ML20140H353
| ML20140H353 | |
| Person / Time | |
|---|---|
| Issue date: | 02/03/1997 |
| From: | Kress T Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-3043, NUDOCS 9705130092 | |
| Download: ML20140H353 (39) | |
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TABLE OF CONTENTS i
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TES OF THE 437TH ACRS MEETING DECEMBER 5-7, 1996 Pace I. Chairman's Report (Open) 1 II. Proposed Standard Review Plan Sections and Regulatory Guides Associated with Risk-Informed, Performance-Based Reculation (Open) 1 III. NRC Research Procram on Instrumentation and Control Systems (Open) 3 IV. Plant Acino Research Procram (Open) 5 V. Human Performance Procram Pla_q (Open) 7 VI. Meetino with the NRC Commissioners (Open) 9 VII. NRC Emeroency Resconse Program (Open) 10 VIII. Executive Session (Open) 12 A.
Letters ACRS Review of Generic Letters, Fulletins, and Informa-Mon Recuests Issued on an Expedited Basis (Letter to James M. Taylor, Executive Director for Operations, NRC, f rom T. S. Kress, Chairman, ACRS, dated December 13, 1996)
ACRS Ouestione on Human Performance Procram Plan (Letter to James M.
Taylor, Executive Director for Operations, NRC, from T.S. Kress, Chairman, ACRS, dated December 3 0, 1996)
B.
Reconciliation of ACRS Comments and Recommen-dations C.
Report on the Meeting of the Planning and Proce-dures Subcommittee Held on December 3, 1996 (Open)
D.
Future Meeting Agenda
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APPENDICES 4
I.
Federal Register Notice l
II. Meeting Schedule and Outline III. Attendees l
IV. Future Agenda and Subcommittee Activities l
V. List of Documents Provided to the Committee VI. Staff Requirements Memorandum from the December 13, 1996, meeting with the Commission j
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MINUTES OF THE FOUR HUNDRED THIRTY-SEVENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS DECEMBER 5-7, 1996 ROCKVILLE, MARYLAND The 437th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on December 5-7, 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 i
attendance.
There were no written statements nor requests for time to make oral statements from members of the public regarding this meeting.
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. John Barton, Dr. Ivan Catton, Dr. Mario H.
Fontana. Dr. Don W.
- Miller, Dr. Dana A.
l Powers, and Dr. William J. Shack.
[For a list of other attendees, see Appendix III.)
W I.
CHAIRMAN'S REPORT (Open)
[ Note:
Dr. John T. Larkins was the Designated Federal Of ficial for this portion of the meeting.)
Dr. Thomas S.
Kress, Committee Chairman, convened the meeting at 8:30 a.m.
and reviewed the agenda.
He announced the recent reorganization of NRC and noted a speech by Chairman Jackson to a Nuclear Energy Agency Workshop on thermal hydraulics and neutronics code requirements.
II.
Pronosed Standard Review Plan Sections and Reculatorv Guides Associated with Risk-Informed. Performance-Based Reculation (open)
[ Note: Mr. M. Markley was the Designated Federal Of ficial for this portion of the meeting.)
Dr.
George Apostolakis, Chairman of the ACRS Subcommittee on Probabilistic Risk Assessment (PRA), introduced this topic to the Committee.
He noted that the PRA Subcommittee had met with the NRC staff and industry representatives on October 31 and November 1, 21, and 22, 1996.
He stated that all but one ACRS Member had
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477th ACRS. Meeting 2
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' December 5-7, 1996 attended the November 21-22, 1996, session, and noted that the Commission had granted ACRS and the NRC staff an extension in I
reporting on these matters.
He introduced Mr.
Gary Holahan,
- Director, Division of Safety Systems and Analysis, Office of Nuclear Reactor Regulation (NRR), to discuss staff activities since the last Subcommittee meeting.
i i
NRC Staff Presentation Mr. Holahan led the discussions for the NRC staff.
Messrs. Wayne Hodges, Director, Division of Systems. Technology, Of fice of Nuclear Regulatory Research (RES), and Mark Cunningham, Chief, Probabilis-tic Risk Analysis Branch, RES, provided supporting discussion.
Mr.
Holahan stated that he planned to discuss two issues: a proposed schedule for future ACRS meetings regarding proposed Standard i
Review Plan (SRP) sections and associated Regulatory Guides, and a policy issue raised by the NRC Office Directors during their review l
of these proposed documents.
Significant points made during the
' discussion included:
k o
The Office Directora had expressed concern that allowing l
increases in risk would permit plants to move closer to the e
Commission's Safety Goals, thereby increasing overall industry j
risk or creating the perception that the NRC was allowing plants to operate less safely.
The staff stated that they i
were developing a Commission options paper to address this issue and planned to forward the document to the' Commission 1
and ACRS in December 1996.
The staff requested a Committee review during the next ACRS meeting, February 5-8,
- 1997, The staff planned to provide revised SRP sections and Regula-e tory Guides for ACRS review by the end of January 1997.
They requested that a Subcommittee meeting be held February 20-21, 1997, to discuss these documents prior to issuance for public comment.
The secff stated that a letter from the Committee would be appropriate at the ACRS meeting on March 6-8, 1997.
Drs. Apostolakis and Kress questioned how a risk-informed environ-ment can exist if the program does not allow for increases in risk in some situations.
They reiterated the ACRS view, as stated in the ACRS report dated August 15, 1996, that it is the overall impact on risk that is important and that related changes should be handled as a package.
The staff stated that allowing increases in risk is a fundamental question which the Commission has not yet decided.
They stated that the Office Directors want to assure that any increases are approved in a controlled manner.
The staff stated that the problem lies, in part, in how measures of risk are defined.
They specifically noted the difficulty associated with defining what is a small or significant increase in risk.
They stated that the same problem applies to defining what constitutes
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I 437th kCRS Meeting 3
December 5-7, 1996 an adequate level of protection.
The staff stated that the Commission paper would offer several options and highlight the advantages and disadvantages of each in considering possible increases in risk.
Dr. Robert Seale asked if this policy issue affects the work being pursued in the pilot applications.
The staff stated that it does apply to the pilot plants and expressed concern that plants might move incrementally closer to the Safety Goals.
