-anitiator and post-initiator human events, and performed " reasonable" HRA.
The insights from Level 2 PRA were not provided.
75% of the IPEs appear to have been performed primarily by licensees and 65% of licensees have indicated the intention of updating their IPEo/PRAs.
Mr.
E.
Butcher, NRR, briefly stated that the IPEs are essential elements in the search for severe accident vulnerabilities.
However, the current IPE resulto do not, by themselves withcut further staf f review, provide a complete basis for supporting risk-informed regulatory decisions.
The PRA quality must be commensu-rate with the proposed regulatory application.
The staff is developing regulatory guides for industry to use PRA in regulatory applications.
In addition, the staff is developing a standard review plan for reviewing industry-generated IPEs/PRAs for use in regulatory decision-making.
Jhw-428th ACRS Meeting 4
February 8-10, 1995 conclusion The Committee intends to write a report to the Commission regarding this issue.
III. Recirculation Sumo Strainer Cloccina Events (Open)
(Note Mr.
S.
Duraiswamy was the Designated Federal Official for this portion of the meeting.)
Introduction Mr. Carroll, Chairman of the Plant Operations Subcommittee, stated that the purpose of this meeting was to continue the ACRS review of the staff and industry responses to strainer clogging events.
He also expressed disappointment in the slow progress made by the staff and the industry to resolve this issue.
NRR Presentation Mr. Gary Holahan, Director, Division of Systems Safety and Analysis (DSSA), introduced the NRR and RES staff.
Mr. Rob Elliot of NRR led the discussion for proposed final NRC Bulletin 96-XX, "Poten-tial Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," and NRC Bulletin 95-02, " Unexpected Clogging of Residual Hea*, Removal (RHR) Pump Strainer Whtle in Suppression Pool Cooling Mode," Mr. Michael Marshall, Jr.. RES led the discussion for the proposed Revision 2 to Regulatory Guide 1.82, " Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident."
Mr. Holahan said that the reason for not resolving the issue in a more timely manner is that the issue turned out to be more technically dif ficult than the staff had imagined.
It also required more research than expected.
He stated that the scaff is ready to issue the proposed final Bulletin and Regulatory Guide so the industry csn resolve this problem within a given time frame.
Mr. Elliot provided an overview of the proposed final Bulletin including the background, regulato: y bases, resolution of public comments, and planned actions.
Mr. Marshall similarly discussed the proposed final Re*tision 2 to Regulatory Guide 1.82.
Signifi-cant points made during the discussion were e
Background:
The Barseback event in July 1992 concerning the partial plugging of the suppression pool strainers; events at Perry in April and November 1993, and at Limerick in September 1995.
428th ACRS Meeting 5
i February 8-10, 1995 e
NRC Bulletin 95 02: In response to the Limerick event, licensees were requested to evaluate the operability of the ECCS
- )y inspecting the suppression pool strainers, pumps establish the suppression pool cleaning i
program, and correct any identified weaknesses.
The inspection results indicated that 29 out of 35 plants had cleaned pools during the last refueling outage.
i e
Significant changes to Revision 2 of Regulatory Guide 1.82: includes provisions for containment cleanliness, drywell debris interceptors, instrumentation, s:tive strainer components or systems, and use of alternative water sources.
Proposed final Bulletin and Regulatory Guide 1.82 Resolution Options: 1) installation of large capacity passive strainers, 2) installation of self-cleaning strainers, and 3) installation of strainer backflush systems, associated instrumentation alarms, and operator training in the use of the system.
o The staff believes continued operation of BWRs is acceptable while the actions requested in the proposed Bulletin are being implemented.
This was based on licensee actions in response to NRC Bulletins 93-02 and 95-02.
BWR Owners Grouc Presentation Mr. Carl Terry, Chairman of the BWR Owners Group (BWROG) Executive Committee, introduced the presenters and provided an overview of the industry and Owners Group activities to resolve this issue.
Mr. Rocky Sgarro, Chairman of the BWROG ECCS Suction Strainer Committee (ESSC) and Dr. A.J. Bilanin provided detailed technical discussion.
Significant points made during the discussion were:
Initial Resp /operatorBWROG initially focused on pipe break e
onse frequencies
- response, safety assessment /
operator guidance
- reports, and European operating experience and knowledge.
e Further Evaluations focused on filtering of corrosion
?roducts by fibrous material that could result in high dead losses, confirmed combined debris effects through testing, and considered the development of alternate strainer designs.
e-
-NRC-Interaction: BWROG has had a high level of interac-tion with the NRC through meetings and report / evaluation submittals.
BWROG differs With the NRC with regard to
428th ACRS Meeting 6
February 8-10, 1995 modeling assumptions for debris-generation, transport, and strainer blockage.
The Owners Group has not had an opportunity to review the details of comment resolution but appears to be in general agreement that the NRC needs to go forward with the proposed Bulletin and Revision 2 to Regulatory Guide 1.82.
Preferred Option BWROG prefers to cNalify the maximum number of plants with passive stra:,ner designs.
The i
BWROG is nearing complet:,on of a Utility Resolution Guide to provide detailed guidance to the industry.
Mr. Carroll questioned the source of fibrous material found in the Limerick suppression pool and whether the sludge woul d cause blockage by itself.
The staff stated it was a polypropylene fiber of unknown origin (i.e.,
foreign material) and that it made the blockage much worse that sludge alone. Mr. Carroll also quartioned what criteria existed for inspectors to verify suppression pool cleanliness, to which the staff replied that the Bulletina contain most of the detailed information.
Mr. Lindblad questioned the applicability to PWRs and Dr. Kress questioned how the NRC verified that licensee responses to Bulletin 93-02 were adequate.
The staff responded that the blockage phenomena do apply to PWRs and stated that the conclusion regarding Bulletin 93-02 was a judgment call.
The Committee extensively discussed this issue and concluded that the NRC staff and industry actions to resolve this issue were unacceptably slow.
The Committee expreshed agreement that the Bulletin and Regulatory Guide should be issued, requesting that they be kept informed of progress being made toward resolution of this issue.
Conclusion The Committee issued a letter to Chairman Jackson, dated February 23, 1996.
IV.-
Distinahouse COBRA / TRAC Best-Estimate Thermal Hydraulic Code (Open/ Closed)
(Notet Mr. P. Boehnert was the Designated Federal Of ficial for this po'. tion.of the meeting.)
A 428th ACHS Meeting 7
February 8-10, 1995 luiloduetion Dr. Catton, Chairman of the Thermal flydraulic Phenomena subcommit-tee, introduced this topic to the Committee.
He noted that the Subcommittee achieved a good dialogue with Westinghouse on its review of this incue.
The Subcommittee believes that the Westing-house best-estimate loss-of-coolant accident (LOCA) methodology is well structured and clearly laid out.
There are some problems, however.
The following concerns remain as a result of the Subcommittee's reviews e
Treatment of the heat transfer coefficients:
H has included some data on heat transfer that is nonphysical (too high heat transfer rates).
o Modeling of the minimum wetting (rewetting) temperature:
H ignored systematic effects that could lead to non-conservative resultu.
o Treatment of compensating errors in the codes the H presentation on this issue was not convincing.
Little can be done about this, however, since such errors are inherent to the structure of the code.
Calculation of mass balance: the code appeared to be unable to conserve mass for calculating test data from the Japanese Slab Core Test Facility '(SCTF).
This problem is believed to be related to data collaction errors / omissions. The Subcommittee urged H to reevaluate this data and see where the problem lies, o
Documentation: the Subcommittee had to " play detective" to obtain adegaate information, which significantly increased the time needed to complete its review.
