ML20217A750
| ML20217A750 | |
| Person / Time | |
|---|---|
| Issue date: | 08/25/1997 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-3067, NUDOCS 9803250203 | |
| Download: ML20217A750 (48) | |
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Date Issued: August 25, 1997 g 4,i.
Date Signed: September 4, 1997 WRS - 304 7 TABLE OF CONTENTS MINUTES OF THE 443RD ACRS MEETING JULY 9-11, 1997 P.AER I. Chairman's Reoort (Open) 1 II. Meetina with the Director of the NRC Office of Nuclear Reactor Reculation (NRR) (Open) 1 III. Accentance Criteria for Plant-Soecific Safetv Goals and Derivine Lower-Tier Accentance Criteria (Open) 4 IV. Pronosed Standard Review Plan Section and
'Reculatory Guide for Risk-Informed.
Performance-Based Inservice Insoection (Open) 6 V. Meetina with NRC Commissioner McGaffican (Open) 9 VI. Procosed Final Modifications to 10 CFR Pan
- 26. Fitness-For-Duty Procram Recuirements (Open) 9 VII. Halden Reactor Proiect (Open) 10 VIII. Use of RASCAL Code Durina Incident Response (Open) 13 IX. NUREG/CR-6372. Recommendations for Probabilistic' Seismic Hazard Analysis; Guidance on Uncertainty and Use of Exoerts. (Open) 14 X. Executive Session (Open) 15 A.
Reports, Letters, and Memoranda e
Procosed Reaulatorv Guide and Standard Review Plan g[
Chanter for Risk-Informed.
Performance-Based In-service Insoection : (Report to Shirley Ann Jackson, Chairman, NRC,-from R. L.- Seale, Chairman, ACRS, dated July 14, 1997.)
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e Pronosed Final Revisions to 10 CFR Part 26. Fit-ness-For-Duty Reauirements (Letter to L.. Joseph Callan, Executive Director - for Operations, NRC, from R.
L. Seale, Chairman, ACRS, dated July 14, 1997) e Pronosed Final Revision 3 to Reculatorv Guide 5.44.
" Perimeter Intrusion Alarm Systems" (Memorandum to L.
Joseph. Callan, Executive Director for Opera-9903250203 970825
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tions, NRC, from-John T. Larkins, Executive Direc-
' tor, ACRS, dated July: 15,.1997) e Pronosed Direct Final Rulemakino Chanaes to Para-oraoh (h) of'10 CFR 50.55a. " Codes and-Standards" (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T.
Larkins, Execu-tive Director, ACRS, dated July 15, 1997)
B.
Reconciliation of ACRS Comments and Recommen-dations C.
-Report on the Meeting of the Planning and Proce-dures Subcommittee Held on July 8 and 10, 1997 (Open)
D.
Future Meeting Agenda J
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. APPENDICES
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I. Federal Register Notice
.II. Meeting Schedule and Outline III. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee J
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MINUTES OF THE 443RD MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS JULY'9-11, 1997 ROCKVILLE, MARYLAND The 443rd meeting of the Advisory Committee on Reactor Safeguards was held in Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on July 9-11, 1997.
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. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2100 L Street, N.W.,
Washington, D.C.
[ Copies of the transcript nre available for purchase from Neal R. Gross and Co.,
Inc., 1323 Rhode Island Avenue, N.W., Washington, D.C. 20005.]
ATTENDEES ACRS Members:
Dr. Robert L. Seale (Chairman), Dr. Dana A. Powers (Vice-Chairman), Dr. George Apostolakis, Mr. John Barton, Dr. Mario H. Fontana, Dr. Thomas S. Kress, Dr. Don W. Miller, and Dr. William J. Shack.
[For a list of other atendees, see Appendix III.]
I.
CHAIRMAN'S REPORT (Open)
[ Note:
Dr. John T. Larkins was the Designated Federal Of ficial for this portion of the meeting.)
Dr. Robert L. Seale, ACRS Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting.
He announced that the Items of Interest included an interesting speech by Commission-er Diaz on May 30, 1997, and the Notice of a large Civil Penalty had been issued to the Clinton Nuclear Power Station.
He also introduced the ACRS Summer Intern, Christine Lootens.
II.
Meetino with the Director of the NRC Of fice of Nuclear Reactor Reculation (Open)
[ Note:
Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.]
Introduction Dr. Seale, ACRS Chairman, welcomed Mr. Samuel J. Collins, Director, Of fice of Nuclear Reactor Regulation (PRR). Dr. Seale s:ated that, as part of the periodic briefings by NRC Office Directors, Mr.
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t 443rd ACRS Meeting 2
July 9-11, 1997 Collins would discuss current important NRR issues and the interaction between NRR and ACRS.
Mr. Collins' Presentation Mr. Collins stated that NRR priorities were divided into three major categories:
oversight of operating reactors, allegation follow-up, and event response.
He indicated that NRR performance will be judged by the handling of these three areas.
He stated that these priorities are the types of issues that will redefine NRR.
Other work like programmatic, long-range planning and advanced reactors will continue.
The oversight of operating reactors is to ensure that NRR keeps the attention and focus on protecting the health and safety of the public. Allegation follow-up proved to have a 33 percent payback on investment as far as providing insights into plant issues, which is higher than from the inspection program.
For event response, he stated that the NRC will be judged on its response to actual events rather than on its
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preparatory activities.
l Mr. Colldns emphasized that the ultimate goal of NRR is to protect public health and safety.
NRR will attempt to be predictive, attempt to prevent extended plant shutdowns, to the extent that they deal with rules and regulations, and pay more attention to individual components.
NRR, in its review of design basis events, applies defense-in-depth, not only to mitigate but to respond to a design event, such as the steam generator tube event.
Mr. Collins stated that NRR has improved timeliness and investiga-tory capability and has performed a great deal of work in the areas of allegations, employee concerns, and a safety-conscious work i
environment.
Mr. Collins described the plant evaluation and assessment proceas.
The findings from the inspection reports are incorporated into the plant issues matrix (PIM).
The findings from the inspection reports are evaluated periodically by the Regions.
These reviews, referred to as plant performance reviews (PPRs), are performed on a quarterly basis.
The outcome of these reviews will bc provided as an input to the screening meeting, which is a prelude to the Senior Management Meeting (SMM).
Depending on the cycle of the plant, the PIM and other attributes will be incorporated into the Systematic Assessment of Licensee Performance (SALP) process.
Currently, the SALP has four major functional areas: operations, maintenance, engineering, and plant support.
The SALP effort is structured to provide an ove all assessment of licensee perfor-mance, provide the ability to communicate to licensees on a fairly uniform basis using uniform criteria, and provide the basis for the allocation of inspection resources.
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443rd ACRS Meeting 3
July 9-11, 1997 The SMM process, as articulated in the management directive, is an NRR process.
However, inputs from the Regions and other offices such as the Office for Analysis and Evaluation of Operational Data (AEOD) and the Office of Nuclear Regulatory Research (RES) are required to complete the process.
For example, AEOD (in response to the Arthur Anderson report) develops the types of indicators that may enhance the current SMM process, and develops attributes that measure plant performance in a consistent way, and if possible in a predictive way.
The SMM is structured to integrate design information and risk probabilities with operating history, thus allowing NRR to analyze plants differently than by using the SALP process.
Mr. Collins encouraged the ACRS to provide AEOD with insights on developing the expected performance indicators.
Mr.
Collins pointed out that the inspection activities for risk-in-
. formed, performance-based regulation could be more difficult and challenging than for prescriptive and deterministic regulation.
Mr. Collins described the design basis and 10 CFR 50.59 process improvements.
As a result of lessons learned from Maine Yankee, Millstone, and Haddam Neck, the staff is finding vulnerabilities in the plants at a lower threshold than expected.
The staff is pursuing changes to the 50.59 process based on the new directions of risk-informed, performance-based regulations and enforceability issues.
The staff is also integrating into this process Generic Letter 91-18 which deals with operability and corrective actions.
Mr. Collins welcomed insights from the ACRS on different issues such as risk policy, the shutdown rule, and steam generator tube integrity.
Mr. Collins outlined other current issues where there is ongoing ACRS/NRR staff interaction, such as spent fuel storage (wet and dry),
steam generators, license renewal, core performance and reactor fuel, and industry deregulation / restructuring. Dr. Powers, ACRS, noted that license renewal activities are increasing and it would be helpful if NRR could structure an integrated schedule that would include a realistic timetable for ACRS involvement.
Mr.
i Collins agreed.
Mr. Collins described briefly how NRR will~ implement Direction-
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Setting Issue #23: " Enhancing Regulatory Excellence."
A working group composed of an Associate Director in NRR and staff from the Offices of the General Counsel,
- RES, and the Office of the Executive Director for Operations (EDO) has been formed to review and define the core of excellence in the NRC charter.
The fundamental research activities, which are different from the process research activities, would remain in RES.
Mr. Collins mentioned some of the challenges NRR will face, such as training of inspectors and enforceability criteria, as the NRC moves toward performance-based regulation. The staff has completed
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443rd ACRS Meeting 4
July 9-11, 1997 the fire protection inspection at the River Bend plant, and plans to inspect pilot plants.
In addition, the staff plans to hold a workshop and issue a Commission paper on this subjecc.
The ACRS expressed interest in participating in these fire protection inspection program activities.
Conclusion This briefing was for information only.
The Committee extended an invitation to Mr. Collins to discuss items of concern with the ACRS whenever he feels the need.
III. AcceDt3nce Criteria for Plant-Soecific Safety Goals and Derivino Lower-Tier Acceotance Criteria (Open)
[ Note:
Mr. M. Markley was the Designated Federal Official for this portion of the meeting.]
Introduction Dr. Thomas Kress, Chairman, Subcommittee on Regulatory Policies and Practices, introduced the topic to the Committee.
He noted that the Commission had requested the ACRS to determine the change in core damage frequency (CDF) and large, early release frequency (LERF) from site to site, when these lower-tier acceptance criteria are derived from the prompt fatality quantitative health objectives (QHOs) as stated in the Staff Requirements Memorandum dated May 27, 1997.
He introduced Mr. Rick Sherry, ACRS Senior Fellow to present the results of an analysis he performed regarding these matters.
ACRS Senior Fellow Presentation Mr. Sherry summarized the issues to be addressed in his presenta-tion, including parameters important to early fatality risk, a j
model for calculating early fatality risk, and an approach for deriving subsidiary LERF criteria from the Safety Goal OHOs for j
individual early fatality risk.
He also discussed additional considerations such as the robustness of individual early fatality frequency (IEFF) calculation and societal risk. Significant points made during the discussion include:
e Issues include: 1) whether there is sufficient site-to-site variability to warrant site-specific determination assuming CDP is a fundamental goal and not derived, 2) whether the range of variability can be evaluated and bounded, and 3) whether generic or site-specific criteria can be determined using simplified approximate methods, i
I 443rd ACRS Meeting 5
July 9-11, 1997 e'
Important parameters to early fatality risk include both plant design and operational features.