They added that it creates a dilemma over what to do about plants that already exceed l
the Safety Goal (i.e.,
whether to pursue backfits or other regulatory approaches) and how to implement the program in a manner that does not penalize certain classes of plants (i.e., BWR versus PWR).
Dr. Apostolakis noted that these concerns are further complicated by the time dependency of the " risk baseline" against which changes will be considered.
Dr. Kress expressed concern over the appearance of increasing risk.
The staff expressed the belief that the industry was safer than it was 15 years ago and was improving.
They stated that they wanted to increase public confidence. However, they acknowledged that the SRP and Regulatory Guide effort could be viewed as a reversal of that trend if changes do not emphasize that adequate health and safety is maintained or enhanced.
Dr.
Apostolakis summarized the discussions and verified the acceptability of proposed future meeting dates and planned attendance by ACRS Members.
He noted that the ACRS was meeting with the Commission on December 6,1996, to discuss items of mutual
- interest, including initiatives for risk-informed, performance-based regulation.
Conclusion The Committee plans to continue its review of these matters during future meetince.
t III. NRC Research Proaram on Instrumentation and Control Systems (Open)
(Note:
Mr.
P.
Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr. Don Miller, Chairman, Instrumentation and Control (I&C) Systems and Computers Subcommittee, introduced this topic.
He noted that, during the Subcommittee review of the issues associated with use of digital I&C systems, the Committee did not explicitly review RES research programs in this area.
Dr. Miller noted the outstanding i
issues of concern to the Committee cited in its June 6,
- 1996, I
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437th hCRS Meeting 4
D'cember 5-7, 1996 e
letter to the EDO and asked Mr. Frank Cof fman, Chief, Control, Instrumentation, and Human Factors Branch, RES, to address their status during his presentation.
Mr. Coffman indicated that he could discuss the one issue under his purview: the balancing of review between design process and assessment of the product.
RES Presentation Mr. Cof fman presented an overview of the RES activities on advanced I&C, noting the following goals for the research program:
Provide regulatory guidance and a technical basis for comput-o er-based I&C systems, including software quality, hardware qualification, and human-system interactions; Assess and develop methods for safety evaluations; and e
e Stimulate and collaborate in international research.
Mr.
Coffman discussed recent products from the I&C research
- program, current on-going projects, research in the planning stages, and possible future research projects.
During the above discussion, Mr. Jared Wermiel, NRR, noted that, while the Agency has not made a final decision on the need to publish a Regulatory Guide to address qualification of digital equipment for electromagnetic interference /radiofrequency interfer-ence conditions, it was likely to do so.
Dr. Seale noted a recent newscast reported that expected intense sunspot activity may deleteriously af fect personal computers.
Dr. Miller suggested that RES investigate this matter.
Mr. John Kramer, RES, committed to provide the Committee with a copy of a letter report that contains a literature search and information on overseas activities related to the topic of hybrid control rooms.
(Note: a copy of this report l
was provided to the ACRS staff.]
Mr. Coffman also noted that the i
National Academy of Sciences Report on the Phase 2 Study on Digital I&C is due to be issued in pre-print form to the Agency in mid-December, and a copy would be made available to the ACRS immediate-i ly upon receipt.
Dr. Miller asked a number of questions on his concern that RES appears to lack a coordinated strategic plan for I&C research.
Mr.
j Hodges offered to provide a matrix document that could serve as a basis for ensuring that all major issues of concern in this area j
are being or will be addressed by the I&C research program.
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Conclusion The Committee plans to continue its review of this matter during the discussion of the National Academy of Sciences / National
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437th ACRS Meeting 5
i December 5-7, 1996 l.
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Research Council Phase 2 study report on the use of digital I&C systems at a future meeting.
IV.. Plant Aoinc Research Procram (Open)
[ Note:
Mr. A.
Singh was the Designated Federal Official for this.
portion of..the meeting.]
Introduction i
i Dr.
Dana Powers, Acting Chairman of the Plant Aging Research Program Subcommittee, summarized the issues and noted that the purpose :of this session was to hear a presentation by the NRC staff regarding the ongoing and proposed research activities associated with plant aging.
He further stated that this briefing was for information only and no Committee report was required.
NRC Staff Presentation Mr. Mike Mayfield, Chief, Electrical, Materials, and Mechanical
. Engineering Branch, Division of Engineering Technology,
- RES, l
provided the background regarding the ongoing and proposed research activities associated with plant aging.
RES has ongoing research activities in areas of reactor pressure l
vessel integrity, embrittlement, environmentally assisted cracking, e
nondestructive examination (NDE), steam generator tube integrity, environmental qualification of electric cables, and degradation of mechanical components. RES has technical assistance contracts with various contractors to -perform these research activities.
Following is the summary of the project description of each of I
these activities.
Reactor Pressure Vessel Intecrity The objective of this project is to develop and experimentally validate the analysis methods needed to fully characterize the fracture behavior of heavy-section reactor pressure vessels and related components and structures under the full spectrum of loading and material' conditions. This will include the development of the material property data, and the appropriate test techniques and data analysis methods needed to perform pressure vessel integrity analyses.
The results of this research will be used by NRR to make safety decisions related to reactor pressure vessel
-(RPV) integrity for operating reactors and by RES and NRR staff in recommending revisions to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and to the American Society of Testing Materials test standards on fracture toughness of RPV materials.
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l 437th ACRS Meeting 6
D'ecember 5-7, 1996 Embrittlement Correlations The objectives of this project are to develop the equations for estimating irradiation embrittlement of RPV beltline
- steels, considering all pertinent material and environmental variables, and to develop correlations for estimating the recovery of upper shelf and transition temperatures resulting from thermal annealing.
The results of this project will be applied to operating plants and would be applicable to advanced reactors with similar materials and operating conditions.
The results also will be used to assess the need for further revisions to Regulatory Guide 1.99.
Environmentally Assisted Crackina The objectives of this project are to supply data and models for predicting environmental effects on fatigue; to supply data,
- models, and criteria for predicting component vulnerability to irradiation-assisted stress corrosion cracking; to establish criteria for predicting cracking of light-water reactor primary T
system components made of nickel alloys; to provide information on the consequences of post-weld heat treatment; and to assess 4
industry crack-growth models.