H needs to provide complete documentation on both co-BRA / TRAC and the result of NRR's review.
Hent.inghouse Presentatica (Closed Session - Proprietary Informa-tion.
Minuten for this portion are included as Appendix VI)
(APPENDIX VI REMOVED - FOIA EX(b) (4))
liRR Prencntation Mr.
R.
Jones discussed the results of the NRR review of the Westinghouse best-estimate, large-break LOCA methodology.
He said that NRR has completed its review and has found this methodolor",
acceptable for use on H 3-and 4-loop PWR plants.
Mr. Jones proceeded to discuss the resolution of the major review issues that had been "nearly resolved" at the time of the Thermal Hydraulic Phenomena Subcommittee's last meeting (January 18-19, 1996).
428th ACRS Meeting 6
February 8-10, 1995 In response to Mr. Lindblad, Mr. Jones said that NRR does not intend to re-review the final documentation submittal made by Westinghouse.
This submittal is scheduled to be sent to the staff in about six months.
Conclusica The Committee issued a report to Chairman Jackson, dated February 26, on this matter.
V.
Human Performance Procram Plan (Open)
(Note: Mr. H. Dudley was the Designated Federal Official for this portion of the meeting.)
Introduction Mr. Carroll, Chairman of the Human Factors Subcommittee, noted that this session on the Human Performance Program Plan (the Plan) would enable the Committee to identify potential human factor issues for future ACRS review, since the Plan envelopes NRC activities in this area.
NRC Presentation Mr. Cecil Thomas, Chairman of the NRC Human Factors Coordination Committee (HFCC),
introduced the HFCC members and provided background information on the creation, charter, and activities of the HFCC.
The HFCC, which is comprised of representatives of the NRC program offices and the regions, developed and inuued the Plan in August 1995.
The Plan identifies the goals and objectives of the NRC human performance program, and prioritizes ongoing and future activities.
Mr.
Thomas noted that the Plan does not represent the views of the cognizant program offices and that the next revision to the Plan will receive office endorsements.
Members of the ACRS and HFCC discussed to whom the Plan was submitted, the extent of interfaces with other public and private organizations, how the staf f shares information with licensees, and the need for research on the elements of organizational culture.
The HFCC discussed specific line items in the Plan, such as creating databases, establishing the human factors information system, and staf fing operating plants.
The ACRS members questioned whether the staf f had considered the American Disability Act during the review of future nuclear plant designs.
The staff stated that plant designs do not appear to be in conflict with the Act.
Members of the ACRS identified several items related to digital instrumentation and control design and to human reliability that could be included in future ACRS subcommittee meetings.
428th ACRS Meeting 9
i February 8-10, 1995 i
conclughn The Committee took no action based on this information briefing.
VI.
Irnolementation Guidance for License Renewal (Open)
(Note:
Dr. M. El-Zeftawy was the Designated Foderal Official for this portion of the meeting.)
Introdation Dr. Mario Fontana stated that the purpose of this session is for the Committee to hear a presentation by the NRC staf f regarding the status of license renewal activities.
Currently, the staff is reviewing a submittal by the Nuclear Energy Institute (NEI) that provides the guidelines of how to implement the license renewal rule (10 CFR Part 54).
The staf f is also reviewing topical reports that were submitted by the licensees regarding certain aspects of their plants.
NRR Presentation Mr. Scott Newberry, NRR, stated that in December 1991, the NRC published 10 CFR Part 54 to establish the procedures, criteria, and standards governing nuclear plant license renewal.
Since publish-ing the original rule, the NRC and the industry conducted various activities related to its implementation.
In September 1994, the NRC proposed an amendment to the rule.
The final amendment was published in May 1!'"
D. f ocuses on the ef fects of aging on long-lived passive structures and components and on time-limited aging analyses (TLAA).
In addition, the amendment allows greater reliance on the current licensing basis (CLB), the Maintenance Rule, and existing plant programs.
NEI has prepared a guideline to implement 10 CFR Part 54.
The major elements of this guideline are:
Identifying the
- systems, structures, and components (SSCs) within the scope of the Rule.
Identifying the intended functions of systems and structures within the scope of the Rule, e
Identifying the structures and components subject to aging management review.
Assuring that effects of aging are managed, o
Identifying and resolving time-limited aging analysis.
428th ACRS Meeting 10 February 8-10, 1995 e
Identifying and evaluating exemptions containing time-i limited aging analyses.
e Identifying a suggested format and content of a license renewal application.
Applicants interested in license renewal are responsible for the preparation of a plant-specific license renewal application that includes technical information such as an integrated plant assessment, Cl.B changes during the NRC review of the application, a supplement to the Final Safety Evaluation Report, and a supple-ment to the plant's environmental report that complies with the requirements of Subpart A of 10 CFR Part 51.
Currently, the staff has developed an integrated schedule for the reviews of the NEI guideline and for preparing a regulatory guide
-(possibly endorsing the NEI guideline) that affords the public the opportunity to participate and comment. as part of the development process.
The initial estimate for finalizing the Regulatory Guide and the NEI guideline is July 1997.
NEI is planning to develop a pilot demonstration program.
During the industry's implementation of the pilot demonstration program, the NRC staff plans to conduct onsite audits.
Additional site audits will be performed as part of the Staf f's review of the license renewal topical reports submitted by the industry.
The purpose of tae site audits is to independently verify that the NEI guideline and the topical reports provide sufficient information to support preparation of a license renewal application.
Insights from these site audits will be factored into the development of a Standard Review Plan (SRP) for license renewal and the inspection program for a license renewal application.
The staf f intends to publish the draf t SRP af ter it gains implemen-tation experience with the final rule amendment, based on the review of a few license renewal applications.
The development of the license review inspection program is in its formative stages, and the staff will continue to develop the license renewal inspection program in parallel with development of the SRP and the regulatory guide.
Mr. John Moulton, NRR, briefly described the Baltimore Gao &
Electric (BG&E) topical report regarding Integrated Plant Assess-ment Methodology, This topical report describes a methodology for determining and screening the structures and components subject to an aging management review, describes a methodology for performing an aging management
- review, and describes a methodology for performing TLAA evaluations.
The a assessment /ging management strategy has four-phases:
Discovery, analysis, corrective action, and confirmation documentation.
The staf f reviewed the BG&E topi-
428th ACRS Meeting 11 February 8-10, 1995 cal report and concluded that the scoping methodology is acceptable for meeting 10 CFR 54.21 (a) (2) and that BG&E can reference it in its application.
In addition, the staff concluded that this topical report can provide a framework for demonstrating that aging will be adequately managed and that TLAA evaluations are adequately performed.
Mr. Sam Lee, NRR, briefly described a Babcock & Wilcox (B&W) Owners Group (OG) topical report entitled:
" Generic License Renewal Program / Demonstration of the Management of Aging Effects for the Reactor Coolant System Piping."
This report contains a generic evaluation of the management of ef fects of aging of the B&W reactor coolant system (RCS) piping components so that the intended f onctions will be maintained for any period of extended operations.
The report addresses the plant-specific piping components of the RCS within the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code Section XI in-service inspection program for Class 1 components (such as pipir.g, valve bodies, and bolting).
The evaluation applies to units that belong to the B&W OG, Generic License Renewal Program (GLRP).
The staff will issue a final safety evaluation report upon resolution of open items.
Currently, no license renewal application has been submitted to the NRC.