These features should be included in the definition for LERF.
Parameters include:
Source Term Characteristics
- magnitude of fission product release from containment
- release thermal energy and height
- reactor thermal power level Timing Characteristics
- timing of release relative to the start of protective actions
- absolute timing of release re]ative to the reactor shutdown Site Parameters (charact rized by the exposure index (EI))
- sector population distribution
- wind direction frequency distribution
- variability due to site-to-site variations in local meteorology
- size of exclusion zone e
The simple model for estimating the distribution of EI includes: 1) determining the distribution from site-to-site population and wind direction frequency variations, 2) adding the variability due to differences in exclusion zone bound-aries, and 3) adding the variability resulting from differenc-es in 1c;41 meteorology.
Conclusions and recommendations: 1) lower-level LERF can be determined on a generic basis, 2) information provided on the variability of the early fatality risk resulting from site-related factors can be used to bound the variability, and 3) t derivation of LERF cannot proceed until a physical definition of LERF is. developed in terms of the parameters important to early fatality risk.
e Additional considerations: 1) the calculation of IEFF is not robust for many sites in that small population changes can have a large effect on IEFF, 2) current NRC Safety Goals are expressed in terms of the individual, and 3) current Safety Goal QHos ignore site population densities.
Dr. Powers expressed the view that CDF and LERF cannot be calculat-ed without risk analysis for low-power and shutdown operations, external events, fire, etc. He further stated that this full-scope
t 443rd ACRS Meeting 6
July 9-11, 1997 risk analysis has to be calculated to get to the QHOs.
Dr. Kress expressed agreement with this view.
Dr. Powers also expressed concern over the use of the Gaussian Plume Model in representing actual dispersion of radionuclide releases.
Dr. Apostolakis questioned whether LERF was considered a fundamental goal in the analysis.
Mr. Sherry stated that there was not enough variability from site to site to warrant revisiting the atmospheric dispersion dose assessment codes.
Mr. Sherry stated that CDF was fundamental but that LERP could vary from site to site and might not be appropriate as a fundamental goal.
Dr. Apostolakis questioned the consideration of the most vulnerable individual in terms of early fathlity.
He also questioned the consideration of latent fatality frequency.
He expressed the view that societal risk would have more site-to-site variability.
At the conclusion of the briefing, Dr. Kress solicited ideas from the Members to be included in a future letter to the Commission.
l Dr.
Powers suggested that Mr. Sherry's study be subjected to
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external peer review.
Drs. Kress and Powers volunteered to pursue this matter and report to the Committee in September 1997.
Conclusion The Committee expects to prepare a letter to the Commission during a future ACRS meeting.
The Committee decided to submit the study completed by the ACRS Senior Fellow for external peer review.
IV.
Proposed Standard Review Plan Section and Reculatorv Guide for Risk-Informed. Performance-Based Inservice Insoection (Open)
[ Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. George Apostolakis, Chairman, Subcommittee on Probabilistic Risk Assessment (PRA), introduced the topic to the Committee.
He stated that the purpose of the briefing was to review the proposed Regulatory Guide DG-1063 and Standard Review Plan Chapter 3.9.8 for risk-informed, performance-based inservice inspection (ISI) for piping.
He noted that the ACRS Subcommittee on PRA had also met on July 8, 1997, with the staff, industry representatives, and other interested parties to discuss these documents and industry initiatives.
443rd ACRS Meeting 7
July 9-11, 1997 NRC Staff Presentation Messrs. Thomas King, RES, and Gary Holahan, NRR, led the discus-sions for the NRC staff.
Messrs. Goutam Bagchi and Syed Ali, NRR, and Jack Guttmann and Lee Abramson,
- RES, provided supporting discussion.
Significant points raised during the discussion includes Based on discussions with the Subcommittee, the staff plans to e
make the following changes prior to issuing the documents for public comment:
Section 4.2.5 of DG-1063 will be expanded to provide a more complete list of what should be considered in assessing the consequences of pipe failure (e.g.,
sprinkler actuation, electrical shorts, etc.).
Section 4.3 of DG-1063 will be expanded to more clearly allow for recognition and consideration of unquantifiable benefits (e.g., ALARA).
Section A2.5.5 of DG-1063 will be revised to clarify guidance to address screening out of unimportant pipe segments and to provide additional guidance related to sensitivity studies (e.g., test assumptions, importance categorization, etc.). of DG-1063 will be expanded to provide additional guidance for inspectors on where and how to look for degradation mechanisms.
Questions to solicit public comment include items concerning:
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- Clarity, completeness, and level of detail in the documents.
The appropriateness of sample size of welds to be inspected for High and Medium Safety Significant pipe segments.
Methods for selecting welds in the sample population for inspection (e.g.,
- randomly, most risk significant, combination of random / risk, etc.).
Allowance for licensee assessment and proposed ISI changes in lieu of assessing entire plant's piping.
Accounting for the time dependence of degradation mechanisms in selecting inspection intervals and catego-l rizing the safety significa:.ce of pipe segments.
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- s-e 443rd ACRS Meeting 8
July 9-11, 1997 Determining whether qualitative assessments can be used to identify and categorize pipe segments.
Determining whether ISI requirements can be eliminated from pipe segments if the risk from failure is negligi-ble.
Dr. Apostolakis asked whether the staff agreed or disagreed with the two approaches proposed by industry (Westinghouse /American Society of Mechanical Engineers and Electric Power Research Institute (EPRI)).
The staf f stated that it was too early to agree on the EPRI approach and noted that there is no absolute basis for comparison without actual submittals.
Dr. Apostolakis noted that the major dif ference is that the EPRI approach does not involve the calculations and modeling that exists in the ASME/ Westinghouse approach.
Dr. Apostolakis also questioned the scope of ISI sampling.
In particular, he questioned whether the sample would be selected randomly or whether the same welds would be evaluated.
The staff offered to address the issue of randomness in the list of questions soliciting public comment.
Drs. Kress and Apostolakis questioned the basis for deciding the inspection interval.
Dr.
Kress expressed the view that the rationale / criteria have little to do with risk.
The staff stated that each application is situational in terms of probability for failure and that each degradation mechanism needs to be addressed commensurate with its safety significance.
The staff further stated that the actual testing intervals (3, 7, and 10 year) do not change.
The size of the sample changes (i.e., welds to inspect) based on inspection findings.
The staff concluded that the risk-informed ISI program focuses attention on safety significant pipe segments.
At the conclusion of the briefing, ACRS Members expressed generally favorable views regarding DG-1063 and SRP Chapter 3.9.8.
Dr.
Apostolakis stated that the staff had done a good job in developing these guidance documents and expressed support for the proposed changes and questions for public comment.
conclusion The Committee issued a report to Chairman Jackson, dated July 14, 1997, on this matter.
t 443rd ACRS Meeting 9
July 9-11, 1997 V.
Mggtino with NRC Commissioner McGaffican (Open).
[ Note:
Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.)
Dr.
- Seale, ACRS
- Chairman, welcomed NRC Commissioner Edward
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McGaffigan and stated that the Committee was pleased to have the opportunity to hear the Commissioner share his thoughts on items of current and mutual interest.
The Committee members appreciated the Commissioner's views on the Direction Setting Issues and praised the way his response was crafted.
The Commissioner offered his views on how the NRC could operate more efficiently and effectively.
Some of the issues that were discussed include the following:
Restructuring of the ACRS Subcommittees e
The 10 CFR 50.59 rulemaking process e
Lead Test Assembly for Tritium production at Watts Bar e
PRA Implementation Plan Risk-informed, performance-based regulation e
e Research activities and the role of the ACRS S
Department of Energy (DOE) oversight Timeliness and the duration of the rulemaking process e
The Commission's Safety Goals and associated implications e
e The AP600 design / technical issues e
NRC and licensee resources Conclusion This session was for information only.
However, the Commissioner encouraged the Committee to follow up on the following:
e Committee views on the choice of DOE facilities that would be transferred to the NRC and the associated pilot programs Briefing by OGC regarding the legal problems associated with e
plant-specific applications of PRA and other related matters (attorney-client privilege)
VI.
Pronosed Final Modifications to 10 CFR Part 26. Fitness-For-Duty Procram Recuirements (Open)
[ Note:
Mr. A. Singh was the Designated Federal Official for this portion of the meeting.]
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443rd ACRS Meeting 10 July 9-11, 1997 Introduction Mr. John J. Barton, Chairman 'of the Plant Operations Subcommittee, I
introduced the topic to the Committee.
Mr. Barton stated that the l
purpose of this presentation was to brief the Committee regarding the proposed final modifications to 10 CFR Part 26, Fitness-For-Duty (FFD)' Program Requirements.
NRC Staff Presentation The NRC staff presented the background and the purpose for issuance of the proposed final modifications to 10 CFR Part 26.
The purpose of the proposed amendment is to improve the effectiveness of licensees' FFD programs, reduce unnecessary burdens, and ensure continued protection of public health and safety.
The staff prepared a draft NUREG document which summarizes public comments and associated staff responses on the proposed amendment to 10 CFR Part 26.
The draft associated NUREG document also discusses the comments and staff responses in relation to FFD programs at other Federal agencies.
The staff concluded that the proposed final modifications would not impose any additional burden on the industry;
- moreover, some modifications would reduce l
licensees' administrative burden and provide increased clarity and
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consistency to 10 CFR Part 26 requirements.
Conclusion t
The Committee issued a letter to the EDO, dated July 15, 1997, on this matter.
VII. Halden Reactor Proiect (Open)
[ Note:
Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.]
Dr. Dana Powers, Cognizant ACRS Member, welcomed the NRC staff and Dr.. Erik Hollnagel, of the Halden Reactor Project (HRP).
Dr.
Powers stated that HRP is an internationally funded cooperative agreement among a number of countries belonging to the Organization for Economic Cooperation and Development (OECD).
The HRP's activities are centered at the Halden heavy-water reactor and its associated man-machine laboratory in Halden, Norway.
The programs conducted at Halden consist of studies on software quality assurance, man-machine systems research, high-burnup fuel perfor-
- mance, degradation of in-core materials, and water chemistry effects research.
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443rd ACRS Meeting 11 July 9-11, 1997 Mr. Jay Persensky, RES, stated that the NRC has participated in the HRP since 1958.
The NRC staff uses the Halden-generated products and information in the development of analytical tools and regulatory guidance. The staff plans to continue its participation during the 1997-1999 agreement period because of the benefits received and the leverage of resources by participation with 14 signature and 7 associate members representing 19 countries.
The main HRP activities address nuclear fuels and materials performance and improved operational safety and efficiency through improvements in control room design.
Since initial startup, the reactor facility has been updated and over 300 in-reactor experi-ments have been performed.
The HRP maintains comprehensive facilities and research staff for performing experimental research on issues regarding the human-system interfaces for advanced technology.
These facilities include the Halden Man-Machine Laboratory, which contains a full scope PWR simulator, a modifiable CRT-based operator interface, and an extensive automated system for recording and analyzing experimental data.