The results of this research will help NRC to assess licensee submittals concerning the residual life, inspection, repair, and replacement of aging reactors.
Source of Nondestructive Examination Material This project will provide a set of up to 18 irradiated and 18 unirradiated specimens, which will be made available for NDE at a separate testing facility.
The results will be used by outside testing groups to develop correlations to known toughness values.
This will provide greater reliability and confidence in the evaluation of toughness measurements and monitoring, as required in Regulatory Guide 1.99, Rev.
2, and in 10 CFR 50.
Steam Generator lube Lpteority The objective of this project is to develop models for predicting potential degradation
- modes, progression
- ratea, leak / rupture behavior, failure pressures, and leak rates for new, degraded, and repaired tubes under normal operating, accident.
and severe accident conditions, as well as to quantify the capability of inservice inspections (probability of detection, sizing accuracy).
The results will be used by NRR: a) for conducting independent integrity analyses, b) for predicting areas of future concern and taking proactive action, c) for validating claims related to inspection capability, d) in support of new rulemaking activities related to steam generator tube integrity, inspection, and maintenance, and e) for evaluating various proposals for implemen-ting the new performance-based rule and Regulatory Guide.
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437th CRS Meeting 7
December 5-7, 1996 Environmental Oualification of Electrical Cables The objectives of this project are i
e to obtain naturally aged cables from nuclear utilities and new cable samples from utilities and/or manufacturers to be used l
to evaluate methods of monitoring and testing the condition of cables; to finalize the review and evaluation of technical literature; e
e no develop a database for operational and test performance auta for safety-related cables.
1 This project was initiated in response to an NRR user need request and was developed to meet the needs identified in the NRR Equipment Qualification Task Action Plan.
Dearadation of Mechanical Components l
The objective of this project is to identify aging-related degradation mechanisms in motor-operated valves (MOV) and pumps, and then quantify them by testing the ef fect of the dominant aging-related degradation mechanism on the performance of MOVs and pumps.
NRR intends to use the results of this study to review (1) licensee assumptions regarding aging effects on MOV thrust / torque require-ments and output in their MOV periodic verification programs, and (2) deterministic and engineering aspects of pumps and valve performance degradation assumed in risk-informed inservice testing programs.
Conclusion This briefing was for information only.
No Committee action was required.
V.
Human Performance Program Plan (Open)
[ Note:
Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Robert Scale, Acting Chairman of the Human Factors Subcommit-tee, noted that on December 3, 1996, the Subcommittee heard staff responses to 18 questions raised by the ACRS after the September 20, 1996, Human Factors Subcommittee meeting.
He stated that the staff would elaborate on some of these questions.
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437th kCRS Meeting 8
December 5-7, 1996 l
Staff Presentation Dr.
Cecil Thomas,
- NRR, introduced the staff presentation by summarizing the status of the Human Factors Coordinating Committee and the Human Performance Program Plan (HPPP).
He explained how the Coordinating Committee developed and updated the HPPP using a formal framework and a top-down approach.
He noted that the Coordinating Committee was recently abolished since it duplicated the efforts of interoffice coordination meetings.
Dr.
Thomas stated that the activities of the Coordinating Committee would continue within the line organization.
In response to questions prepared earlier by the Committee, the staff provided the following information:
Mr. Coffman stated that the HPPP was not built on the concept of risk, due to the inability to equate human actions to a quantitative risk value.
Dr. Thomas presented a road map of the HPPP that began with data and ended with tools used to assess human performance at nuclear power plants.
He explained the uncertainties associ-ated with long-term planning.
Mr.
Coffman explained how the Coordinating Committee used perceived safety significance, immediacy, management direc-
)
tion, and regulatory needs to prioritize the HPPP items.
l Dr.
Dennis Serig, Nuclear Material Safety and Safeguards (NMSS), explained that material licensees have not applied the safety systems, redundancy, diversity, and defense-in-defense concepts used by utility licensees.
He noted that NMSS is waiting for Commission direction before continuing its human factors efforts.
Mr. Cof fman explained that consensus standards are endorsed by regulatory guides after the staff evaluates the experience base.
He noted that there is no guarantee of suf ficiency when using consensus standards, and that the scope of the standards should not exceed the scope of the evparience base.
Mr. Frank Collins, NRR, e"plained the process for verifying simulator fidelity, and e:.p ressed his opinion on how operators would respond to unexpecu.d plant indications.
Mr. Jack Rosenthal, Chief, Reactor Analysis Branch, Office for Analysis and Evaluation of Operational Data (AEOD),
mentioned several AEOD reports on human factors.
He explained the develop-ment of the human performance event database and presented analyses
417th ACRS Meeting 9
December 5-7, 1996 l
of the data.
Dr. Thomas described the human factors information system maintained by NRR.
Committee Discussion The Committee and the staff discussed how the panel of human factors experts developed the HPPP, the elements of the HPPP other than the modeling of human error, the need to document the spirit and motivation for the HPPP, and the lack of documentation of the considerations used in the priority-setting process.
They also discussed the use of the Institute of Nuclear Power Operations databases, how identified human factors concerns are addressed if there is an insufficient experience base, and the use of human performance event database analyses.
Conclusion The Committee issued a letter to the Executive Director for Operations dated December 30, 1996, on this matter.
The Committee decided to continue its discussion of a proposed report concerning this issue during the ACRS meeting on February 5-8, 1997.
VI.
Meetino with the NRC Commissioners (Open)
[ Note:
Mr.
S.
Duraiswamy was the Designated Federal Official for this portion of the meeting.)
The ACRS met with the NRC Commissioners on December 6, 1996, in the One White Flint North Building, Rockville, Maryland.
The NRC Commissioners were briefed by and held discussions with the Committee on the following topics:
Digital Instrumentation and Control Systems Office of Nuclear Regulatory Research Plan for Upgrading NRC e
Thermal-Hydraulic Codes Risk-Informed, Performance-Based Regulation and Related Matters e
Potential Use of IPE/IPEEE
[ Individual Plant Examina-tions/ Individual Plant Examinations for External Events]
Results to Compare the Risk of the Current Population of Plants with the Safety Goals e
Use of Safety Goals on a Plant-Specific Basis e
Use of RuleNet in the Regulatory Process
437th ACRS Meeting 10 December 5-7, 1996 Conclusion The December 13,
- 1996, Staff Requirements Memorandum (SRM) resulting from this meeting is attached as Appendix VI.