An NRC-sponsored workshop is planned for July 1996 for the presentation of the views of NRC and the other participants and information on the draft NE1 guideline and the draft regulatory guide, as well as the results of the NEI pilot demonstration program.
Conclusion This briefing was for information only.
VII. Procesed Final Revision 2 to_Reculatory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Ocerator License Examinations (Open)
(Note:
Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.)
Mr. Carroll, Chairman of the Human Factors Subcommittee, introduced the session by mentioning that he was on the original standards committee for ANSI /ANS 3.5, "American National Standard for Nuclear Power Plant Simulators for Use in Operator '. raining and Examina-tion."
He noted that the proposed final revision 3 to Regulatory Guida 1.149 endorses the 1993 version of ANSI /ANS 3.5.
428th ACRS Meeting 12 February 8-10, 1995 NRC Presentation Mr. Frank Cc411ns, NRR, provided an overview of the regul' tory a
1 background of Regulatory Guide 1.149 and ANSI /ANS 3.5.
He exp'.ained *, hat the proposed revision was needed-to add ef ficiency the M.itial certification and quadrennial performance testing of
- m. M ation facilities.
Mr.
Collins stated that the changes incorporated in the 1993 version of ANSI /ANS 3.5 included different requirements for simulator capabilities, tolerances, train!. g value 3
assessments, configuration management, and certification..
Mr.
Collina described the changes made to the revised regulatory guide.
The changes included defining simulator malfunctions and overrides, clarifying the scope of validation testing, explaining operability testing, outlining the periodicity of design updates, and specify-ing the use of appendices.
The ACRS members and NRC staff discussed the fidelity of simula-tors, the use of digital self-checking routines, and the certifica-tion of simulators used at the NRC Chettanooga Technical Training Center.
The Committee commended the staff for making the latest draft of the proposed revision available to the public.
Nuclear Enerov Institute (NEI) Presentation:
Mr. James Davis, NEI, stated that the industry supports endorsement of the 1993 version of ANSI /ANS 3.5 due to the increased capacity of newer simulators and the need to define, clarify, and bound testing requirements.
The industry supports limiting simulator t
testing to only those areas used in training and allowing sir.ulator testing during training sessionc.
The ACRS members and Mr. Davis discussed whether licensees would adopt the revised regulatory guide and whether future enforcement of the regulatory guide
- requirements would result in onerous amounts of documentation.
==
Conclusion:==
The Committee issued a letter to James M.
- Taylor, Executive Director for Operatim 0- February 22, 1996, which stated that the i
staff should proce.ed
. s th the publication of Revision 2 to Pegulatory Guide 1.10,
VIII. EXECUTIVE SESSION (Open)
(Note s Dr. ' John T. Larkins was the Designated Federal Of ficial for this portion of the meeting.)
(
428th ACRS Meeting 13 February 8-10, 1995 A.
Reports, Letters and Memoranda Prooosed Final NRC Bulletin 96-XX, " Potential Pluccine of Emercency Core Coolino Stiqfdon Strainers by Debris in Boilino Wate-Reactqrs" and an Associat C raft Revisi D Q
2 of Reculatory Guide 1.82, " Water Sou;ygpr Lona-term Recirculation Coolina Followinc a_,1ggi-ot - Coolant Accident" (Report to The Honorable Shi"lcy Ann Jackson, Chairman, NRC, f rom T.S.
Kress, Chairmata ACRS, dated February 26, 1996.)
Westinchouse Best-Estimate Loss-of-Coolant Accident 3nalvsis Methodoloav (Report to The Honorable Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated February 23, 1996.)
Revision 2 to Reculatory Guide 1.149,
" Nuclear Power Plant Simulation Facilities for,Use in Ooerator License Examinations" (Letter to Mr. James M. Taylor, Executive Director for Operations, NRC, from T.S. Kress, Chairman, ACRS, dated February 22, 1996.)
Letter to The Honorable Albert Gore, Jr.,
President of the United States Senate, and The Honorable Newt Ging-rich, Speaker of the United States House of Representa-tives, from T.S.
Kress, Chairman, ACRS, dated February 27, 1996, transmitting the ACRS Annual Report on the NRC Safety Research Program.
ProDosed Generic Letter 96-XX on Periodic Verification of Desian-Basis Cacability of Safetv-Related Motor-Ocerated Valves (Memorandum to James M. Taylor, Executive Director for Operations, from John T. Larkins, Executive Director, ACRS, dated February 22, 1996)
Consistent with the Committee's decision, Dr. Larkins informed Mr. Taylor that the Committee decided not to review the subject proposed generic ~1etter.
Procesed Generic Communication Recardino Borafles Degradation in Soent Fuel Pool Storace Racks (Memorandum to James M.
Taylor, Executive Director for Operations, from John T.
Larkins, Executive Director, ACRS, dated February 22, 1996) -Consistent with the Committee's deci-sion -Dr. Larkins informed Mr. Taylu: that the Committee decided not to review the subject proposed generic communication.
Procosed Final Amendment to 10 CFR Part 50 Recardino Frecuency of Emercency Plannino Exercises at Nuclear Power Plants (Memorandum to James M.
Taylor,' Executive
. ~ -
rG,5 o 428th ACRS Meeting 14 February 8 10, 1995 7
- Director for Operations, from John T. Larkins, Executive Director,-ACRS, dated. February 22, 1996)
Consistent with the committee's decision, Dr. Larkins informed Mr.
Taylor that the Committee decided not to review the subject proposed final amendment.
B.
Reconciliation of ACRS Comments and Recommendations (Note: Mr. Sam Durr.iswamy was the Designated Federal Official
-for this portion of the meeting.)
The committee discussed the response from the NRC Executive Director for Operations to ACRS comments and recommendations included in recent ACRS reports:-
e EDO letter dated December 14, 1995, responding to the ACRS report dated November 13, 1995, concerning NUREG-
- 0700, Rev.
1,
" Human-System Interface Design Review
. Guideline."
The Committee decided that it was satisfied with the EDO's
- response, o
EDO letter dated December 18, 1995, responding to the ACRS letter dated November 14, 1995, concerning Proposed Modifications to the BWR Owners Group Emergency Procedure Guidelines to Address Reactor Core Instabilities.
The Committee decided that it was satisfied with the EDO's response.
e EDO letter dated December 28, 1995, responding to the ACRS letter dated December 13,
- 1995, concerning the Proposed Final Generic Letter, " Testing of Safety-Related Logic Circuits."
The Committee has concerns about this response but decided not to take action at this time, e
EDO letter dated January 5, 1996, responding to the ACRS letter dated November 14, 1995, concerning the Proposed Final Regulatory Guide 1.164,
" Time Response Design Criteria for Safety-related Operator Actions," to Resolve
- Generic Safety Issue B-17.
The Committee accepted the response of the NRC staff but wishes-to be kept informed of further developments in the review of this issue.
1 A
k w
e.
- 428th-ACRS Meeting 15 February 8-10, 1995 1
Meeting of the Planning and Procedures
- C.
Report on the Subcommittee (open)
The Committee did not discuss the Report of the-Planning and Procedures. Subcommittee.
The-items on the' agenda for this month will be discussed at the next ACRS meeting, March 7-9, 1996.
D.
Future Meetina Aaenda Appendix IV summarizes the proposed items endorsed by the Committee for the 429th ACRS Meeting, March 7-9, 1996.
The-428th-ACRS meeting was adjourned at 1:30 p.m.
on Saturday, February 10, 1996.
W 9
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APPENDIX 1
).