The HRP has been an integral part of the development of NUREG-0700, Rev. 1, " Human-System Interface Design Review Guidelines." Another example of how a HRP designed product is used in the NRC research program is presented in NUREG/CR-6398," Evaluation of the Computer-ized Procedures Manual II (COPMA II)."
The purpose of this study was to evaluate the effects of a computerized procedure system on the performance and mental workload of licensed reactor operators.
COPMA II, designed and developed by HRP, contains features that display system parameters and provides graphics that allow operators to track their progress through several parallel paths of procedures.
Mr. Persensky outlined the overall objectives of a Human Error Analysis Project (HEAP) developed by Dr. Erik Holinagel (Institutt For Energiteknikk/OECD-HRP). The objectives of HEAP are to provide a better understanding and explicit modelling of how and why
" cognitive errors" occur and provide improved design guidance for advanced control rooms.
HEAP has pilot experiments that compare concurrent and interrupted verbal protocol techniques, test how eye movement tracking analysis can supplement verbal protocol, and test effects of complexity on performance. Some of the HEAP experiments are designed to investigate the relation between error rate and error detection in control rooms.
Mr. Leo Beltracchi, RES, stated that HRP conducts research to j
ensure and enhance the quality of computer-based systems.
The research addresses topics covering various types of instrumentation and control systems.
The development and application of both formal and conventional methods to verify and validate high integrity software are also subjects of HRP research.
The HRP also
443rd ACRS Meeting 12 July 9-.11, 1997 de'veloped a Picture Assembly Software (PICASSO) which is a user interface management system to be used.to generate display formats for. computer graphic displays.
The PICASSO software is the foundation of the nuclear engineering workstation simulstor (NEWS) developed by the NRC technical training division (TTD) staff for use at the technical training center (TTC).
The NEWS can be connected to the TTC full-scope simulators to display simulator model output that is not readily available on the full-scope simulator benchboards and to show physical phenomena in such a way as to add to the conceptualization of system interactions.
The NEWS is also used to independently demonstrate the operation of control systems, component logics, and flow processes.
The use of NEWS has added substantially to the efficiency and effectiveness of the NRC technical training programs.
PICASSO is also the core of the new Safety Parameter Display System (SPDS) developed by the NRC TTD staff, which has recently been placed into operation on the BWR/4 simulator.
Another tool developed by the HRP is a Computer-ized Alarm System Tool (COAST), which is designed to build and execute alarm systems that filter, suppress, and structure alarms.
The HRP is also addressing the technical issues identified by the National Academy of Sciences for the study of the safety and reliability issues for digital instrumentation and control systems in nuclear power plants.
Mr. Harold Scott, RES, summarized the HRP activities in the areas of fuels and materials performance research.
He noted that in the early 1980s, the NRC de-emphasized its research and licensing reviews in the area of fuel behavior and did not actively follow the HRP work.
With the NRC's recent interest in high-burnup fuel operation, the results from HRP's experimental work in this area are now being used to update NRC's analytical codes (e.g., FRAPCON) and to support licensing reviews for extended burnup.
The NRC has an extensive research program to provide an independent understand-ing of irradiation assisted stress corrosion cracking (IASCC) of core internals sufficient to permit reliable assessments of licensee submittals concerning such issues as residual life, inspection intervals, and replacement / mitigation strategies. The IASCC research is being performed at Argonne National Laboratory.
The Argonne test program relies on Halden to irradiate specimens of known prespecified fluences.
The Halden work on materials perfor-mance will be extended through 1999.
Other future Halden results to be utilized by the NRC are corrosion tests with new cladding alloys, Gadolinia fuel temperature and gas release, and mixed-oxide (MOX) fuel temperature and gas release.
Conclusion This briefing was for information only.
The Committee, however, plans to follow up on the progress of this project.
r 443rd ACRS Meeting 13 i
July 9-11, 1997 VIII.Use of RASCAL Ccde Durino Incident Resoonse (Open) i (Note:
Mr.
P.
Boehnert was the Designated Federal Official for this portion of the meeting.]
Introduction f
Dr.
- Seale, Acting
- Chairman, Occupational and Environmental Protection Subcommittee, introduced this topic to the Committee.
He noted that this session was scheduled as a follow-on from a I
cLiscussion held during the December 5-7, 1996, ACRS Meeting when ACRS Members raised questions about the use of the RASCAL code by the NRC to aid decisions related to protective action decision-t making.
Specifically, concerns were expressed associated with prediction of fission product dispersal, especially for the case of low-energy releases.
The ACRS, therefore, requested a briefing from representatives of the NRC staff regarding the uses and limitations of the RASCAL code.
AEOD Presentation f
i Dr. Frank Congel, AEOD, discussed the role of emergency dose I
projection in protective action decisionmaking and the key features of an emergency dose projection system. Regarding the former, AEOD noted that prompt response is critical in the early phase of a radiological accident and a
qualitative projection of dose estimates is all that can be expected at that stage.
For the latter, the dose projection system is intended to identify areas where potential offsite exposures could exceed the Protective Action Guides established by the Environmental Protection Agency (1-5 Rem).
The NRC staff uses the RASCAL dose assessment computer model to simulate potential offsite exposure from radionuclide releases from nuclear power plants.
Details of the atmospheric dispersion models used in RASCAL were discussed by Dr.
J. V.
Ramsdell, Jr. (Pacific Northwest National Laboratory).
He noted that three versions of RASCAL exist:
Versions 2.1, 2.2, (the current version in use by AEOD), and 3.0 the developmental version. The key upgrades to Version 3.0 include the addition of the NUREG-1465 source term and a major revision of the meteorological and atmospheric dispersion models. Mr. Ramsdell noted that Version 3.0 underwent extensive peer review by three different cognizant groups.
Dr. Ramsdell described the dispersion model, release characteriza-tion, environmental description, and model output.
For each, the differences among the code versions were discussed.
Dr. Powers questioned why the Gaussian plume model was utilized in this code.
Dr. Ramsdell replied that no other dispersion models exist that are
v 443rd ACRS Meeting
. July 9-11,'
1997 14 as easy to use and provide results superior to the Gaussian model.
Results'of the evaluation of the near-field dispersion model were discussed, as was a code vs. data comparison for two release events that occurred at the Hanford site a series of Krypton-85 releases and an accidental release of Iodine-131.
The. near-field model evaluation gives evidence that this model overpredicts at high (>10 meters /sec.) wind speeds.
The code calculations for the Hanford data show acceptable results.
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As a consequence of the above discussion, two issues were identi-I fled for -follow-on: (1) the way NRC addresses the issue of-recovery i
of areas that may have been judged to be unavailable, based on
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initial dose projections that later turn out to be in error, and (2) the way plant workers are treated in the case of a low-energy radiological release that results'in contamination in and around the~immediate site (e.g., an event that occurs during a refueling outage).
Dr.
Powers stated that the latter event may have
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implications for shutdown risk, in relation to the proposed rule I
pertaining to shutdown and spent fuel pool operations.
I Conclusion This briefing was for information ' only.
The Committee will consider these issues further and may hold additional discussions on this matter during a future meeting.
)
IX.
Recommendations for Probabilistic Seismic
. Hazard Analysis; Guidance on Uncertainty and Use of Exnerts (open)
(Note:
Mr. A. Singh was the Designated Federal Official for this portion of the meeting.)
Dr. William Shack, Chairman of the Structural Engineering Subcom-mittee, introduced the topic to the Committee.
Dr. Shack stated that the purpose of this presentation was to brief the Committee regarding the results of NUREG/CR-6372, which was prepared by the Lawrence Livermore National Laboratory for RES.
This NUREG documents the recommendations resulting from a study performed by the Senior Seismic Hazard Analysis Committee (SSHAC), which was organized and co-sponsored by the NRC,.the Department of Energy, and the Electric Power Research Institute.
The' objective of the study performed by SSHAC was to develop implementation guidelines, including a recommended methodology, suitable for performing a Probabilistic Seismic Hazard Analysis (PSHA) for use in regulating nuclear power plants.
J
.l
.a 443rd ACRS Meeting 15 July 9-11, 1997 The SSHAC report concluded that many of the major potential pitfalls in executing a successful PSHA are procedural rather than technical in character.
One of the most difficult challenges for the PSHA analyst is to properly represent the wide diversity of 1
expert judgments about the technical issues taking into account the large uncertainties.
This conclusion was primarily based on procedural guidance.
)
Conclusion This briefing was for information only.
No Committee action was required.
X.
EXECUTIVE SESSION (Open)
[ Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.)
A.
Reports, Letters and Memoranda e
Procosed Reculatory Guide and Standard Review Plan Chanter for-Risk-Informed. Performance-Based Inservice Insoection (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated July 14, 1997.)
Pronosed Final Revisions to 10 CFR Part 26. Fitness-For-Duty Recuirements (Letter to L. Joseph Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated July 14, 1997) e Procesed Final Revision 3 to Reculatorv Guide 5.44.
" Perimeter Intrusion Alarm Systems" (Memorandum to L.
Joseph Callan, Executive Director for Operations, NRC, f rom John T.
Larkins, Executive Director, ACRS, dated July 15, 1997) e Procosed Direct Final Rulemakino Chanaes to Paracraoh (h) of 10 CFR 50.55a. " Codes and Standards" (Memorandum to L. Joseph Callan, Executive Director for Operations, j
NRC, from John T.
Larkins, Executive Director, ACRS, i
dated July 15, 1997)
B.
Reconciliation of ACRS Comments and Recommendations
[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.)
l 443rd ACRS Meeting 16 July 9-11, 1997 i
Thie Committee discussed the response from the NRC Executive Director for Operations to ACRS comments and recommendations included in recent ACRS reports:
The Committee discussed the response from the EDO dated e
June 12, 1997, responding to ACRS comments and recommen-dations included in the ACRS report dated May 7,
- 1997, concerning design basis verification.
The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the EDO dated June 23, 1997, responding to ACRS comments and recommen-dations included in the ACRS report dated May 8,
- 1997, concerning the proposed final policy statement on the restructuring and economic deregulation of the electric utility industry.
The Committee decided that it was satisfied with the EDO's response.
'The Committee discussed the response from the EDO dated July 7,1997, responding to ACRS comments and recommenda-tions included in the ACRS report dated May 9,
- 1997, concerning stockpiling of potassium iodide.
The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the EDO dated July 9,1997, responding to ACRS comments and recommenda-tions included in the ACRS report dated May 23, 1997, concerning regulatory guidance for implementation of digital instrumentation and control systems.
The Committee decided that it was satisfied with the EDO's response.
C.
Report on the Meeting of the Planning and Procedures Subcommittee (Open)
The Committee heard a report from Dr. Seale on the Plan-ning and Procedures Subcommittee meeting held on July 8 and 10, 1997.
The following items were discussed:
)
.. o.
443rd ACRS Meeting 3 17 July 9-11, 1997 1)
COMMISSION REOUIREMENTS IN ACRS SUBCOMMITTEES (Open)
In a memorandum from John C.