VII. NRC Emercency Response Procram (Open)
[ Note:
Dr. M.
El-Zeftawy was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Seale, Chairman of the Occupational and Environmental protec-tion Systems Subcommittee, stated that the purpose of this session was to hear presentations by AEOD regarding the NRC emergency response program and the Operations Center.
Dr.
Denwood Ross,
- AEOD, outlined the response roles for the licensees, the States, and the NRC for this program.
The licensee has the immediate action, and primary continuing responsibility for limiting the consequences of an accident.
The licensee recommends protective actions to State or local authorities.
The State and local authorities have the ultimate responsibility for ensuring the protection of the public from offsite consequences of an accident.
Licenses for the use of nuclear material are issued by NRC.
During an accident, NRC takes the lead in coordinating Federal technical oversight and support.
The NRC role is as follows:
e Monitor the situation to understand the problem and the licensee's response; e
Monitor the licensee's recommendations to ensure that appro-priate protective actions are provided to State and local authorities; e
Provide technical or logistic support to the licensee and to state and local authorities, as requested; e
Work with other Federal agencies to ensure that Federal technical activities are helpful and coordinated; and e
Take the Federal lead in providing technical information to other Federal, State, local, and international agencies, the Congress, the White House, and the public.
Mr. Frank Congel, AEOD, stated that AEOD maintains and implements the NRC Incident Response Center Program with the support of other
42i7th ACRS Meeting 11 December 5-7, 1996 headquarters and Regional Offices.
This program includes the receipt of data and reports for both emergency and nonemergency events from licensees, followed by an appropriate NRC response.
The response for the more serious emergencies is through an incident response organization that includes representatives from several headquarters offices and the affected Regional Office. The NRC response program also includes coordination with other Federal agencies, as well as State and local governments.
Dr. Richard Barrett, AEOD, stated that the new Operations Center at Two White Flint North began operating in May 1994.
The Operations Center provides the focal point for NRC communications with the Commission, licensees, State agencies, and other Federal agencies regarding the events that occur in the commercial nuclear sector.
The Operations Center is staffed with reactor system engineers trained to receive, evaluate, and respond to all types of events.
The Operations Center also features a state-of-the-art Operation Center Information Management system, which integrates voice,
- video, and data subsystems to provide timely and effective information flow during NRC's response to an incident.
In the event of an emergency at an NRC-licensed facility, the licensee places an emergency telephone call to the Operations Center immediately af ter notifying the appropriate State and local agencies. Emergencies are classified by licensees into one of the following levels in order of increasing severity:
Unusual Event - denotes a condition that does not represent an e
immediate threat to the public health Alert - indicates substantial actual or potential degradation e
in plant safety Site Area Emergency or General Emergency - indicates a major e
failure of one or more systems required for public safety or a potential for a major offsite radiological release The NRC response to an event may range from a routine follow-up to a complete activation of the regional Incident Response Center and headquarters Operations Center.
The NRC utilizes four formal modes for responding to events: Normal, Standby, Initial Activation, and Expanded Activation modes.
If the event threatens public health and safety, the NRC will enter the initial activation mode which requires promptly sending an NRC team from the cognizant Regional Office to the site to lead the NRC response.
During 1995, AEOD conducted an aggressive State Outreach Program designed to increase and improve NRC interaction with States during events and exercises.
The program also included an increased i
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4,27th ACRS Meeting 12 December 5-7, 1996 frequency of exercise participation consistent with the goal to exercise with each State on a 3-year cycle.
Conclusion This briefing was for information only.
No Committee action was required.
VIII.
EXECUTIVE SESSION (Open)
[ Note:
Dr. J. Larkins was the Designated Federal Of ficial for this portion of the meeting.]
A.
Reports, Letters and Memoranda ACRS Review of Generic Letters, Bulletins, and Informa-tion Recuests Issued on an Excedited Basis (Letter to James M. Taylor, Executive Director for Operations, NRC, f rom T.S. Kress, Chairman, ACRS, dated December 13, 1996)
ACRS Ouestions on Human Performance Procram Pl_a_n (Letter to James M.
Taylor, Executive Director for Operations, NRC, from T.S. Kress, Chairman, ACRS, dated December 30, 1996) l B.
Reconciliation of ACRS Comments and Recommendations
[ Note:
Mr.
S. Duraiswamy was the Designated Federal Official for this portior of the meeting.)
The Committee discussed the response from the NRC Executive Direct or for Operations (EDO) dated November 12, 1996, responding to ACRS comments and recommendations included in the ACRS report dated October 21,
- 1996, concerning the Thermal-Hydraulics Research Plan.
The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the NRC Executive Director for Operations dated November 20, 1996, responding to ACRS comments and recommendations included in the ACRS report dated October 22,
- 1996, l
concerning the capability of the SCDAP/RELAP code to l
predict temperatures and flows in steam generators under severe accident conditions.
In order to determine the acceptability of the' staff response, the Committee requested copies of the sensitiv-I
457th ACRS Meeting 13 December 5-7, 1996 l
ity analysis of the thermal-hydraulic code, which was described in the November 20, 1996, letter.
The Commit-l tee noted that this letter did not address the uncertain-ties of the models used for fission product deposition l
and transportation.
1 C.
Report on the Meeting of the Planning and Procedures Subcommittee (Open) 1 The Committee heard a report from Dr. Kress on the Plan-ning and Procedures Subcommittee meeting held on December 3,
1996.
The following items were discussed:
1)
ELECTION OF ACRS OFFICERS (Open)
A list of members who withdrew their names from consideration as ACRS officers was provided.
Elections were scheduled during this meeting.
Elected officers are:
Dr. Robert L.
Seale Chairman Dr. Dana A.
Powers Vice Chairman Dr. Thomas S.
Kress Member-at-Large J
2)
Conflict-of-Interest Procedures (Open)
)
Procedures have been drafted to ensure that members have a consistent policy covering conflict-of-interest requirements during meetings.