Federal Ragiater / V;1. 61. No 18 / Friday, January 26, 1996 / Notices 1547 i
Deted january 22,199e-Coopeas, b NRC, the Statu and the Advloory Commtnee on Reector R Reeers WieMer, Conference of Radiation Control
' Sofeguerde; Nocce of Meecng smaatree Manorment ofmer Program Directors. The egends will Ibt Doc. 9&t:3e riled 1-ts-es; a es am]
include a summary of the IOM findings in accordance with the purposes of and recommendations, a summary of Sections 29 and 182b. of the Atomic eusso cous ms the staff plan, to date, for analysis of b Energy Act (42 U.S.C. 2039,2232b), the report; and a discussion of b Advisory Committee on Reector imp cauons and irnpacts of b eight Safeguards wil! hold a meeting on li NUCLEAR REGULATORY recommendations.
February 6-10,1996, in Conforence COMMISSION Room T-283,11545 Rockville Pike, ADohasets: U.S. Nuclear Regulato Adyteory Committee on the Medicel Commission. Two White Flint Nor Rockville, Maryland. The date of this Usee of lootopes; Meeting Notice 11545 Rockville Pike, Room T2B3, meeting was previously p,ublished in the f ederal Re5 ster on Monday, 1
Rockville, MD 20852-2738.
Aooecyt U.S. Naclear Regulatory November 27,1995 (60 FR 583931 Commisalon.
POR FURTHER IMF08esADON, CO8fTACT!
IoneP ne M. Picrone, Ph.D., U.S.
nareday, February 8,1996 hi Acnow: Nodce of meeting.
Nuclear atory Commission Office y;3g g_y__g.45 A.M : Opening flemarks sunesARY:The U.S. Nucleet Regulatory of Nuclear terial Safety and by b ACilS Chirman (Open)
Commission will convene a meeting of Safeguards, MS T8FS, Washington, DC th) Advisory Committee on 6 Medical 20555 Telephone (301) 415-7270. For
% ACRS Chairman will make Uses of Isotopu (ACMUI) on February administrative information, contact opening remarks regarding conduct of 21-22,1996. The ACMUI will review Torre Taylor, (301) 415-7900.
the meeting and comment briefly regarding items of cunent interest.
the National Academy of Sdences, C aduchf M M wd y During this seulon, the Committee will Institute of Medicine (IOM), report and provide comments on the possible Barry Siegel, M.D., will chair th discuss pnorities for preparation of impacts of the report, including any meeting. Dr. Siegel will conduct the ACRS reports.
poucy, legislative, rulemaking, and meeting in a manner that will facilitate a:45 AR-10:45 AX: Adequocyof guidance issues. The meetin will take the orderly conduct of business. The Individual Plant Erominorsons (IPEs) place at 6 address provid below. All following procedures apply to public (Open) swaions of the meeting will be open to participation in the muting:
the public.
- 1. Persons who wish to provide a The Committee will hear DATse: The meeting will begin at 8:30 written statement should submit a presentations by and bold discuulons e.m., on February 21 and 22,1996, reproducible copy to Josephine M.
with representatives of the NRC staff Piccone (address listed previously), by regarding the adequacy of the IPEs for supeuseptrARY eNropusAnON: In January 1994, the NRC contracted with the IOM, February 16,1996.The transcript of the regulatory appilcations, to conduct an external review of the meeting will be kept open until Representatives of the nuclear February 26,1996, for inclusion of industry will participate, as appropriate.
NRC's medical regulatory program, written comments submitted after which included a review of the basic regulatory rules, policies, practices, and February 16,1996. Statements must 11:00 AR-2:45 P.M(LUNCH 12:30 procedures. There were three major Pertain to the topics on the agenda for PR-2:Jo PR): flecirculation Su np f
goals of the study:(1) examination of the moedng.
Strainer Clogging Events (Open) th) overall risk sunciated with the use
- 2. At the meeting, quesdons from The Committee wig 3 hear of ionir.ing radiation in medicine;(2) members of the pubhc will be permitted and ho usajg ns g
,,(
p extinination of the broad policy luuw at the discretion of the Chairman, th:t underlie the regulation of the
- 3. N transcript and wntten and BWR Owners Group (BWROG) medical uses of radioisotopes; and (3) a comments will be evallable for regarding the recirculation sump critical assessment of the current inspection, and copying, for a fee, at the stribr c
'ng events, including those frcmework for the regulation of the NRC Public Document Room,2120 L that at Barseback Perry, and medical uses of byproduct material. The Street, NW, Lower Level Washington.
Limerick Nuclear Power Piants, and the NRC was seeking specific DC 20555 (202) 634-3273, on or about associated regulatory acthons, recommendations on two me}or issues.
March 8,1996. Minutes of the meeting l
First, it requated recomseendations on will be available on or about April 5, 300 PR-520 PR: Westinghouse COBRA /7RAC Best Estimate Thermal a uniform national appmach to the 1996.
regulation of ioninns radia4cn in all
- 4. Seeting for the public will be on a Hpfroulic Code (Open/ Closed) medical applications, including first come, first served basis.
i[, y and h I discussions consideration of how the regulatdry This meeting will be held in p,,,,
authonty and responsibility for medical accordance with the Atomic Energy Act with representatives of b dsvices sold in interstate commerce for of 1954, as amended (pnmarily Sectir'n Westinghouse Electric Corporation and application of radiation to human 161a); the Federal Advisory Committee the NRC staff regarding the beings should be allocated among Act (! U.S.C. Apph and the Westinghouse COBRA / TRAC best-Federal Government agencies and Commission's regulations in Title to-estimate code to be used in support of between the Federal and State U.S. Code of Federal Regulations, Part 7.
b AP600 panive plant duign Governments. Secondly, it requested Deted: January 22.1996.
certification.
recommendations on appropnate
^*d'" L 8****-
A portion of this session may be critena to measure the eIfectiveness of f
regulatory prograrn(s) needed to protect Adusory Commstree Management Offker.
closed to discuss Westinghouse i
public health and safety. The IOM (FR Doc. 96-1326 Filed t-25-96. m 45 ami proprietary information applicable to this matter.
r2 port provides recommendations to mumi coce nee + +
I ' 4548 Federal Regist:r / Vol. 61. No.18 / Friday, January 26, 1996 / Notices S:15 PM-6.45 P.M : Preparution cf f M PM-3 JO PM: Proposed Fmal or written statements may be presented ACRS Ileports (Open)
Revision 3 to Regulatory Guide 1.149, by members of the public, electronic Nuclect Power Plant Simulabon recordings will be permitted only The Committee will discuss pmposed facihbes for f)se m OperatorIJeense during the open portions cf the meeting.
ACRS reports on matters considered Examinobons (Open) and questions may be asked only by l
during this moeung na well as a proposed ACRS report to Congrus on The Committw will hear members of the Committee,its the NRC Safety Research Program, and prowntations by and hold discussions consultants, and staff. Persons desiring a proposed report on the twoluuon of with reprmntatives of h NRC staff to male oral statements should notify regarding the to Regulatory breposed Final Revision 2 Mr. Sam Duraiswamy, Chief Nuclear Multiple System Responses Program uide 1.14g.
Reactors Branch, at least five days NSRP) lasues.