Hoyle, SECY, dated June 30, 1997, the Commission requested that the ACRS reevaluate its subcommittee structure to determine the appropriate number of primary subcom-mittees that are needed to carry out ACRS responsi-bilities.
Additionally, we should conduct a peri-odic review to keep the number as low as is consis-tent with the programmatic Committee needs.
ACRS staff is currently preparing a proposed subcommit-tee restructure for Committee review and comment.
The ACRS. should also reevaluate how it interacts with other NRC advisory committees so that issues-can be readily identified and - communication en-hanced between committees.
Guidelines have already been developed for interaction between ACRS and Nuclear Safety Research Review Committee (NSRRC) and are currently in use.
RECOMMENDATION The Subcommittee recommended that the Executive Director, ACRS, and the Chairman, ACRS, draft a proposed response for Committee approval at the September 3-5, 1997 meeting.
ACRS Members should also provide their comments on the proposed subcom-mittee structure to S.
Duraiswamy by August 8,.
1997.
2)
STAFF REOUIREMENTS MEMORANDUM ON WESTINGHOUSE AP600 (open)
The Commission issued a Staff Requirements Memoran-dum that, based on the uncertainties associated with the performance of passive safety systems, the AP600 should include a containment spray system or equivalent for accident management.
This is con-sistent with the ACRS recommendation.
It was also suggested by the Commission that the staff work with the ACRS for a complete understanding of the ACRS concern, noted in our letter of June 17, 1997, that the design concept of the spray system as suggested by the staff is " marginally adequate."
The Commission also directed the staff to continue to explore methods for dealing with uncertainty in applying PRA in a regulatory framework.
I
.j_
443rd ACRS Meeting 18 July 9-11, 1997-RECOMMENDATION The Subcommittee recommended that the ACRS staff schedule a briefing on the AP600 containment at the earliest possible date.
The staff should also work with NRR and RES to develop a schedule for provid-ing recommendations to the Commission on the use of uncertainty in applyin PRA in the regulatory decisionmaking process. g 3)
COMMISSION REQUIREMENTS ON PERFORMANCE MEASURES FOR THE ACRS/ACNW (Open)
In response to the Strategic Assessment Issue Paper:
Independent Oversight (DSI 19), the Execu-tive Director, ACRS/ACNW, forwarded a memorandum to the Commission recommending that the ACRS and ACNW remain as separate advisory committees for the next two to three years.
The memorandum also suggested performance measures and criteria for evaluating the effectiveness of the ACRS and ACNN, and, based on a ' comprehensive review of the ACRS and ACNW charters, concluded that no change was necessary.
The Commission agreed with the recommendation for continued separation of the ACRS and ACNW and that-it was not. necessary to ' change the Charters for either Committee. They agreed that the performance criteria and measures were reasonable; however, they requested that we propose additional perfor-mance measures and criteria that would permit the commission to relate the benefits received from Committee activities to total resources expended relative to Committee operations and activities.
In response to this, ACRS/ACNW staff has developed a proposal to address this Commission request.
RECOMMENDATION The Subcommittee recommended that the ACRS staff meet with individual Commissioners to determine what specific performance measures will best reply to their request.
The_ staff will provide a draft performance assessment of the ACRS for approval at the September 3-5, 1997, meeting.
1 a
443rd ACRS Meeting 19 July 9-11, 1997 4)
USE OF CDP OF 10-* AS A FUNDAMENTAL SAFETY GOAL (open)
{
l In a memorandum dated July 2, 1997, Chairman Jack-son directed the EDO to develop a policy paper to the Commission with the staff views on the merits of the ACRS recommendation to elevate the subsid-iary CDF objective to a fundamental Safety Goal.
No suspense date was established for this task.
The ACRS might want to help the staff develop this
(
policy paper and facilitate the industries' partic-ipation in commenting on this proposed policy.
This issue and others related to the use of PRA in the regulatory process need to be integrated.
RECOMMENDATION The Subcommittee recommended that the ACRS staff work with NRR and RES to develop a recommendation I
for the Commission and address industry concerns on this issue.
This issue will have to be coordinated with ongoing PRA/ Safety Goal activities and pro-jected future actions.
5)
STATUS OF ACRS BUDGET FOR FY 1998 AND BEYOND (Open)
As a status report, the Executive Council for the NRC has recommended to the Commission that the ACRS/ACNW Office budget be held at the FY 1997
-level, except in the case of a 5 percent reduction from either the Office of Management and Budget or Congress, in which case it has been suggested that the ACRS reduce its resources by 10 percent, which would result in a reduction in ACRS meetings and ACRS support staff (pp.18-19).
6)
STATUS OF TRANSFERRING NSRRC RESPONSIBILITIES TO THE ACRS (Open)
Since the last discussion on this subject, a draft commission paper has been revised several times due to disagreement on the resources required for the ACRS to assume NSRRC responsibilities.
Currently, we are suggesting that the resources being provided i
will only accommodate 1 full Committee and 1 sub-committee meeting, which would probably occur in
{
January or February.
At some point in the future we would evaluate whether a second full Committee meeting and subcommittee meeting would be neces-l sary.
It is anticipated that the SECY paper will
443rd ACRS Meeting 20 July 9-11, 1997 go to the Commission during this full Committee meeting.
This matter should not be discussed in an open meeting until the SECY paper is made public.
7)
FUTURE FOREIGN AND DOMESTIC TRAVEL (Open)
Any Member planning ACRS-funded foreign travel or domestic travel must request this travel prior to the end of July in order for it to be included in the FY 1997 travel budget.
Any projected ACRS-sponsored travel should be brought to the attention of the office as soon as the pertinent information is available.
RECOMMENDATION The Subcommittee recommended that the Committee approve travel for T. Kress to Luxembourg and D.
Powers to Denver.
Dr. Powers also recominended that the ACRS discuss having one or more Members attend the Halden Project meeting in Norway in FY 1998.
Dr.
Seale recommended that a Member attend the International Atomic Energy Agency Conference on upgrading fire safety for operating power reactors.
The Committee approved travel for Dr. Kress and Dr.
l Powers.
Dr. Miller and Dr. Apostolakis expressed j
an interest in attending the Halden Project meet-ing.
They agreed to postpone a decision on the IAEA and Halden meetings until the September 3-5, 1997 meeting.
8)
FORTIETH ANNIVERSARY OF THE ACRS (Open)
Dr. Apostolakis has noted that the Fortieth Anni-
{
versary of the ACRS will occur in October 1997 and has suggested that the Committee might want to commemorate this significant event.
RECOMMENDATION The Subcommittee recommended that the Committee have a coffee and cake reception to celebrate this occasion and invite the Commissioners and NRC Senior Management.
The Subcommittee also recom-mended that ACRS issue a press release commemorat-ing this anniversary.
The Committee agreed to have a reception and issue a press release.
o
'443rd ACRS Meeting 21 July 9-11, 1997 9),
. STATUS OF APPOINTMENT OF MEMBERS. (Open)
The ACRS Executive ' Director has contacted three individuals with expertise in the area of thermal hydraulics and computational fluid dynamics about applying for membership on the Committee, and, as a consequence, expects to have at least two names to forward to the Commission prior to the end of September 1997.
The Executive Director will ar-range telephone interviews for any member interest-ed in talking with these individuals prior to having their names forwarded to the Commission for consideration.
RECOMMENDATION The Subcommittee recommended that the Committee endorse forwarding the names of additional candi-dates for ACRS membership to the Commission.
10)
MEMBER ISSUES (Open)
Dr.
Powers raised the issue of ACRS review of licensee renewal activities. He suggests consider-ation of the formation of a subcommittee that is devoted to license renewal issues and that.the subcommittee start reviewing background material as soon as practical.
RECOMMENDATION The Subcommittee recommended that the License Renewal Subcommittee be reactivated and develop a schedule for reviewing licensee and staff activi-ties in this area.
D.
Future Meetina Acenda Appendix IV summarizes the proposed items endorsed by the Committee for the 444th ACRS Meeting, September 3-5, 1999.
The 443rd ACRS meeting was adjourned at 12:12 p.m. on Friday, July 11, 1997.
W N. WiPNy, June 24, 1997 / NoticMNC S4089 doc'amants are cvailable for public frequency and
,early release 2:25 pm.-2M5
/
laspection et the Commlaston's Public frequency, when lower-tier criteria Activities (Open)fm.:Psrtum ACRS h Committee will Document Room,the Celman Bauding, are derived from the apt intality discuss the recommendations of the 2120 L 8treet, NW., W Ma='an; DC, quantitative health vos.
Planning and Pmeedums Sub-and at the local public document room Representatives of NRC staff will committee regarding items proposed for located at the AthensPublic library,405 participate.
consideration by the full Committee i
- . South Strost Athens, Alaha== 35611.
Impme2:30pm.; Proposed during future meetings.
\\
g StandardReviewPlan Secdon and geseg og neck,gge, mgary ang, egg, segg g,,
Regulatory Guidefor Risk-informed, 2M5 pm.-2mpm.:Recoachtion of etgaaeteer.
ACRS Comments and For the Nuclear Reguletery th=i-t=
PsiformanceBased laservice InspecHon Recommendades (Open)-b Jenspb F WMuans, (Open)--h r===ittee will hear Committee will discuss responses from g
presentations by and hold discussions b NRC Executive Director for g,,,g, gg,,,,g m g.,*
with representatives of the NRC staN Operations (EDO) to comments and EcJoerAnscear yp,f the Standard.
recommendations included in recent
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for risk-h pmvi hased inservice laspection.
ra==ittee prior to the meeting 2M5 pm?3M5pm.:Meeung with 2m p.m.-7m pm.:Paparotion of
'NUCt. EAR REQUI.ATORY NRCCommissionerMcGoffigan ACRS Reports (Open)--h Committee (Open)--b ra==Ittee wm meet with
- will discuss proposed ACRS ports on nnannaammerm NRC Commissioner necCaf5gan to.
O AsfvisoryCommletesenRemotor discuss items of mutuallaterest.
matters canaldered during this meeting Safeguer isSeesung Nolloo including AGS activities and NRC.
Psiday,Joly 11,1997
-seeensch c:30 ames:ss a.m.: Opening la accordance with the pwgoees of 4mpm.-4mpm.:PsoposedPtnal Remarks by the ACRS Chairman
. Sections 29 and 182b.of the ntomic
. Energy Act (42 tJ.S.C. 2089,2132b), the Modificadons to JD GR Part 28,
{0 pen)--b ACRS Chairman will make Advisory Committee on Ranctor PJtness-For'DirtyProgram uframents opening reenarks regarding the conduct Safeguards will hold a seesting on July (Open)--b Committee will of b meeting 9-11,1997,in Conference Room T-2B3+ presentations by and hold discussions s:35 am.-20m a.m.:NUREG/CR-11545 Rockville Pike,Rockville, with mpresentatives of the NRCstaf 8372.Recomunendationsfor naaryland. N date of this muting was regarding b propoeed Anal Pi A,.wre-S SeismicNasanf Analysis, vlously published in the Federal modifications to atness-for duty Guidance on Uncertaintyand Use of aginese on Thweday, January 23,1997 program requirements.