These j
procedures have been sent to the Office of General Counsel (OGC) for review.
Members are encouraged to comment.
RECOMMENDATION The Subcommittee recommended that members review these procedures and provide comments to the ACRS Executive Director by December 7, 1996.
3)
FEDERAL REGISTER NOTICE AND PRESS RELEASE TO SOLIC-IT CANDIDATES FOR APPOINTMENT TO THE ACRS (Open)
The closing date for applications from candidates for appointment to the ACRS has been postponed f rom December 31, 1996, to January 31, 1997.
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4)
COMMITTEE ROLE IN REVIEWING GENERIC LETTERS (Open) l l
4$7th ACRS Meeting 14 December 5-7, 1996 Certain safety-significant generic letters have been approved on an. exigent. basis without ACRS review.
The. Committee should determine its role in reviewing such letters.
The Memorandum of Under-standing (MOU) states that any deviation from the MOU should be mutually agreed to by the EDO and the ACRS Executive Director.
RECOMMENDATION The Subcommittee recommended that the ACRS staff prepare a draft letter from the ACRS Chairman to the EDO requesting that urgent generic letters be
'sent to the ACRS at the same time they are sent to the' Committee for the Review of. Generic Require-ments so the cognizant Subcommittee Chairman can determine whether the ACRS should review and com-ment on the letter.
i 5)
INTERNATIONAL ACTIVITIES (Open)
An e-mail message was received from Mr.
Shoji
-Yamada, Science and Technology Agency, Japan.
The Committee was asked to review the_ suggested dates, topics for discussion, and sites for a trip visit and indicate a preference which will be transmitted to Mr. Yamada.
RECOMMENDATION The Subcommittee recommended that the suggested topics for discussion and dates for a trip to Japan be discussed by the full Committee.
At the full Committee meeting, the Members chose October 20-24, 1997 as the preferred date and the advanced boiling water reactor at Niigata-ken as the preferred site to visit.
The preferred agenda items were:
risk-based regulation, fire modeling, steam explosions, steam generator operating experi-ence (focusing on failure mechanisms),
and high burn-up fuel (broadly based--not limited to reac-tivity insertion accidents).
6)
MEETING WITH CHAIRMAN JACKSON AND ANNOUNCEMENTS (open)
The Executive Director met with Chairman Jackson alone twice and together with Dr. Apostolakis once since the last ACRS meeting.
He briefed the Com-
. -. ~. -.. -. - ~. ~ ~
~.. _ -.
.(
,4)7th hCRS Meeting 15 December 5-7, 1996 mittee on these discussions as well as on recent announcements by Chairman Jackson regarding the direction of the Agency.
7)
TIMING OF RESPONSE TO STAFF REOUIREMENTS MEMORANDA ACTION ITEMS (Open)
A review has been made of SRMs over the past 36 months and it has been determined that the ACRS was not late in responding to these action items.
)
J RECOMMENDATION The Subcommittee recommended that all SRM require-l ments be tracked, including the name of the ACRS l
member and staff responsible for the response and the proposed date for Committee consideration of the response.
8)
CRITERIA TO EVALUATE ACRS CANDIDATES (Open)
The ACRS staff has been asked to draft criteria to determine the eligibility of candidates (principal-l_
ly ex-utility officials) for ACRS membership.
Mr.
J. Carroll has been asked to assist in this effort, which will also be coordinated with OGC.
l 9)
ASSESSMENT OF TECHNICAL EXPERTISE OF ACRS MEMBERS l
(Open) l The ACRS staff has been asked to provide a list of the areas of technical expertise of current ACRS members and an assessment of future needs of the Committee, based on current capabilities, future vacancies, and most importantly, the projected workload and topics for review, RECOMMENDATION ACRS should review and approve the procedures, prior to forwarding them to Dr. Morrison, RES.
10)
NUCLEAR SAFETY RESEARCH REVIEW COMMITTEE (NSRRC) l PARTICIPATION IIT ACRS MATTERS (Open) t It is anticipated that on occasion, NSRRC members l
will attend ACRS meetings or ACRS members will y
attend NSRRC meetings.
The procedures for such meetings have been drafted and will be sent to Dr.
Morrison as a proposal after ACRS comment.
i-
-\\
437th hCRS Meeting 16 December 5-7, 1996 RECOMMENDATION ACRS members should review and comment on the final i-draft procedures.
11)
MEMBERS ISSUES Dr. Seale requested ACRS approval for travel to France to participate in a review of recent Phebus experiments.
t RECOMMENDATION l
The Subcommittee recommended approval of the trip and the full Committee approved it.
f D.
Future Meetina Acenda j
Appendix IV summarizes the proposed items endorsed by the Committee for the 438th ACRS Meeting, February 6-8, 1996.
Desion-Bases Verification - The Committee will hear i
presentations by and hold discussions with representa-tives of the NRC staff and of,the industry regarding the acceptance criteria to be used by the staff in judging l
the adequacy of the design-bases information provided by the licensees in response to the 10 CFR 50.54 (f) letter 4
issued to all licensees in October 1996.
AEOD Scent Fuel Pool Studv - The Committee will hear presentations by and hold discussions with representa-tives of AEOD regarding the results of the study per-formed by AEOD on the adequacy of -spent fuel pool designs.
Representatives of the nuclear industry will participate, as appropriate.
Subcommittee Reoort - The Committee will hear a report by the Chairman of the Thermal Hydraulic Phenomena Subcom-mittee regarding matters discussed during the December 18-19, 1996, Subcommittee meeting, and comments on the future scope and direction of the Subcommittee's review of the Westinghouse AP600 Test and Analysis Program.
Shutdown Ocerations Risk - The Committee will hear presentations by and hold discussions with representa-tives of the NRC staff regarding issues associated with shutdown operations risk. Representatives of the nuclear industry will participate, as appropriate.
g
. 437th ACRS Meeting 17 December 5-7, 1996 S_ubcommittee Report - The Committee will hear a report by the Chairman of the Instrumentation and Control Systems and Computers Subcommittee regarding the ACRS review of the National Academy of Sciences / National Research Council Phase 2 study on digital instrumentation and control systems.
l B_isk-Informed, Performance-Based Reculation and Related Matters - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed Standard Review Plan Sections and Regulatory Guides for risk-informed, performance-based regulation, and related matters.