Reprowntatives of the nuclear
+ before the meeting,if possible, so that Fr6 day, February 9,199g lodustry will parucipate, as appropriate. appropriate arrangements caa be made
[
8:J0 A M-8.35 AM:OpeningItemarks 3:30 pm.-Je p in.:lieport of the to allow the necessary time during the Procedures Subcommittee meeting for such ststements. Use of still, by the ACRS Chairman (Open)
Plannin[o during tbgg,,,,,,,g,,;,,;, gag e,,,7,,
,,, g o, O*
P s meadng may be limited to The ACRS Chairman will mak*
no Committee will bear a nport of selected portions of the meeting as opening remarks regaMing conduct of 6 Planning and Procedures determbed by the Chairman.
the meeting.
Subcommittee on matters related to the Informa"t@n regarding the time to be set 8:35 AM-240 AX: Human conduct of ACRS business, and aside for this purpose may be obtained Performance Program Plan (Open) oryenir.ational and personnel matter
- by contacung the Chief of the Nuclear plating to the ACRS staff roombers.
Reacton Branch pnor to the meeting. In The Committee will hear A portion of this neesion may be prewntauons by and hold discussions closed to discuss organisational and view of the possibility that 6 schedule with reprwentauves of the NRC staff Personnel matters that relate solely to for ACRS meeungs may be adjusted by regarding the human priormana the internal personnel rules and the Chairman as necwsary tc facilitate program plan dmlo by the staff to Practices of this Advisory Committw, the conduct of the moeung, peons integrose all NRC vities in this area, and matters the release of which would planning to attend should check with the Chief of the Nuclear Reactors Branch Reprwentatives of h nuclear C'",
pharranted if such racheduling would rwult in industry will participale, as appropriate.
major inconvenience.
10,15 AM-tL45 AM: Implementation 3:15 PR -3:45 P.m.: Future ACRS In exordants wtth Subsection 10(d)
A
"( Pen)
P.L 92-463, I have determined that it is Guidance for IJcense RenewalfOpen) no Committee will select topice for necessary to close portions of this The Committee will hear considereuon during futum ACRS mwting noted above to discuss matters prwentations by and hold discussions matings.
that relate solely to the intemal with representativu of b NdC staff personnel rules and practices of this regarding updated implementation jf o":45 m -6 m,
paration of Advisory Committes per 5 U.S C.
guidance for license renewal.
P 8 552b(c)(2), to discuss Wwtinghouse Representatives of b nuclear no Committu will discuse proposed propnetary informsuon per 5 U.S C.
Industry will participate, as appropriate. ACRS reports on matters mnaidered 552b(c)(4), and to discuss matters the during this mooting as well as a please of which would constitute a 11:45 A.M-1340 Noons Reconciliation proposed ACRS report to Congress on clearly unwarranted invasion of of ACRS Comments and the NRC Safety Research
,and personal privacy per 5 U.S.C. 552b(c)(6).
Recornmendations (Open) ap to on e Further informadon regarding topics The Committee will discusa responses Responses Pro 6 ram (MSRP) Issues, to be discussed, whebt the meeting of the NRC Executive Director for has been cancelled or rescheduled, the Operations (EDO) to comments and Saturday, February 10,19ee Chairman's ruling on enquests for the i
recommendations included in ACRS 8:30 o.m.-!1:30 a m.:Pnparotion of opportunity to present oral statements I
reports on: NUREG4700, Revision 1 ACRS fleports (Open) and the time allotted therefor can be
" Human. System Interfeca Design obtained by contacting Mr. Sam I
Review Guideline," dated November 13, Dursiswamy, Chief, Nuclear Reacton The Comminee will continue its 1995: proposed Final Regulatory Guide asQe A
mpons Brunch (telephone 301/415-7364),
4 t
for Safety Related Operator Acuona,to as well as thi proposed reports on other betwwn 7:30 a.m. and 4:15 p.m. EST.
1.164, " Time Response Design Criteria matters noted above.
ACRS meeting notices, meeting Resolve Generic Safety Issue B-17 "
transcripts, and letter reports are now dated November 14,1995:" Proposed 21:45 a.m.-1:30 p.m.:Stmtegic Planning avallable on FedWorld from the "NRC (O ent MAIN MENU." Direct Dial Access l
Modifications to the BWR Owners P
Group Emergency Procedure Guidelines no Committee will discuss items that number to FedWorld is (600) 303-9672, l
to addrwa Reac*or Core Instabilities "
are of significant importance to NRC, the local direct dial number is 703-321-dated November 14,1995: and proposed including rebaselining of the Committee 3339-Final Generic 1Atter," Testing of Safety-activities for fiscal year 1996-1997.
Deted: lanuary 22.1996 Related Logic Circuits " dated December Procedures for b conduct of and udrew 1., sesen, 13,1995. The Committee will also participation in ACRS meetings won discuss other responses expected to be published in the Federal Register on Admorycannunw mnosernent ofpcer recalved from the FDO before the September 27,1995 (60 m 49925). In in D c. 96-1325 Filed 1-2be6 a 45 aml meeting.
eccordance with these procedures, oral same come am+4 h..
e APPENDIX 11 l, * ' "/#
'o UNITED STATES g
NUCLEAR RECULATORY COMMISSION o
y ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
W ASHINGTON, D. C. 20656 January 17, 1996 SCNEDULE AND OUTLINE FOR DISCUSSION 42sth ACRS MEETING FEBRUARY s-10, 1996 Thutadav. February 8, 1996. Conference Room 233, Two White Flint Morth.
Regkville. Marvisag 8th5A.M.
Openina Remarks by the ACRS Chairman (Open) 1)
8:30 1.1)
Opening Statement (TSK/SD) 1.2)
Items of Current Interest (TSK/JTL/SD) 1.3)
Priorities for Preparation of ACRS T
Reports (TSK/SD) 2)
8:f5
- 10:45 A.M.
Adeauncv of Individual Plant Examinations (IPEs) (Open) (GA/MME) 2.1)
Remarks by the Subcommittee Chairman 2.2)
Briefing by and discussions with representatives of the NRC staff regarding the adequacy of the IPEs for regulatory applications.
Representatives of the ruclear industry will participate, as appropriate.
T 10:45 - 11:00 A.M.
BREAK 7 t o *1 s
3) 11:00 -
2:46 P.M.
Recirculation Sumo Strainer Cloccina Events (12:30-1:30 - LUNCH)
(Open) (JCC/MTM) 3.1)
Remarks by the Subcommittee Chairman 3.2)
Briefing by and discussions with representatives of the NRC staff and BWR Owners Group regarding tha recirculation sump strainer clogging events, including those that occurred at Barseback, Perry, and Limerick Nuclear Power Plants, and the associ ated regulatory actions.
2:45 3:00 P.M.
BREAK 4) 3: N -
5: N P.M.
Westinahouse COBRA / TRAC Best-Estimate Ther-mal Hydraulic Code (Open/ Closed) (IC/PAB)
L(),3.j : 3: 3r. S t o 7 f,w]
4.1)
Remarks by the Subcommittee Chairman T
4.2)
Briefing by and discussions with representatives of the Westinghouse Electric Corporation and the NRC staff regarding the Westinghouse 7
hort.'os
{ h meeh'nj transc e abl.
a
-1 W
--,6 R-a_,
--.~
4-a:a
-.msm
,e a
COBRA / TRAC best-estimate code to be used in support of the AP600 passive plant design certification.
[ Note:
A portion of this session may be closed to discuss Westinghouse proprietary information applicable to this matter.)
5:0h 5:1k P.M.
BREAK 5) 5 t hk
$P.M.