Expwis(Open)-N Conunitwo wdl
,62FR3539).
8:25 par 7:25 pm.:Pipparadon of hear presentations by and hold ACRS Reports (Open)--h Committee discussions with representatives of the Nedneedey, July s,1907 will discuss proposed ACRS sportsan NRC staN and its contractois regarding 8
cm 5a matters considend durintthis meeting NUREG/CR-6372.
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as well as a proposed Acas report on 20:25 a.m.-22m am.: Report of the.
> pen) - e ACRS Chairman will snake the use of risk-informed, periannance-P1 andProcedures Subcommittee IWI8 WMPo
- P "8 "
da a comm bri y o th 1 and regar items of current interest.
Thereday, July 10,1987 Proceduru Subcommittee on matters Dming session, the Comuninae will discuss priettim forpapandon of 8:30 am.-8:35 cm.:Openi'If inwa cad as o dates ACRS repets.
. Remarks bythe ACRS Chairman nominstehu
- Ih (Open)--%e ACRS Chairman will maks forap intment to the
,'#hjyj f
markss gardingconductof ACRS[ssoladng to b ACRS. personnel and tional and gg, yg matte NssclearRecteReguladn WRR) 8:35 aml20:30 am.:Nalderineoctor M A & m ble m elom m &
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'(Open)-b Committee will hear Pts (Open/Clomd)-b Committee
" ***** "'**I'I'**I '"#
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ads
- "d ai f
3 o,,'hi' mutualinterest, including low and shutdown operations risk, power NRC staN and its contrectors regarding nienne of which would constitute a clearly nux h ongoing and planned work at the sawarranted leveston of personal privacy.1 researchawds statuQs nspeedon OECD Halden Reactor Project in the 22mo.m-22mNoon Preparadon
,, N E,and bACRS mal coordinadosof CRSreviewofNRR
- Ports on matters conal eb during (Note: A activities'me22:00 noon: Acceptance Cl***d '* d' portion of this sessies a ey bethis meeting J0:30 a
- C*** I*I**'I** F'evided in 2m mesapm.:Pseparation of Criteria for Plant. Specific Safety Goals eenfidence by a foreign sowoe.)
ACRS (Open)--b Committee andDedvinglower*71ierAcceptance 20:45 a.m.-22:25 pm.: Use af will con ne its discussion of proposed Crfteria (Open)-b Committee will RASCAL Code Duringincident ACRS reports on matters considered bear a prwentation by and hold Response (Open)-b Committee will during this meeting i
discussions with the ACRS Senior hear prwentations by and hold 3:25 pm,-dmpm.: Strategic illow regarding b results of his discussions with representadves of b Planning (Open)-b Committee will
.alysis riormed to determine the NRC staff renarding the use of the continue its discussion ofitems of
.ite-s e changes in core damage RASCAL code to calculate off site doses. significant importance to NRC, O
,64090 Federal Mie / W1. 82, No.121 / Tresday, Jun;, 24,1997 l'N tices including rebaselining of the Committee ACRS meeting' notices, meeting http1/www.nre. gov /SECY/sm}/
activities for FY 1998.
transcripts, and letter mports are now schedule /htm 4.00 30 pm:Miscelloneous available on FedWorld from the "NRC This notice is distributed by mail to (Open)p.m.-d:
-The Committee wul discuss MAIN MENU." Direct Dial Accus several bundred subscribers; if you no matters related to the conduct of number to FedWorld is (800) 303-9672 longer wish to receive it, or would like 4
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internet at http//www.nrc. gov /
415-1661).
Procedures for the conduct of and
- ACRSACNW, In addition, distribution of this meeting notice over the internet system j
Participation in ACRS meetings wer*
Dated: June is,1997.
1 is available.If u are interested in October 1,1996 (61 FR 51310). In Adrhary Comme = Managessent-race.tving this bmmission meeting f
published in the Federal Register on Aednw I. Beten, schedule electronically, pluse send an.
accordance with these procedures, oml (FR Doc.efeas FM Mur:a4s W electronic message to wmhenrc. gov or or written statements may be presented dkwenre gov.
by members of the public and nuclar
- e e
e e
e i
industry, electronic tocordings will be permitted only during the open portions NUCLEAR REGULATORY Dated: June 18,1997.
'Amesene viessM of the meeting, and questions may be COM m asked only by members of the Anantsecrocaryofdie cowa.
Committee,its consultants, and staff-Sunshine Act Moodn3
[Fh eMesto FM NW7 ad Persons dwiring to make oral statements AomeCY H0t.DeIG THE RIEETesa: Nuclear name aces me ei as s
should notify Mr. Sam Duralswamy, Chief, Nuclear Reactors Branch, at least Regulatory ^='at= ton.
tve days before the meeting,if possib' DAfts: Weeks of June 23,30, July 7 and NUCLEAR REGULATORY so that appropriate armngements car 14,1997.
COMMISSION Pt.Act:Comml= loners' Conference made to allow the necessary time dr the meeting for such stataments. ' u a Room,11555 Rockville Pike, Rockville, (Docket No.364es snel todos) 7 still, motion picture, and television Maryland.
cameru during this meeting may be STATUS:Public and Closed Document Room limited to selected portions of the mAmis To at coussosa Notice is hereby by given that the meeting as determined by the Chairman.
information regarding the time to be set Week ofJune 23 Nuclear Regulatory Ommi= ion (NRC) aside for this purpose may be obtained
- Wednesday, June 25 will be relocating thelocal public by contacting the Chief of the Nuclear 10:00 am Briefing on Operating document room (LPDR) for records Ructors Branch prior to the meeting. In Reactors and Fuel Facilities (Public pertaining to Washington Public Power.
view of the possibility that the schedule Meeting)[
Contact:
Supply System's Washington Nuclear 301-415-1726)
Units 3 and 5 (WPPSS) site located in for ACRS meetings may be adjusted by 11:30 a.m. A!!Lrmation Susion Satsop, Washington.The WPPSS LPDR the Chairtnan as necessary to facilitate (Public Meeting)(if sseeded) is curnntl located at the W.H. Abel the conduct of the meeting, persons 2:00 pa Briefing on Salem (Public g,,,,.lal
,125 Ma6 Street, piming to attend should check with the Chief of the Nuclear Reactors Brsnch Meeting)(Contact: John Zwolinsid' Montesano, Washington. Library staff 301-415-1453) informed the NRC that they no longer if such rwcheduling would result in major inconvenience.
W8'A Olhune 30--Tantatfre wish to aain'ain the document conection and request that it be moved.
In accordance with Subsection 10(d)
[
gI don Susion This notice invites pubbe comment on,
Public Law c2-463,I have determined Wbuc Matbg)(if needed) gossible LPDR locations in the Satso that it is necessary to close portions of Week offu 7-Tentative ashington, area.
this meeting noted above to discuse Tuesday'.
ation Session (Public Among the factors the NRC wiu -
a ruatters that relate solely to the internal 3:30 p.m consider in selecting a new location for personnel rules and pmetices of this.
Meeting)(if nesdod) the LPDR are the fonowing:
Advisory Committee per 5 U.S.C.
Week ofJuly 14-Tentative (1) Whether the institution is an.
552b(c)(2), to discuss information the Thursday,fufy 17 established document repository located release of which would constitute a 2:30 pa Meeting with NRC near the nuclear facility with a history clearly unwarranted invasion of Executive CouncU (Public Meeting) personal privacy per 5 U.S.C. 552b(c)(6).
(Contact:~ James L. Blaha 301-415-ofimpartially serving tne public; (2) The physical faciuties available, and to discuss information provided in 1703) confidence by a foreign source per 5 -
4:00 p.m. Affirmation Susion (Pub!!c including shelf space, storage space, U.S.C. 552b(c)(4).
Meeting)(if nuded) patron workspace, copying equipment and computer access; Further information regarding topia
.The schedule for CoWon Meednas is (3) The willingness and ability of the to be discusud, whether the meeting Subject To Change on Short Notics.
library staff to maintain theLPDR has been canceued or rescheduled. the To verify the status of Meetings Can collection and assist the pubuc in Chairman's ruling on requests for the.
(Recording). -(301) 415-1292. Contact Persais for More information: Bill Hill (301) 415-locating records; opportunity to present oral statements -
(4)The nature and extent of related and the time allotted therefor can bar teet.
research resouren, such as government obtained by contacting Mr. Sam The NRC Commi= ion Meeting documents:
Duralswamy, Chief, Nuclear Reactors Schedule can be found on the Internet (5)The public accessibility of the Branch (telephone 301/415-7364),
library, including hendicap between 7:30 as and 4:15 p.m. EDT.
at:
d
_A
UNITED $TATES Appendix II A
NUCLEAR RECULATORY COMMISSION y
l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS a
wAsmNGTON, D. C. 20696 June 24, 1997 SCHEDULE AND OUTLINE FOR DISCUSSION 443rd ACRS MEETING JULY 9-11, 1112, WEDNESDAY JULY 9, 1997, CONFERENCE ROON 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND 37 1) 8:30 -
8:55 A.M.
Onenino Remarks by the ACRS Chairman (open) 1.1)
Opening Statement (RLS/SD) 1.2)
Items of current interest (RLS/JTL/SD) 1.3)
Priorities for preparation of ACRS reports (RLS/SD) 39 U
2) 8:45 - 10:22 A.M.
Meetino with the Director of the NRC Office of Nuclear Reactor Reculation (NRR) (Open) (RLS/MME) 2.1)
Remarks by the ACRS Chairman 2.2)
Briefing by and discussions with the NRR Director on items of mutual interest, including low-power and shutdown operations risk, NRR research needs, status of fire inspection program, use of risk-informed, performance-based process for prioritizing compliance issues, and coordina-tion of ACRS review of NRR activities.
10:25 - 10:35 A.M.
- BREAK ***
CD 0%
3) 10 :De- - 12 : 90 NOON Accentance Criteria for Plant-Scecific Safety Goals and Derivino Lower-Tier Accentance Criteria (Open)
(TSK/MTM/RRS) 3.1)
Remarks by the Subcommittee Chairman 3.2)
Briefing by and discussions with the ACRS Senior Fellow regarding l
the results of the analysis performed to determine the site I
specific changes in core damage T
~Jn~ weiluOpo d,%r af % n,eebay )
)
2 s/
h frequency and large, early release frequency, when these lower-tier criteria are derived from the. prompt fatality quantitative health objectives.
i I
Representatives of the NRC staff will participate.
o 7-12:05 -
1:00 P.M.
- LUNCH ***
)
1 4) 1:00 -
2:3 P.M.
Pronomed Standard Review Plan Sertion and Reculatory Guide for Risk-Informed, Performance-Based Inservice Insnection (Open) (GA/MTM) 4.1)
Remarks by the Subcommittee Chairman 4.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed Standard Review Plan Section and Regulatory Guide for risk-informed, performance-
)
based inservice inspection.