The 437th ACRS meeting was adjourned at 1:45 p.m.
on Saturday, December 7, 1996.
r_
l APPENDIX I Federal Regimer / Vel. 61, No. 225 / Wednendey, November. 20,.1996 / Notices 59119 i
Desuments to this pseemeding ssopm420 pm.:Mont Ashw Ausserch misen of which would constitute e s
see evadsbis der inspecdon at the anyum (OpsahThe hw== will ciserly unwarrantedinvasion of pmonal i
{
cammimampisjughuc Document Raam, k"'pmsenssiaan by and hold pe9ecy.
'#*h "NOps. TI
]
6e Gelman DeGdies, also 1.Serest, sec i
NW., W DC, missS:and at th*
ressoch aevismw
'cammense how passenmuons by NElmaal Decament Room at plant asius and hold d"=d-with j
the Onoma Camely LReary, Raissemos asynsumassives of 4 emelser ladustry supressamoves of the NRC sialf Util er#cipets,ma saganitag the mediScenoes to the NRC
{
Department,101 Washington Street, P
- Numan Russyncy Rasponse 4:1g(Open)-The Osamitase 2A0 pm448 p.ma Ascene tion ofACRS 345 j
has River, NJ 08753.
l lesund in hackvuls, Maryland,'am hear pressnestines by and hand Commener and Ascounseendations
]
Hsvamber 14, tees.
A===d-with supuessnestives of ties (OpushbCammittee will discuss E sesRreyeding egning and mopoases been the NRC Executive i
per the Atmanic Salsey and Mommsing esGwithms essestsend with the IMeesear her (EDO) to g,gg, M aman Ferdsnaaman Pn y o n Plan.
esmuments m===dehns S.Pand Bauwerk,IE, Espsessmentives of the ancisar ladustry tachaded la sonnet ACRS reports.
Candrussa, AdenhuisseePsoJus(pr.
wtB partlpipses, as appeuprism, laciuding the EDO response to the FR Dec. ee-sps74 FGod 11-10-es: ads anal 888Pm-Fds paaptopamedan sfAQtS Outshbr 21, teos Acts report on EsperarlOpenbThe Causalltse wul Nnmal;; ^_. % Raamarch Plan.
ename sees m**
discuss peoposed Acts apara em 3 ss pm4ds 'pm.: Election ofOfficers for l
amasses aussidsmed during this sesstener
.CY 1897 (Opes)-The Comunittee will j;
It many also discussa psoposed AGS.
enact'Gainman and Vlas. Chairman for Advloory Casasniese est Reacter separt to Omeyes em the NRC Sadsty the Acts and Member et-1.ary for the Sdegiserde;Moseng Nesse a===ch Payan.
Phm=Ime andJareandunes h wetw.
sm a Fas pmaheWn ofAGS y,gg,I' % g'gggg iOpenhN Canunitise will la anxertiance with the of l
Sections 29 and 182b. of Atomic 880e m.-e2s s m a Asmaris by the ammtinus is ds==aawn of proposed A cts G ehoism(
)--no Acts AGts reports on matter, considered Baergy Act (42 U.S.C. 3039,2232b), the i
Chainnas willmaks rumarks during this mestias It may also ducuss
{
Ad'I88'I ommines 8" Rasc' tor suprding conduct e
ACRS mport to Congress on C
i Saanguards willhold a meeting en ads am-ed5 sma MapamWon for the Safety Rasensch Program i
December 5-7,1996,in Conference wah theNRC'h-h"--(Open)-
Roesa T-153,11545 Rockville Pike, no Comediese will discuss the Seemrday, December 7,19e6 Rackville,bdaryland.11ne date of this followleg iteses der sesoting with the eso em,3sso pm.:pysperation of ACRS N RC h== " d " =e Aspers (OpenhN Committa will was previously published in
{
hF Register on Monday,
- Digital lastrummensthan and control emotinue its discussion of proposed 8 oterm-ADt3 mpans ce sanners coneidered F
Nevesnber 27* 1995 (60 FR 58393)'
e OlBee of Nuclamr story a-- ch during this meeting. h may also discuss Tbreday,Documsber 5,iggs Plan int Upgneding NstC
-Hydraulic a propaned ACRS soport to Coopees on Codes.
she NRC Saisty itsesarch Program 8Jeam44 ssma aby Asmarhr bythe e Risk.lafonned.Pr/bnnanco Bened.
2:30p.s.,3Jo paa Spessgic Plannhg Acts Chahman (
}-The ACRS Regulatlas and RaleM Matters (Open) -The Comunittee will continue Qiairman wulanske opealagremarks e Feesatial Uso d IPh/IPEEE Results to its discussion of itsens of signiScant ragsding oseduct of me masting and Gesaparo the Risk W the Cuneet P=g=&h importanos to NRC. including samment brie 0y reguding temas of of Plant with ti.e Salsey Goals. '
robeselining of the Comrenn oeuvitin survoet interest. During tids ases6ee,she a, Use of Seisty Goals on a Plast-SpeciSc garyy stet.
Commitase wul discuss paiacities for Resis.
l
-" of Acts soports e Use of RULENETin the Regulatory Precedures for the conduct of and ads om.-s#W amaproposed Sansdord hecues partici tion la ACRS meetings were EswaswPlan fSAP)$sceans and
- 20 sa-2120 ama Adssting wnh she NRC ha in se Federal Register on tory Guidor Asesedoesd with Adsk.
Camrdasionen, Cas===h== s ober 1 1996 (61 F1t 51310). In G88J rence Room, One lerhas FIJnf North acuerdance whh eene Wures, oral h
In
. 7 f,-
-Sased.". ' ^"
(Open)-N Cansduse will bear (OpenHThe Conunittes wHl mat whh or written statements may be pro ented tbs NRC Casamissioners to ducess the 3
E" tattoos by and hold discussions an,m atthe NnC eat mensa identined abom.
by members of the public, electronic i
supeding propoemd sRP n=*===d
- 3as em-2sss sma Phsum Acts recortlings will be permitted only guides W with risk.