Precaration of ACRS Renorts (Open)
Discussion of proposed ACRS reports on:
5.1)
Annual ACRS Report to Congress on the NRC Safety Research Program (RLS/MME) 5.2)
Proposed Final Bulletin related to Recirculation Sump Strainer Clogging Events (JCC/MTM) 5.3)
Westinghouse COBRA / TRAC Best-Estimate Thermal Hydraulic Code (IC/PAB) 5.4)
Resolution of Multiple System Responses Program (MSRP) issues (CJW/MME/AWC) 5.5)
Adequacy of Individual Plant Examina tions (GA/MME)
Friday, February 9, 1996. Conference Roum 233. Two White Flint Morth, Engkville. umeviand 8:35 A.M.
Onenino Remarks by the ACRS Chairman (Open) 6)
8:30 (TSK/SD) 10:0[A.M.
Human Performance Procram Plan (Open) 7)
8:35 (JCC/NFD) 7.1)
Remarks by the subcommittee Chairman 7.2)
Briefing by and discussions with representatives of the NRC staff regarding the Human Performance Prgram Plan developed by the staff to integrate all NRC activities in this area.
Representatives of the nuclear industry will participate, as appropriate.
m 10:Ob
- 10:15 A.M.
BREAK 2r
)
11: 5 A.M.
Imolementation Guidance for License Renewal 8) 10:15
_(Open) (MHF/MME) 8.1)
Remarks by the Subcommittee Chairman
---. -. = _. - _..
~. - _.
8.2)
Briefing by and discussions with representatives of the NRC staff regarding updated implementation guidance for license renewal.
Representatives of the nuclear industry will participate, as appropriate.
-MNrhoNoon Reconciliation of ACRS Comments and Recom-9) 11: 5 mandations (Open) (TSK, et.al. /SD, et.al.)
Discussion of the responses from the NRC Executive Director for Operations to com-ments and recommendations included in recent ACRS reports, il147 s2:4f 1:00 P.M.
LUNCH 19790 A c.4 s. Re PetJ J2f WT 1.'
- f f. H.
/
10) 1: 0/~
2:$$ P.M.
Proposed Final Revision 2 to Regulatorv
~
Guide 1.149. Nuclear Power Plant Sirulatio.D Facilities for Use in Operator License Examinations (Open) (JCC/NFD) 10.1)
Remarks by the Subcommittee Chairman 10.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed final Revision 2 to Regulatory Guide 1.149.
Representatives of the nuclear industry will Re conell.atsek (sa.aj 9.)propriate.
participate, as ap 2:ot
- 2. ! ff f. N.
T 3:00 P.M.
Report of the Plannina and Procedur's 11) 2:30 e
Subcommittee 'Open/Closep) (TSK/JT )
Report of th Planning ynd Proced res Sub-committee o matters r lated to e conduct ofACRSbus/ ness,and rganizat nal and ff',[fD personnel atters rol ting to t e ACRS staff members.
gggg,3 (Note:
portion o this ses ion may be closed o discuss rganizati/nalandperson-nel na ers that late sol ly to the inter-nal pe sonnel rul s and pr tices of this Advis ry Committ s, and ma ters the release of wh ch would onstitute a clearly unwar-ranQd invasio of perso 1 privacy.)
atSC se 3:14 P.M.
BRF.AK 3tc0 12) 3:$$
3:45 P.M.
Future ACRS Activities (Open) (TSK/SD)
Discussion'of the recommendations of the Planning and Procedures Subcommittee regard-
, ' *, ~.
a t
4 ing items proposed for consideration by the full Committee during future meetings.
7:oe P. H.
- s46 P. M.
Prenaration of ACRS Pecorts (Open) 13) 3:45 Continue discussion of proposed ACRS reports on:
13.1)
Annual ACRS Report to Congress on the NRC Safety Research Program (RLS/MME) 13.2)
Proposed Final Bulletin related to Recirculation Sump Strainer Clogging Events (JCC/MTM) 13.3)
Westinghouse COBRA / TRAC Best-Estimate Thermal Hydraulic Code (IC/PAB) 13.4)
Resolution of Multiple System Responses Program (MSRP) issues (CJW/MME/AWC) 13.5)
Adequacy of Individual Plant Examina tions (GA/MME) 13.6)
Proposed Final Revision 2 to Regula-tory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations (JCC/NFD)
Eniurday, February 10, 1996. Conference Room 2B3, Two White Flint Morth, Rockville, Marylagg 14) 8:30
- 11:30 A.M.
Precaration of ACRS Reports (Open)
Continue discussion of proposed ACRS reports identified under Item 13.
11:30
- 11:45 A.M.
BREAK 1:30 P.M.
Stratecic PIannina lhpen) (T K/JTL)
- 19) 11:45 Discussio of item of sign ficant importanc to NRC, includi g rebaselining
)ReMcb Fdo" of the C maittee ctiviti s for FY 96-97.
Acrcho Presentation time should not exceed 50 percent of the total MQTE:
o time allocated for a specific item.
The remaining 50 percent of the time is reserved for discussion.
Number of copies of the presentation materials to be provided o
to the ACRS - 35.
. ~ ~. -.. _ -... -
'V e i
APPENDIX III - MEETING ATTENDEES 428TH ACRS MEETING FEBRUARY 8-10, 1996 i
l NRC STAFF
. Wayne Hodges RES=_
Mary Drouin RES Mark Cunningham-RES John-T. Chen RES ED Rodrick RES 4
Christian Lui RES s
John H. Flack NRR John-Lane RES Sarah Malik RES Ann Ramey-Smith RES William B. Jones' RES E. Collins.
RES S.-Dinsmere
'NRR T. M..Su RES A.H. Hsia NRR-L. Soffer EDO D.- O'Neal NRR Jim:Trapp
. Region I David Allsopp NRR
' David J. Nelson NRR Mike Cheok NRR T. Murphy RES David Morrison RES Nark Reinhart NRR Michael Marshall RES Charles Serpan-RES Iam_Jung-RES Robert-Jones NRR Rob ~Elliott NRR Samuel-Lee NRR Frank Orr NRR Eric Weiss-NRR Dale Rasmuson AEOD Cecil Thomas NRR
-Tom Bundick R III
-Frank-Coffman RES
-J.
Peasensky-RES P. Lewis RES Sarah-Malik _
.RES Joel J.-Krarier RES A..Ramey-Smith RES' Mary Drouin RES Bruce-Boger NRR-Clare Goodman-NRR David Morrison RES Steve Reynolds NRR John Moulton NRR
+
Y v
7
~
e + 1,,.
t
- jAppendixJ III 2-
- 428th ACR$ Meeting:
i Scott.TNewberry NRR l Sam-Lee-NRR Paul Shemanski.
. NRR-
-Pr T.sKuo-NRR-Scott-LFlanders:
NRR Steve Hoffman NRR Christopher'Regan NRR-L. Soffer NRC S.-Richards NRR
.A t
L h
a h
1 d'
r 1
g m
s N
N
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' Appendix III 3
428th ACRSiMeeting
" ATTENDEES FROM OTHER AGENCIES'AND GENERAL PUBLIC CarlLTerry BWROG Gordon Hart-Performence-Contracting'Inc.
Paul B.
Politzi Nine Miles Point UNST #1NMPC Pasquale'Bartolini_ Niagara Mohawk Mitchell Nissleg.
Westinghouse Electric Corp.
Stephen Bajorek Westinghouse C. P. Fineman INEL L. E. Hochreiter Westinghouse D. S. Boulton Jectra M. Young Westinghouse Allice Carson Bechten James W. Davis NEI Margo Barron NUS/LIS Dr. Hostethen GWV Eng.