N 2:3 2:45 P.M.
- BREAK ***
5) 2:45 -
3:45 P.M.
Meetina with NRC Commissioner McGaffican (Open) (RLS/MME) i 5.1)
Remarks by the ACRS Chairman 5.2)
Meeting with NRC Commissioner p* e* 6gcA*
McGaffigan to discuss items of mutual 3: 45 -
3 $"O 8
interest, including ACRS activities and NRC research.
3:fo 6i 1.S~
6)
N-Ge#O P.M.
Pronosed Final Modifications to 10 CFR Part (BREAK 4e95-5:00 P.M.)
- 26. Fitness-For-Duty Procram Recuirements f:or-520 (Open) (JJB/AS) 6.1)
Remarks by the Subcommittee Chairman 6.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed final modifi-cations to fitness-for-duty program requirements.
Representatives of the nuclear industry wil' g
participate, as appropriate.
/
)
/
,' I 3
- {
' S ! As 4: Vf 7) 6T99' -
7:15 P.M.
Prenaration of ACRS Reoorts - (Open)
Discussion of proposed ACRS reports on:
i 7.1)
Proposed Standard Review Plan Section and Regulatory Guide for Risk-Informed, Performance-Based Inservice Inspection (GA/MTM) 7.2)
Proposed Final Modifications to 10 CFR Part 26 (JJB/AS) 7.3)
Use of Risk-Informed, Performance-Based Process for Prioritizing Compliance Issues (TSK/PAB)
TEUREDAY. JULY 10. 1997. CONFin NCE ROOM 2B3. TWO WHITE FLINT NORTH.
ROCKVILLE. MJ4RYLAND j
8) 8:30 -
8:3fA.M.
Ooenino Remarks by the ACRS Chairman (Open)
(RLS/SD) 1 17 9) 8:35 - 10:36 A.M.
Halden Reactor Proiect (Open/ Closed) i (DAP/MME) 9.1)
Remarks by the cognizant ACRS member 9.2)
Briefing by and discussions with representatives of the NRC staff and j
its contractor regarding the ongoing and planned work at the OECD Halden Reactor Project in the areas of human factors, instrumentation and control
, systems, software quality, and reactor fuels.
[ Note:
A portion of this session may be closed to discuss information provided in confidence by a foreign source.]
27 10:90 - 10:45 A.M.
- BREAK ***
JL s/
- 10) 10:45 - 12:35 P.M.
Use of RASCAL Code Durino Incident Response (Open) (RLS/PAB) 10.1)
Remarks by the Subcommittee Chairman 10.2)
Briefing by and discussions with representatives of the NRC staff regarding the use of RASCAL code to calculate offsite doses.
l a m_f 31 3
12:35 -
P.M.
- LUNCH ***
A
___...,.,,d
r
,t 4
3y A:'T
)
11) 1:N 13W5 P.M.
Future ACRS Activiting (Open) (RLS/SD)
Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.
2:!S li 12) 2=95 2:00 P.M.
Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et.al./
SD, et.al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports.
18 5: 20 23) 2:06 -
W P.M.
Precaration of ACRS Renorts (Open)
(BRKAK 3333-3:30 P.M.)
Discussion of proposed ACRS reports on:
Q:gr-3;2o 13.1)
Proposed Standard Review Plan Section and Regulatory Guide for Risk-Informed, Performance-Based Inservice Inspection (GA/MTM) 13.2)
Proposed Final Modifications to 10 CFR Part 26 (JJB/AS) 13.3)
Use of Risk-Informed, Performance-
)
Based Process for Prioritizing Compliance Issues (TSK/PAB)
FRIDAY. JULY 11, 1997. CONFERENCE ROOM 2B3. TWO WHITE FLINT NORTH.
ROCKVILLE, MARYLAND
)
14) 8:3b -
8: $A.M.
Onenino Remarks by the ACRS chairman (Open)
(RLS/SD)
\\?t 'l 6 h N' fejdatbry)voSL O y Shul fynfg g),p oy - D,0LMS fplo 15) 8:Bk-10:$hA.M.
NUREG/CR-6372. Recommendations for Probabilistic Seismic Hazard Analysis; Guidance on Uncertainty and Use of Excerts (Open) (WJS/AS) 15.1)
Remarks by the Subcommittee Chairman 15.2)
Briefing by and discussions with representatives of the NRC staff regarding NUREG/CR-6372.
\\
W 11107 10 : M - 19,66 A.M.
- BREAK ***
i
)
[1 a
5
't
^ nso1 I Ll s 2.
16). 39535 - Abs @C A.M.
Reoort of the-Plannina and Procedures Subcommittee (Open/ Closed) (RLS/JTL)
- Report of.the Planning and Procedures Subcommittee on matters related to the conduct of ACRS. business, qualifications of candidates nominated for appointment to the ACRS, and organizational and personnel matters relating to the ACRS.
~[ Note:
A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory. committee, and information the zelease of which would constitute a clearly unwarranted invasion of personal.
privacy.)
- 17) 11:00 -
12:00 NOON
'frenaration hf ACRS Reoorts (Open)
C tinue disc sion of proposed ACRS rep ta on:
17.1 Proposed andard Review Plan ection and egulatory Guide for
' k-Informe Performance-Based In rvice Insp ction (GA/MTM) 17.2)
Prop ed Final difications to 10 CF art 26
(-
/AS) 17.3)
Use of sk-Inform Performance-Based Pro ss for P oritizing Compliance ssues (TS PAB) 12:00 -
1:00 P.M.
- LUNCH ***
18) 1:00 -
3:00 P.M.
Precaration\\bf ACRS Rhoorts (Open)
Continue discu on of oposed ACRS reports identifie under em 17.
jgin-
/2l/4 19) 9?ts -
4:00 P.M.
Stratecic Plannina (Open) (RLS/JTL)
Discussion of items of significant importance to NRC, including rebaselining of the Committee activities for FY 1998.
4 6
6 e.
)
- 20)
- 4 : 0 0' -
4.30 P.
Miscellaneous Open) (RLS/JTL/SD)
Discussion of m cellaneous matters related to the conduct.o Committee activities and matters and specif issues that were not completed during pre ious meetings, as time and availability of i ormation permit.
NOTE:
Presentation time should not exceed 50 percent of the total 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 e
to the ACRS - 35.
APPENDIXlil: MEETING ATTENDEES 443RD ACRS MEETING July 9,1997 NRC STAEE J. Mitchell, OEDO S. Dinsmore, NRR S. Ali, NRR S. Weiss, NRR L. Cunningham, NRR R. Rosano, NRR L. Abramson, RES J. Shackelford, RIV ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC A. Wyche, Bechtel T. Sutter, Bechtel H. Fonticello, VA Power R. Weston, ABB-CE B. Jaquith, ABB-CE M. Neal, NUS G. Weil, McGraw-Hill P. Riccardella, StructuralIntegrity Assoc.
4 R. Fougerouse, Entergy M. Beaumont, Westinghouse D. Sarley, PECO Energy Com R. Enkeball, NEl J. Hollerman, Self J. Savage, Morgan, Lewis, Bockius, LLP l
4 k
)
Appendix Ill 443rd ACRS Meeting NRC STAFF J. Mitchell, OEDO L. Beltracchi, RES M. McNell, RES J. Kramer, RES W. Hodges, RES R. Brill, RES J. Calvert, RES J. Persensky, RES H. Scott, RES R. Meyer, RES J. Ridgley, RES J. Guttman, RES S. Ali, RES -
G. Bagchi, RES N. Siu, RES J. Quissell, AEOD R. Hasselberg, AEOD F. Congel, AEOD A. Mohseni, AEOD E. Weinstein B. Zaleman, NRR ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC E. Holinagel, Halden Reactor Project J. Ramsdell, Jr., PNNL i
Appendix ill 443rd ACRS Meeting NRC STAFF J. Mitchell, OEDO B. Ibrahim, NMSS M. Bell, NMSS M. Lee, NMSS N. Choicshi, RES L. Shao, RES R. Kennerily, RES R. Komasiewicz, RES A. Murphy, RES E. Zurflueh, RES J. Costello, RES B. Hardin, RES R. McMullen, RES S. Dinsmore, NRR G. Bagchi, NRR ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC J. Kimbell, DOE A. Comell, ACA Co.
R. Benning, Battelle I
P. Robstock, Scientech J. Sanchez Caban6ro, Consezo Seguridad Nuclear A. Jimenez, Consezo Seguridad Nuclear R. Budnitz, RRA Inc.
I
..,,, n n ~. < g hug:MacO5ia(3?N/230MGTOW_l39tMl4genfaAQ43_444 Atml
' l,'
Appendix IV Arg:st 8,1997 SCHEDULE AND OUTLINE FOR DISCUSSION
(
444th ACRS MEETING SEPTEMBER 3-5,1997 WEDNESDAY SEPTEMBER 3,1997, CONFERENCE RODM 2B3, TWO WIIITE FLINT NORTH, ROCKVILLE, MARYLAND 1) 8:30 - 8:45 A.M.
Opening Remarks by the ACRS Chairman (Open) 1.1)
Opening Statement (RLS/SD) 1.2)
Items of current interest (RLS/JTL/SD) 1.3)
Priorities for preparation of ACRS reports (RLS/SD) 2)
8:45 - 9:45 A.M.
Staff Action Plan to Improve the Senior Management Meeting Process, SECY-97-072 (Open) (JJB/PAB) 2.1)
Report by the Subcommittee Chairman.
2.2)
Discussions with representatives of the NRC staff, as needed, regarding the action plan to improve the Senior Management Meeting process.
3) 9:45 - 10:45 A.M.
Draft Regulatory Guide DG-1069: Fire Protection Program for Permanently shutdown and Decommissioning Nuclear Plants (Open) (DAP/AS) 3.1)
Remarks by the Subcommittee Chairman.
3.2)
Briefing by and discussions with representatives of the NRC sta.ff regarding the draft Regulatory Guide on the fire protection program for permanently shutdown and decommissioning nuclear plants.
10:45 - 11:00 A.M.
- BRRAK***
4) 11:00 - 12:30 P.M.
Proposed Generic Letter and Regulatory Guide Associated with Steam Generator Integrity (Open) (RLS/NFD) 4.1)
Remarks by the Subcommittee Chairman.
4.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed Generic Letter and Regulatory Guide associated with steam generator integrity.
Representatives of the nuclear industry will participate, as appropriate.
l 12:30 - 1:30 P.M.
- LUNCH ***
5) 1:30 - 2:00 P.M.
Reporting Reliability and Availability Information for Risk-Significant Systems I cf 6 12/04/97 18:36:05
wiMg littp:ftec.nrc. gov /ACRS/rrs t / agendas _ACRS/A genda_A CRS_444.html
'll and Equipment (Op:n) (GA/MTM) 5.1)
Report by the Subcommittee Chairman.
5.2)
Discussions with representatives
{
of the NRC staff, as needed, regarding the voluntary approach proposed by the industry for reporting reliability and availability information for risk-significant systems and equipment.