Asafrities (Open)-he Commaittee will during the open portions of the meeting, ha
' ' regulation.
discuss Wt6ces of the and questions may be asked only by and mise [m"Eters Planaias and Procedures 8=n====h members of the Committee,its 1
aspressantives of the nuclear indusey 8Q8""g' g consuhants, and staff. Persons de< iring to make oral statements should notify I280 **.-!JJ8,7m : AstC Ansserch
,,,k,,,h,,,, p,esday l
wu] participate,as appropriese m
Mr. Sean Duralswamy, Chief. Nuclear
. Aspart of the Ffensdre Mayum an '= and Canenf
.andprecedures se6anammasetOpen/
Reactors Branch, at least Sve days 3)shm8 (OPsehne Camsdtta will Gessd)-N Commalans wul hear a before the moedag, if possible, so that hear pmanauens by sad hold.
separt of the Flamains and Procedurm appropriate arrangements can be made 3.
. discussions with re, ofthe paa==m on menare related to the to allow the -sy time during the i
E sentmensag the esgotas and senduct of AQts business,and meeting for such statements. Use of still, I, d pesonnelmarum
,and o
eras d
)
instrunwn d cost N
I j
Representedves of the nuclear ladustry of this sesslan be adosed to wul parecipais, as approprieta.
AO esgudassamar Epenommet "l*chd portions es mating as I
asanan that relats solely to the lamanal determined by the Chairman.
personant rules and precoces of this Information regarding the tirne to be set f
Advisory Casamittee,and manen the eside for this purpose may be obtained j
i E
i 59130 FedeontRegister / Vol. 61, No. 225 / Wednesday., Neember 20,19e8 / Notices j
by contacung the casf.f the Naclear 37082.Wahington,DC20e2-8328. A POR FWDER BronnunON 00Nfact:Mr.
J Reor. ors Branch prior ta the
. In. copy of the daru==ne is also available John W. Lubinski, Mail Stop '!WFN s-viewof the posaitsutty that the ila for '-
^'m and/or copying in the B, DIvisteen ofIndustrial and Medical j
, folr AQts mesdags may be adjusted by NRC P'uhuc Document Room. 2120 L Nuclear Safety, OlBee of Nuclear i l the Chairman as necesenry to decihtate Street NW, Washington, DC 20686-MaterialAalstyand f
. si.,U.S.
I the conduct of the meetists, 0001.
Nuclear =7_ _ y emn-w,
)'
planning to attend should with ponMtronasanoescmwracT Mr*
W' 7. DC 20585.* Telephone-the Chief of the Nuclear Reactors Brancf1 m is 7est if such nocheduhng would resultin John W. Lubinald, Mail Stop TWFN S. mmamurm.
- 18. Division ofIndustrial and u.as.a sponstanom N NRC-major inconvenience.
Nuclear Saisty Osce dNuclear has NUREG-1550," Standard in accordance with Subsection 10(d) y,g,g,3 g g 3,g,g
,g,g,g, Plan for Apphcodcas for Sealed j
P.L.92-463, I hat s determined that it is Nuclear Regulesey em Sauros and Devios Evaluations and
-'y to close portions of this
,-- DC 20685. Telephone Registrations,' to provide the reviewer meeting noted above to discuss matters 301-415-78a8'
. nf a request for a osaled souxe or device i
that nlate solely to the lasernal selsey evaluatinerwith the inforenation personnel rules and practices of this mamsuurm sensesanom On June and materialsneasseery to make a j
Advisory Committee per 5 U.S.C.
20,1985, the ei==was appresed the d ame=innene that the product is r
552b(c)(2), and to discuss matters the Irmatim of a woridag group===M"f le for licensing purpooss. It
. release of which would cocatitute a
.of4 a ne b A yeo m at the reviewer with a listing of l
clearly unwarranted inveelan op Dates and Irasa the Nuclear MO--i the licable regulations and industry
[c-and general 1], Mow, r=== wen to evaluate stan
, policies afiscting evaluation personal privacy per 5 U.Sc 552b(c)(6).
and licensees --
ior.
and on, certain ad=ial=*>stin Further information sogarding topics I
to be discussed, whether the meetina devices-to be followed, and of this notias is to inform on how to perform the has been cancelled or reacheduled, tb j,
Qiairman's ruling on requests for the the that the Snel repost of the evaluation and write the registration 4
W G88uP,that was completed and certiScate. Applicants for esaled source opportunity to prnent oral statensets i
and the time allotted therefor con be Blad in a mesnesandum dated July 2, or devios safety evaluations may find j
obtained by contacting Mr. Sam 19es,is being issued as NUREG-1551, the daan===' useful in preparing their Qaief, Nuclear Reactors
" Final ofthe N lications. 'the standard review plan Duraiswamy, hone 301/415-7364),
Branch (telep State W Group to E be seriand periodicaUy, as between 7;30 A.M. and 4:15 P.M. EST.
Control and Accountability.of finen==d aprqwists, to area =modate comunents j
ACRS meeting noticas, meeting Devim." This report is being made and to reflect newinformation and 1
4 transcripts, and letter reports are now. available to laterested members of the experience.N document is being.
j available on FedWorld trom the "NRC Public.
made evallable to interested members of j
MAIN MENU." Direct Dial Access Desed at Rockettle.:.:,*- ' this 15th day the public.
t number to FedWorld is (e00) 303-9672 of November, tsee.
Dated at Rockville. Maryland, this 14 day i'
or Ap.fedworld. '!hese documents and For the Nuciser Regulatory e-=ta-sam of November,1986.
i the meeting agenda are also evallable for Donald A.Casi, For the Nuclear Regulatory r==i=1on.
downloading or nyiewing on the armesor, Dvisise of bedesetal and Modical Demeld A.Casi, internet at htip /www. arc. gov /
Nuciser Safety. Offlee ofNuciserMessrsal Director;&venon ofindustrief andmdical 1
j ACRSACNW.
So/styandSofgruards Nucisar Sefury, Office ofNucisar maorial l
Deted: November 14,1996.
[FR Doc. 98-29870 Filed 11-19-46; e:46 een) Sefuryendsefiguards i
j Andrew L Bates, animum cost senswes.,
(FR Dor. 96-29871 Filed 11-16-es; a:45 aml f1 Advisory CoaurijnseMnegament Officer.