-B. W. Doroshuk BGE B.-M. Tinden BGE John M. Osborne BGE Paige Neyis BGE Frederick W.
Plasky PECO Energy Mark Rinekel PTI Hans Renner NLIS/LIS Lynn Connor Self Gilbert Zigler SEA Kimberley R. Leone PP&L George Corvelius Northwest Utilities Mark:Mjaatvedt PP&L Altheia Wyche Search Lecensing/Bechtel Bill-Houston SEQUOIA Consulting Group Inc.
Dan Maret=
SEQUOIA Consulting Group Inc.
Mike Schoppman PP&L Alan bilanin CDI Princeton NJ R. R. Sgarro PP&L Bill Maker PSE&G Toshiyaki Zamance TEPCO Tony Pietrangelo NEI Mark C. Nolan BGE Scott Midgett BGE Francois Cattant Elechicity of France Ronald E.-Cole Enteray Operations Inc.
Joseph L. Jerz Boston Edison Co.
-Parge Negua GE Lynn Connor 2.206 Enterprises Doug Walters NEI-
'Theresa Sutter Bechtel
_. ~ - -..
, ? j ', A e APPENDIX'IV:
FUTURE AGENDA The Committee agreed to consider the following during the 429th ACRS Meeting, March 7-9,-1996:
' Thursday M=rch 7.
1996
.1)
Br45 10r00'A.M.r Reculatory Guidance Documents Related to Digital Instrumentation and ' Co*1 trol Systems (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC Staff regarding proposed Regulatory Guides, Standard Review Plen Sections, and Branch Technical Positions related to digitial instrumentation and control systems.
The 2) 10r15 11:45 A.M.r Reactor Vessel Annealing (Open)
Committee will hear presentations by and hold discussions with representatives of the NRC st.aff and the Department of Energy (DOE) regarding the details of the DOE pilot projects for annealing reactor vessels.
12:15 P.M.r Adecuacy of Individual Plant Examinations 3) 11545 The Committee will continue its. discussion (IPEs)
(Open) with representives of the NRC staff regarding the IPE review process and findings.
2:45 P.M.- Apolicability of RF11AP5/ MOD 3 Code for the
.4) 1r15 The Committee will hear AP600 Design (Open/ Closed) presentations by and hold discussions with representatives of the NRC staff and its consultants regarding the staff program to evaluate the applicability of the RELAPS/ MOD 3 Code to perform accident / transient analyses-of the AP600 design.
5).
2:45 3:45 P.M.-
Fire Protection Issues (Open)
The Committee will hear presentations by and hold discussions with representatives _of the NRC staff and its consultants regarding a PRA model associated with the risk of fires during a self-induced station blockout and scoping analysee to evaluate the ef fectiveness of degraded-fire dbarriers in mitigating the consequences of a fully developed fire.
Fridav. March 8.
1996 6) 8 35 - 9r45 A.M.;
Probabilistic Risk Assessment (Open) - The Committee will hear presentations by and hold discussions with representatives of the NRC staff and its consultants regarding the PRA framework
- document, its relationship to pilot applications, and the use of PRA in the regulatory decision-making process.
'7) 9:45 10:15 A.M.: Resolution of Generic Safety Issue 78, Monitoring of. Fatigue Transient Limits for the Reactor Collant System (Open) - The Committee will' hear presentations by and u
I
- . fj f s
- *
(Appendix IV 2
- 429th ACRS Meeting.
- hold discussions;with reprecentatives of the NRC staff _and-its
-consultants.regarding the measures taken to correct an error
- in the PRAISE Code, which was used to vertify the resultas of a parametric study on risk associated with fatigue fallure of-primary collant-pressure boundary components._
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APPEtiDIX V
. i LIST OF-DOCUMENTS PROVIDED TO THE COMMITTEE 1
(Notes
-Some documents listed below.may have been provided or.
prepared for Committee use: only.
These documents must be reviewed-1 prior to release to the public.)
MEETING HANDOUTS AGENDA DOCUMENTS ITEM NO.
1 Items of Interest 1.
Introductory Statement of the ACRS
- Chairman, dated February 8-10, 1996 2.
Memorandum to ACRS Members f rom Noel F.
Dudley, Senior
~
Staff Engineer ACNW. Meeting with the NRC Executive Director for Operations:
Regulatory Oversight of Department of Energy Facilities, dated January 29, 1996 2
Adecuacy of Individual Plant Examinations (IPEs) 3.
Individual Plant Examinations, Presented by Mark Cunningham and Mary Drouin, RES, dated February 8, 1996 (Viewgraphs) 4.
Adequacy of IPEs for Regulatory Applications, Presented by Ed Butcher, NRR, dated February 8,1996.
(Viewgraphs) 3 Recirculation Sumo Strainer Cloccina Events 5.
ACRS Briefing on the Proposed Bulletin Titled " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," and Proposed Revision
=2 of Regulatory Guide 1.82, Water Sources for Long-Term Recirculation Cooling Following a
Loss-of-Coolant Accident," Presented by Gary Holahan and Rob Elliott,
-NRR, and Michael Marshall (RES), dated February 8. 1996.
[Viewgraphs) 4-Westinahouse COBRA / TRAC Best-Estimate Thermal-Hydraulic Code 6.
Consultants?- Reports:
Review of Westinghouse Best-Estimate: ECCS Code:
Report of V.J.
Dhir,- Thermal-Hydraulici Subcommittee Meeting, dated January 18-19, 1996; and-Report by-N. Zuber, " Review - Of. Westinghouse
-Best-Estimate Thermal-Hydraulic Code HCOBRA/ TRAC, dated January 18-19, 1996. (Handout 4.2] (Contains Proprietary 4
Information: Do Not Release Without Prior Authorization.)
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!.18th ACRS Meeting 7.
Status of BWR Owners' Group Work to Resolve ECCS Strainer
- Issues, Presented by Dr.
A.J.
- Bilanin, Continuum
- Dynamics, Inc., and R.R. Sgarro, Pennsylvania Power
(<
Light Co., dated February 8, 1996 (Viewgraphs) 8.
Presentation Schedule:
Review of Westinghouse Best-Estimate ECCS Code (Handout 4.1) 9.
Westinghouse Best-Estimate Large Break LOCA Methodology Introduction, Presented by L.E.
Hochreiter, Consulting
- Engineer, Westinghouse Electric Corporation, dated February 8, 1996 (Viewgraphs)
(Proprietary Information:
Do Not Release Without Prior Authorisation.)
10.
NRR Review of Westinghouse Best-Estimate ECCS Code, Presented by Robert C.
Jones, dated February 8, 1996.
[Viewgraphs) 7 Human Performance Procram Plan 11.
Human Performance Program Plant A Presentation to the ACRS by the Human-Factors Coordination Committee,
-Presented by Cecil Thomas, dated February 9,
1996.
(Viewgraphs) 12, Speech given by Zack T. Pate to the INPO CEO Conference:
The Control Room, dated November 3,
- 1995, i
Imolementation Guidance for License Renewal 8
13.
NRC Staff Presentation to the ACRS:
- Status, dated February 9,
- 1996, presented by Scott Newberry, John Moulton, and Sam Lee.
9 Reconciliation of ACRS Comments and Recommendaticns 14.
Reconciliation of ACRS Comments and Recommendations (Handout #9.1) 10 Procosed Final Revision 2 to Reculatory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Ooerator License Examinations 15.
NRR Staff Presentation to the - ACRS on Revision 2 to Regulatory Guide 1.149, presented by Frank Collins.
[Viewgraphs) 16.