Representatives of the nuclear industry will participate, as appropriate.
6) 2:00 - 2:30 P.M.
NRC Programs for Risk-Based Analysis of Reactor Operating Experience and Special Studies (Open) (GA/AS) 6.1)
Report by the Subcommittee Chairman.
6.2)
Discussiona with representatives of the NRC staff, as needed, regarding the NRC Programs for Risk-Based Analysis of Reactor Operating Experience as well as the results of several special studies performed by the staff, including those related to auxiliary feedwater, Westinghouse reactor protection systems, loss of cffsite power, initiating events, reactor core injection cooling, high pressure core injection, and fire events.
I 7) 2:30 - 3:30 P.M.
Site-Specific Safety Goals (Open)
(TSK/NFD/RRS) 7.1)
Remarks by the Subcommittee Chairman.
7.2)
Briefing by and discussions with an ACRS Senior Fellow, and representatives of the NRC staff, as needed, regarding the use of site-specific safety goals.
3:30 - 3:45 P.M.
- BREAK ***
8) 3:45 - 4:15 P.M.
Use of Uncertainty Versus Point Values in the PRA-Related Decisionmaking Process (Open) (GA/MTM)
Report by the Subcommittee Chairman regarding issues discussed / raised on the use of uncertainty versus point values in the PRA-related decisionmaking i
process at the August 28-29, 1997
)
Subcommittee meeting.
Representatives of the NRC staff will j
participate, as appropriate.
i 9) 4:15 - 7:00 P.M.
Preparation of ACRS Reports (Open)
Discussion of proposed ACRS reports on:
9.1)
Action Plan to Improve the Senior
\\
Management Meeting Process 1
(JJB/PAB) 9.2)
Draft Regulatory Guide DG-1069, 2 of 6 12/04/97 18:36:05
em a *:q LIIFEaty.nrc.g:vy/Jci24Nagen%/XctM gen 9q_A CRS_444.html
}
s..
i Fira ProtGetien Progrcm for j
Parmansntly Shutdown and Decommissioning Nuclear Plants (DAP/AS)
{
9.3)
Site-Specific Safety Goals (TSK/NFD/RRS) 9.4)
Proposed Generic Letter and Regulatory Guide associated with Steam Generator Integrity
)
(RLS/NFD) i 9.5)
Reporting Reliability and Availability Information for Risk-Significant Systems and Equipment (tentative) (GA/MTM)
THURSDAY, SEPTEMBER 4,1997, CONFERENCE ROOM 2B3, TWO WHITE FLINT N40RTH, R0HC)CVIllJE, h1AJtYLABU) 10) 8:30 - 8:35 A.M.
Opening Remarks by the ACRS Chairman (open) (RLS/SD) 11) 8.35 - 10:15 A.M.
heeting with the NRC Executive Director for Operations (open) (RLS/MMI) 11.1)
Remarks by the ACR3 Chairman.
11.2)
Briefing by and discussions with the NRC Executive Director for Operations regarding items of mutual interest, including the following:
Human Performance Program Plan Research Program DOE Oversight / Direction Setting Issue #2 NRC staff procedures for providing the ACRS with J
generic letters, bulletins, j
and other regulatory guidance 1
issued on an expedited basis l
Development ef risk-informed regulation Role of ACRS in resolving technical differences between NRC staff and industry 10:15 - 10:30 A.M.
- BREAK ***
- 12) 10:30 - 11:00 A.M.
BWR Pressure Vessel Shell Weld Inspections (Open) (RLS/AS)
Report by the Subcommittee Chairman regarding issues discussed / raised at the August 26, 1997 Subcommittee meeting associated with BWR pressure vessel shell weld inspections.
Representatives of the NRC staff and nuclear industry will participate, as appropriate.
- 13) 11:00 - 11:15 A.M.
Subcommittee Report (Open) (TSK/PAB)
Report by the Subcommittee Chairman regarding matters discussed at the I
July 29-30, 1997 meeting of the Thermal Hydraulic Phenomena Subcommittee.
3cf6 12/04/97 18:36:05
444 ALR5 hdi Comm ttee Meetmg http:/Rxxy.nrc.g:v/ACRS/rrs t / agendas _ACRS/ Agenda _ACRS,_444.html J
f.'t R prc0gntetiv23 of tha NRC ctcff will participate, as appropriate.
- 14) 11:15 - 11:30 A.M.
Subcommittee Report (Open) (TSK/MME)
{
Report by the Subcommittee Chairman regarding matters discussed during the August 27, 1997 Regulatory Policies and Practices Subcommittee meeting associated with the defense-in-depth approach.
Representatives of the NRC staff will participate, as appropriate.
- 15) 11:30 - 12:00 Noon Future ACRS Activities (Open)
(RLS/JTL/SD)
Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.
12:00 - 1 00 P.M.
- LUNCH ***
16) 1:00 - 2:45 P.M.
Proposed Rule on Shutdown and Fuel Storage Pool Operations (Open) (DAP/MME) 16.1)
Remarks by the Subcommittee Chairman.
16.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed rule on shutdown and fuel storage pool operations.
Representatives of the nuclear industry will participate, as appropriate.
2:45 - 3:00 P.M.
- BREAK ***
17) 3:00 - 7:00 P.M.
Preparation of ACRS Reports (Open)
(5 : 00-5 :15 P.M. BREAK) 17.1)
Action Plan to Improve the Senior Management Meeting Process (JJB/PAB) 17.2)
Draft Regulatory Guide DG-1069, Fire Protection Program for Permanently Shutdown and Decommissioning Nuclear Plants (DAP/AS) 17.3)
Site-Specific Safety Goals (TSK/NFD/RRS) 17.4)
Proposed Generic Letter and Regulatory Guide associated with Steam Generator Integrity (RLS/NFD) 1 17.5)
Proposed Rule on Shutdown and l
Fuel Storage Pool Operations (DAP/MME) 17.6)
Reporting Reliability and Availability Information for Risk-Significant Systems and l
{
Equipment (tentative) (GA/MTM)
I FRIDAY, SEPTEMBER 5,1997, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MIARYLAND l
I i
4ef6 12/04/97 18:36:05
Nhittechs http://www.nrc.gsv/ACRS/rrs t / agendas _,ACRS/ Agenda _ACRS_444.html
,.l s'
18) 8:30 - 8:35 A.M.
Opening Remark 3 by th3 ACRS Chirman (open) (RLS/SD) 19) 8:35 - 10:30 A.M.
Improper Control Rod Movement During
(
Shutdown at Eion Unit 1, and Nonconservative Operations During Isolation of Recirculation Pump Seal Leak at Clinton (open) (JJB/NTM) 19.1)
Remarks by the Subcommittee Chairman.
19.2)
Briefing by and discussions with representatives of the NRC staff regarding improper control rod movement during shutdown at Zion Unit 1, nonconservative operations during isolation of recirculation pump seal leak at the Clinton Nuclear Power Plant, and human / organizational performance issues associated with these incidents.
Representatives of the nuclear industry will participate, as appropriate.
10:30 - 10:45 A.M.
- BREAK ***
- 20) 10:45 - 11:00 A.M.
Reconciliation of ACRS Comments and Recossnandations (Open) (RLS, et.al./
SD, et.al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports.
- 21) 11:00 - 11:30 A.M.
Report of the Planning and Procedures Subcosmiittee (Open/ Closed) (RLS/JTL)
Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, qualifications of candidates nominated for appointment to the ACRS, and organizational and personnel matters relating to the ACRS.
(Note: A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory Committee, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.)
11:30 - 12:30 P.M.
- LUNCM***
- 22) 12:30 - 3:30 P.M.
Preparation of ACRS Reports (Open)
Continue discussion of proposed ACRS reports on:
22.1)
Action Plan to Improve the Senior Management Metting Process (JJB/PAB) 22.2)
Draft Regulatory Guide DG-1069, Fire Protection Program for Permanently Shutdown and Decommissioning Nuclear Plants i
I (DAP/AS) 22.3)
Site-Specific Safety Goals (TSK/NFD/RRS) 5 cf 6 12/04/97 18:36:05
11ttp:///tcc.nrc.g:v/AccM201/agenib3_ACRS/ Agenda _ACRS_444.html
.. ', 'I *.'
22.4)
PropoOsd Ginaric Lettsr cnd Regulatory Guide associated with Steam Generator Integrity (RLS/NFD) l 22.5)
Proposed Rule on Shutdown and Puel Storage Pool Operations (DAP/MME) 22.6)
Reporting Reliability and
. Availability Information for Risk-Significant Systems and Equipment (tentative) (GA/MTM) 3:30 - 3:45 P.M.
- BREAK ***
23) 3:45 - 4:30 P.M.
Strategic Planning (0 pen) (RLS/JTL)
Discussion of items of significant importance to NRC, including rebaselining of the Committee activities for FY 1998, 24) 4:30 - 4:45 P.M.
Miscellaneous (0 pen) (RLS/JTL/SD)
Discussion of miscellaneous matters related to the conduct of Committee activities, and matters / specific issues that were not completed during previous meetings, as time and availability of information permit.
NOTE:
Presentation time should not exceed 50 percent of the total 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 to the ACRS - 35.
't I
i i
6 of 6 12/04/97 18:36:05
e APPENDIX V
'(
LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE
[ Note: Some documents listed below may have been provided or prepared for Committee use only. These documents must be reviewed prior to release to the public.)
MEETING HANDOUTS AGENDA DOCUMENTS ITEM NO.
1 Onenina Remarks by the ACRS Cnairman i
1.
Items of Interest, dated July 9-11,1997 2
:_ tins with the Director of the NRC Office of Norimer Reedor Raanlation (NRR) 3.
NRR Current issues, dated July 9,1997, presented by Samuel Collins, Director, NRR [Viewgraphs) 3 Accentance Criteria for Plant-Soecific Safety Goals and Derivino Lower-Tier Accantance Cnteria i
4.
Considerations for Site-Specific Derivation of Subsidiary Risk Acceptance Criteria, dated July 9,1997, presented by Rick Sherry, ACRS Senior Fellow [Viewgraphs) l 4
Pronosed Standard Review Plan Mian and Reanlatorv Guide for Risk-informed. Perfor-mance-Based Inservice insoection 5.
Perdue-Abramson Model: The Global Model of the Perdue-Abramson Method (undated), Risk-informed Inservice Inspection Programs 5
Meetina with NRC Commissioner McGaffiaan 6
Prooosed Final Modifistiens to 10 CFR Part 26. Fitnama-For-Duty Proaram Reauirements 6.
Selected Drug Testing issues, dated July 9,1997, presented by Loren L. Bush, NRR [Viewgraphs)
(
i
,. 1'.,,
i Appendix V 443rd ACRS Meeting 9
Halden Reactor Proiect 7.
OECD Halden Reactor Project, Brochure, undated [ Handout) 8.
Achievements of the Halden Project Programme in the 1994-1996 Period, dated february 1997 [ Handout) 9.