Revision 2 to Regulatory Guide 1.149,. Nuclear Power Plant Simulation Facilities, Presented by James Davis, Nuclear Energy Institute, dated February 9, 1996. (Viewgraphs)
+-
c
^ 1 :' e Appendix V 3
418th ACRS Meeting 11' Reoort of thq_Plannina and Procedures Subcommittee 17.
Final Draft Minutes of Planning and Procedures Subcommittee Meeting - February 7, 1996 (Handout #11.X) 12 Future ACRS Activities 18.
Future ACRS Activities - 429th ACRS Meeting, March 7-9, 1996 [ Handout #12.1)
- ~ -
~.
- ,4 j y o Y Appendix V
'4 418th ACRS-Meeting MEETING NQTEBOOK CONTENTS 3
TAB DOCUMENTS 2.
Adecuacy of Individual Plant Examinations (IPEs)
.1~
Table of Contents 2.
Tentative Schedule 3.-
Project Status Report, dated February 8, 1996 4.
Staff Requirements Memorandum to John T. Larkins, ACRS, from John C. Hoyle, Secretary, NRC, dated December 22, 1995:
Meeting with Advisory Committee on Reactor-Safeguards-(ACRS) 1:30 P.M. Friday, December 8, 1995.
5.
Generic Letter 88-20, dated November 23, 1988: Individual' Plant Examination for Severe Accident Vulnerabilities -
-6.
Memorandum to Steven A. Varga, NRR, f rom M. _ Wayne.Hodges, RES: Review of San Onofre Individual Plant Examination Internal Events, dated December 28, (IPE) Submittal
- 1995, 3.
Recirculation Cumo Strainer Clocoino Events Environmental Oualification Recuirements for Dicital
- Instrumentation and Control (I&C) Systems 8.
Table-of Contents 9.
Agenda 10.
Project Status Report, dated February 8, 1996 11.
Memorandum to - Edward L.
- Jordan, Committ.ee.:o Review Generic-Requirements, from Frank J. Miraglia, NRR, dated January 23, 1996: Request for Review and Endorsement of the-Proposed Bulletin Titled,
" Potential Plugging of
-Emergency Core Cooling Suction Strainers by Debris- -in Boiling Water Reactors. " (TAC No. M86925) (Predecisional:
Do Not Release Without Prior Authorization) 12.
Memorandum from Lawrence
-C.<
- Shao, RES, to John T.
Larkins, ACRS,- dated January 5,
1996: ACRS Review of Regulatory. Guide = 1. 82, Revision 2,
" Water. Sources for Long-Term Recirculation Cooling ' Following a Loss-of-Coo) ant Accident."
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i
-Appendix V 5
-418th ACRS Meeting i
i 13.
NRC Bulletin 95-02: " Unexpected Clogging of a Residual Heat-Removal - (RHR) - Pump Strainer While Operating in Supprecsion Pool cooling Mode,"-dated October 17, 1995, 14.
Letter from Dr. T.S. Kress, Chairman, ACRS, to Dr. Ivan Selin, Chairman, NRC, dated. October 14, 1994: Potential for BWR ECCS Strainer Blockage Due to LOCA-Generated Debris.
15, Letter from the Executive Director for Operations, James M. Taylor, to Dr. Thomas S. Kress, Chairman, ACRS, dated January 27, 1995: Potential for BWR ECCS Strainer Due to LOCA-Generated Debris.
16.
Memorandum from William T.
Russell, Director, NRR, to James M. Taylor, Executive Director for Operations, dated December 14, 1994: ACRS Concerns Related to the Potential for BWR ECCS Strainer Blockage by LOCA-Generated Debris.
17.
Letter from BWR Owners' Group' to Rules Review and Directives Branch,
- NRC, dated October 2,
1995:
BWR Owners' Group Comments on NRC Draft Bulletin and Regulatory Guide Regarding
" Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors."
18.
Letter from Juhani Hyvarinen, Finnish Centre for Radiation and-Nuclear Safety (STUK) to the Rules Review and Directives Branch, NRC, dated October 2, 1995: Draft NRC Bulletin 95-XX, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," July 1995, and Draf t Regulatory Guide DG-1038,
" Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident," July 1995.
4.
Westinahouse COBRA / TRAC Best-Estimate Thermal Hydraulic Code 19.-
Table of Contents 20.
Agenda 21.
Project-Status Report, dated February 8, 1996 22.
Draft Working Copy, Minutes of ACRS Thermal-Hydraulics Phenomena Subcommittee Meeting, January 18-19, 1996:
-Review of Best-Estimate ECCS Code - H COBRA / TRAC 23.
Letter from Dr. Thomas S. Kress, Chairman, ACRS, to James M. Taylor, Executive Director for Operations, NRC, dated i
May
-17, 1995:
Review of Best-Estimate Models for
Appendix V 6
-418th ACRS. Meeting Evaluation of Emergency Core Cooling System Performance.
24.
Letter from W.
norr, Chairman, ACRS, to Victor Stello, Jr., Executive Director for Operations, NRC, dated July 20, 1988:
Comments on the NRC Staff's Draft Safety Evaluation of the Westinghouse Topical Report, WCAP-
- 10924,
" Westinghouse Large-Break LOCA Best-Estimate Methodology.
Road
- Map,
- 25. : Westinghouse Best-Estimate Methodology Viewgraphs Presented to ACRS Subcommittee by L.E.
Hochreiter, Westinghouse Electric Corporation, dated January 18-19, 1996.
[ PROPRIETARY INFORMATION: DO NOT RELEASE WITHOUT PRIOR AUTHORIZATION.]
7.-
Human Performance Procram Plan 26.
Table of Contents 27.
Proposed Agenda 28.
Status Report, dated February 9, 1996 29.
Human Performance Program Plan, Issued in August 1995 by the Human Factors Coordination Committee.
8.
Imolementation Guidance for License Renewal 30.
Table of Contents 31.
Tentative Schedule 32.
Status-Report, dated February 9, 1996 33.
10 CFR Parts 2, 51, and 54, Nuclear Power Plant License Renewal; Revisions 34.
NEI 95-10 Draft, Revision F: Industry Guidelines for Implementing the Requirements'of 10 CFR Part 54 - The License Renewal Rule, January 1996.
35.
Letter from Dr. T.S. Kress, Chairman, ACRS, to Dr. Ivan Selin, Chairman, NRC, dated March 14, 1995: Proposed Amendment to the Nuclear Power Plant License Renewal Rule (10 CFR Part.54) 36.
Letter from Robert E. Denton, Baltimore Gas and Electric Company, to NRC, dated January 11, 1996': Revision I to Integrated Plant Assessment Methodology (TAC Nos. M93326 and M93327)
--,.4 g,. y a
Appendix V 7
418th-ACRS Meeting 10.
Pronosed Final Revision 2 to=Reculatory Guide 1.149, Nuclear Power Plant Simulation Facilities for-Use in Ooerator License Examinations 37.-
. Table of Contents i
-l 3 8. - Proposed Agenda 39.
Status _ Report, dated February 3, 1996 i
4 0. - Memorandum from Bill B. Morris, RES, to John T. Larkins, l-ACRS: Proposed Resolution of Draft Regulatory Guide DG-1043,-Nuclear Power Plant-Simulation Facilities for Use in Operator Licensing Examinations American National Standard for 41.
ANSI /ANS 3.5-1993, Nuclear. Power Plant Simulators for Use in Operator
-Training and Examination," published - by th9 American Nuclear Society, March 26, 1993.
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