OECD Halden Reactor Project, dated July 10,1997, presented by J. Persensky, Leo Beltracchi, Harold Scott, and Erik Holinagel [Vewgraphs) 10.
Halden Reactor Project Briefing to ACRS, dated July 10,1997, presented by L.
Beltracchi, RES [Viewgraphs) ~
11.
Halden Reactor Project Briefing to ACRS, dated July 10,1997, Fuels and Materials, presented by H. Scott [Viewgraphs) 10 Use of RASCAL Code Durina incident Resaansa 12.
RASCAL Atmospheric Dispersion Models, undated, presented by J.V. Ramsdell, Jr.,
Pacific Northwest National Laboratory [Viewgraphs) 13.
ACRS Presentation on RASCAL, undated, presented by Frank Congel and James Ramsdell, Jr. [Viewgraphs) 1 11 Future ACRS Activities 14.
Future ACRS Activites -444th ACRS Meeting, September 3-5,1997 [ Handout #11-1) 12 Reconciliation of ACRS Comments and Recommend =+ians 15.
Reconciliation of ACRS Comments and Recommendations [ Handout #12.1]
15 NUREG/CR-8372. Recerninendia; ens for Prda" =i;c Raismic Havard Analvsis: Guidance on Uncertaintv and Use of Exoerts 1
16.
Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on l
Uncertainty and Use of Experts, dated July 11,1997, presented by Andrew J.
Murphy [Viewgraphs) 17.
Guidance on the Use of Experts, dated July 11,1997, presented by Robert J.
Budnitz, Future Resources Associates, Inc. and C. Allin Comell, CAC Co.
I
[Viewgraphs) l d
.i.k.,.
Appendix V
(
443rd ACRS Meeting 16 Reoort of the Plannina and Procedures Subcommitteo 18.
Final Draft Minutes of Planning and Procedures Subcommittee Meeting - July 9, 1997 [ Handout #16.1]
19.
Memorandum to A. Singh and Planning and Procedures Subcommittee from D. A.
Powers, ACRS Member, undated: Review of Regulatory Guide " Fire Protection Program for Permanently Shutdown and Decommissioning Nuclear Power Plants
[ Handout]
i
(
.' 3s. %*.,,
Appendix V g:
443rd ACRS Meeting MEETING NOTEBOOK CONTENTS I&B DOCUMENTS 2
Meetina with the Director of the NRC Office of N*ar Reactor Ramdatian (NRR) 1.
Table of Contents 2.
Proposed Schedule 3.
Status Report, dated July 9,1997 4.
Memorandum from John T. Larkins, Executwe Director, ACRS, to Samuel J. Collins, Director, NRR, dated June 17,1997: ACRS Meeting with the NRR Office Director 5.
Report from R. L. Seale, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated April 18,1997: Establishing a Benchmark on Risk during Low-Power and Shutdown Operations 6.
Letter from L. Joseph Callan, Executive Director for Operations (EDO), to R.L.
Seale, Chairman, ACRS, dated May 28,199: Establishing a Benchmark on Risk during Low-Power and Shutdown Operations 7.
Letter from L. Joseph Callan, Executive Director for Operations (EDO), to R.L.
Seale, Chairman, ACRS, dated June 6,1997: Establishing a Benchmark on Risk during Low-Power and Shutdown Operations 8.
Memorandum from John T. Larkins, Executive Director, ACRS, to L Joseph Callan, EDO, dated June 19,1997:
Establishing a Benchmark on Risk during Low-Power and Shutdown Operations 9.
Memorandum from Samuel J. Collins, Director, NRR, to Ashok C. Thadani, Director, RES, dated June 18,1997: Request for Assistance in Developing Guidance on Emergency Action Levels Applicable in the Shutdown Mode of Reactor Operation (User Need Memorandum) 10.
FAX from Dr. Dana Powers, to ACRS Members, undated: EDO Response to ACRS Shutdown Risk Letter 11.
ACRS Report to The Congress dated February 21,1997: Safety Research Program 12.
Letter from T.S. Kress, Chairman, ACRS, to L. Joseph Callan, EDO, dated December 13,1996: ACRS Review of Generic Letters, Bulletins, and Information Requests issued on an Expedited Basis 13.
Letter from L. Joseph Callan, EDO, to R. L. Seale, Chairman, ACRS, dated April 11, 1997: Review by the Advisory Committee on Reactor Safeguards of Generic Letters, Bulletins, and information Requests issued on an Expedited Basis 14.
Report from T. S. Kress, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated August 15, 1996: Risk-Informed, Performance-Based Regulation and Related t
Matters
- e :r
,o
\\
I Appendix V 443rd ACRS Meeting
~ 15.
Letter from J. M. Taylor, EDO, to T. S. Kress, Chairman, ACRS, dated September 6,1996: Risk-informed, Performance-Based Regulation and Related Matters 16.
Report from T. S. Kress, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated April 23,1996: Probabilistic Risk Assessment Framework, Pilot Applications and Next Steps to Expand the Use of PRA in the Regulatory Decision-Making Process
{
17.
Letter from S. Jackson, Chairman, NRC, to T. S. Kress, Chairman, ACRS, dated i
June 3,1996 18.
Memorandum to Hugh L. Thompson, Jr., Acting EDO, from John C. Hoyle, Secretary, NRC, dated January 22, 1997: Quarterly Status Update for the -
i Probabilistic Risk Assessment (PRA) Implementation Plan, including a Discussion j
of Four Emerging Policy lasues Associated with Risk-informed Performance-Based Regulation 3
Arg;gotance Criteria for Plant-Soecific Safety GM s and Derivina Lower-Tier Accentanco i
Cnteria 19.
Table of Contents 20.
Proposed Schedule 21.
Status Report, dated July 9,1997 22.
Memorandum from Rick Sherry, Senior ACRS Fellow, to ACRS Members, dated June 27,1997: Considerations for Plant-Specific Site-Specific Application of Safety Goals and Definition of Subsidiary Criteria 23.
Memorandum from Michael T. Markley, Senior ACRS Staff Engineer, to ACRS Members, dated June 23,1997: Comments on Analysis of Accident Consequences 24.
Questions to be Addressed at the ACRS Probabilistic Risk Assessment Subcommitti;e Meeting on July 7,1997 25.
Memorandum tom Dr. Ivan Catton, ACRS Consultant, to Dr. George Apostolakis, dated June 24,1997: Some Comments on Issue Lists of Sherry and Apostolakis 26.
Report from R. L. Seale, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated April 11,1997: Risk-Based Acceptance Criteria for Plant-Specific Application of Safety Goals 27.
Letter from J. M. Taylor, EDO, to T. S. Kress, Chairman, ACRS, dated December i
26,1996: Plant-Specific Application of Safety Goals 28.
Report from T. S. Kress, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated November 18,1996: Plant-Specific Application of Safety Goals 29.
Letter from J. M. Taylor, EDO, to T. S. Kress, Chairman, ACRS, dated September 6,1996: Risk-Informed, Performance-Based Regulation and Related Matters 30.
Report from T. S. Kress, Chairman, ACRS, to S. Jackson, Chairman, NRC, dated August 15, 1996: Risk-Informed, Performance-Based Regulation and Related Matters 31.
Policy Statements, dated August 1986: Power Plants - Safety Goals for the Operations of Nuclear Power Plants; Policy Statement: Republication 4
Prooosed Standard Review Plan Section and Reaulatorv Guide for Risk-Informed. Perfor-I mance-Based Inservice insoection
.s S,,
Appendix V 443rd ACRS Meeting 32.
Table of Contents 33.
Proposed Schedule 34.
Status Report, dated July 9,1997 35.
Memorandum from G. Holahan and B. Sheron, NRR, and W. Hodges and L Shao, RES, to J. T. Larkins, Executive Director, ACRS, dated June 3,1997: Transmittal of Predecisional Draft regulatory Guide DG-1063: "An Approach for Plant-Specific, Risk-informed Decision-making: Inservice inspection of Pipes," and Draft Standard Review Plan Chapter 3.9.8, " Standard Review Plan for the Review of Risk-Informed Inservice Inspection Applications"w/o attachment [Predecisional Information: Do Not release Without Prior Approval.]
36.
Report from R. L. Seale, Chairman, ACRS to S. Jackson, Chairman, NRC, dated March 17,1997: " Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation 37.
Letter from L. J. Callan, EDO, to R. L. Seale, Chairman, ACRS, dated April 25, 1997: Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation 5
Meetina with NRC Commissioner McGaffiaan 38.
Table of Contents 39.
Proposed Schedule 40.
Status Report, dated July 9,1997 41.
Commissioner McGaffigan's views on DSl#2,4,5,6,7,9,10,11,12,13,14,20, 21,22,23, and 24 42.
Comments by Individual ACRS Members Regarding Direction-Setting lasues, dated November 27,1996 43.
ACRS Report to The Congress on Nuclear Safety Research and Regulatory Reform, dated February 1997 6
Pronosed Final Modifications to 10 CFR Part 28. Fitnass-For-Duty Proaram Raouirements 44.
Table of Contents 45.
Proposed Schedule 46.
Status Report, dated July 9,1997 47.
Listing of Recommended Modifications to Proposed Revisions to 10 CFR Part 26, dated June 16,1997 9
Halden Reactor Proiact 48.
Table of Contents 49.
Proposed Schedule 50.
Status Report, dated July 10,1997 51.
Memorandum from Leo Beltracchi, RES, to Franklin D. Coffman, Jr., RES, dated i
November 1,1996: Trip Report on the One Hundred and Fourteenth Halden i
o
. f.s:..
Appendix V 443rd ACRS Meeting Program Group Meeting and Related Activities 52.
Memorandum from D. Powers, ACRS Member, to Planning and Procedures Subcommittee, undated: Halden Pro'ect i
53.
Memorandum from Leo Beltracchi, RES, to Jay Persensky Coffman, Jr., RES, dated July 11, 1997: Trip Report on the One Hundred and Fifteenth Halden Program Group Meeting 10 Use of RASCAL Code Durina ineMont Remnanse 54.
Table of Contents 55.
Presentation Schedule 56.
Project Status Report, dated July 10,1997 57.
Memorandum from R. Savio, Deputy Executive Director, ACRS, to F. J. Congel, AEOD, dated June 19,1997: ACRS Member D. Powers Concems Regarding Use of the RASCAL Code 58.
Memorandum from M. Markley, Senior ACRS Staff Engineer, to ACRS Members, dated June 23, 1997:
Comments on Analysis of Accident Consequences
[ Attachment is Predecisional Information: Do Not release Without Prior Approval.]
59.
E-Mail Message from D. Powers, ACRS Member, to P. Boehnert, Senior ACRS Staff Engineer, dated June 26,1997: ST Code 15 NUREG/CR-8372. Recommendations for Protet4listic Esmic Harard Analysis GnW=nce on Uncertainty and Use of Fmerts 60.
Table of Contents 55.
Proposed Schedule 56.
Status Report, dated July 11,1997
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