'f IFR Doc. 96-20049 Filed 11-16-es; SAS aml Standard Review Plan for Seeted j
mums come reso.*S-*
Source end Devios Evaluetons POSTAL MATE CORANSSION e
1 l
Aasect: Nuclear Regulatory l0nier No.1130; Deshet No. A97-4]
Final Report of the NRC. Agreement Comminalaa
'i !
State Worldng Group To Evaluego Cuyama, CA93214 W, blo0owen, Control and Acoountabitty of Woonced.Acnom Nodce davauaMty.
Poutionerk Negos and Order Devlees
'[.
suaseARY:N U.S. Nuclear Regulatory Un U
C.
Assocy: Nuclear Regulatory Counmi== ion is===anndng the l
404M(5)
Co*P etion and availabili ofNUREG-reunmission.
,l 1550," Standard Review P for Issued Noveenbar 14, toes.
Acmose:Notics of availability.
Applications for Sealed Srnuce and Befuse %==t=ionero: Edwerd I. Gleiman, r
- l suessany
- The U.S. Nuclear Regulatory Device Bualuations and M 'S-Chalnean; M. Edward Quick. Jr., Yks-
- I Commission is announcing the anneensen Copies of NUREG-1550 f,Gemy W. Haley, WR " Trey" completion and availability of NUREG-anay be obtained by writing to th*
Docket Number: A97-4.
1551," Final Report of the NRC-Superintendent of Documents, U.S.
Name of A5ected Post OEce:
Agreement State Working Group to Government Pdating OfBee, P.O. Box Cuyama, California 93214.
I Evaluate Control and Accountability of 37082, Washington, DC 20402-4324. A Hame(s) of Poudoner(s):J. McGowan.
Licensed Devices."
copy of the document is also available Type of Determination: Closing.
,[
Acontsets: Copies of NUREG-1551 for inspection and/m copying in the Date of Filing of Appeal Papers; may be obtained by writing to the NRC Public Document Room,2120 L Novenh=r 8,1996.
4 Superintendent of Documents U.S.
Strost NW, Washington, DC,20555-Categories ofIssues Apparently Covernment Printing OfBee, P.O. Box 0001.
Raised.
i e
m w--
T
'-7
APPENDIX II p ue,.q'g
- /
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION p
y I
ADVISORY COMMITTEE ON. REACTOR SAFEGUAROS g
WASHINGTON, D. C. 20006 REVISED Deceanbar 3,1996 SCEEDULE AND OUTLINE FOR DISCUSSION i
437th ACRS MEETING DECEMEER 5-7, 1996 I'
TEURSDAY, DECEMBER 5, 1996, CONFERENCE ROOM 2E3, TWO MEITE FLINT NORTH, ROCKVILLE, MARYLAND s
i 1) 8:30 -
8:
A.M.
Onenino Remarks by the ACRS chairman (Open)
I 1.1)
Opening Statement (TSK/SD) i 1.2)
Items of current interest
{
(TSK/JTL/SD) l 1.3)
Priorities for preparation of ACRS reports (TSK/SD) 2)
8:N -
9:N A.M.
Precaration for Meetino with the NRC j
Commissioners (Open) (TSK, et.al./SD, et.al.)
i Discussion of the following items for j
meeting with the NRC Commissioners:
2.1)
Digital Instrumentation and Control l
Systems (DWM/MTM) 2.2)
Office of Nuclear Regulatory Research i
Plan for Upgrading Thermal Hydraulic Codes (IC/PAB) 2.3)
Risk-Informed, Performance-Based Regulation and Related Matters (GA/MTM)
]
2.4)
Potential Use of IPE/IPEEE Results j
to Compare the Risk of the Current Population of Plants with the safety Goals (TSK/NFD) 2.5)
Use of Safety Goals on a Plant-Specific Basis (TSK/NFD) 2.6)
Use of RuleNet in the Regulatory i
3 Process (WJS/AS) 1 9:.?S - 9: 3 7 9. H.
M'M 3) 9:N-
~
A.M.
Pronosed Standard Review Plan (SRP)
(10:30 - 10:44 EREAK)
Sections and Reculatorv Guides
.2 o o
Associated with Risk-Informed, Performance-Based Reculation (Open)
(GA/MTM) 3.1)
Remarks by the Subcommittee Chairman j
D
[
((
[
2 e
)
3.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed SRP Sections and regulatory guides associated with risk-informed, performance-based regulation and related matters Representatives of the nuclear industry will participate, as appropriate.
ji.,2,_ 11 : 30 P. g.
B R EAK 4) 11:30 -
1:00 P.M.
NRC Research Procram on Instrumentation and Control Systems (Open) (DWM/PAB) 4.1)
Remarks by the Subcommittee Chairman 4.2)
Briefing by and discussions with representatives of the NRC staff regarding the ongoing and proposed research activities in the area of instrumentation and control systems Representatives of the nuclear industry will participate, as appropriate.
3 1:00 -
1:45 P.M.
LUNCH 5) 1:45 -
3:h P.M.
Plant Acino Research Procram (Open)
(DAP/AS) 5.1)
Remarks by the Acting Subcommittee Chairman 5.2)
Briefing by and discussions with representatives of the NRC staff regarding the ongoing and proposed research activities associated with plant aging Representatives of the nuclear industry will participate, as appropriate.
N -
3:45 P.M.
3:
BREAK 6) 3:45 -
5: hhp.M.
Human Performance Procram Plan (Open)
(GA/RLS/NFD) 6.1)
Remarks by the Subcommittee Chairman /
Acting Subcommittee Chairman
1 i
3 6.2)
Briefing by and discussions with representatives of the NRC staff regarding ongoing and proposed i
activities associated with the NRC fiuman Performance Program Plan Representatives of the nuclear' industry will
\\ participate,asappropriate.
l 27 47 5:N -
5:M P.M.
BREAK 7) 5 :$k -
bhhP.M.
Prenaration of ACRS Recorts (Open)
Discussion of proposed ACRS reports on:
7.1)
NRC Research Program on Instrumenta-tion and Control Systems (Tentative)
(DWM/PAB) 7.2)
NRC Research Program on Plant Aging (Tentative) (DAP/AS) 7.3)
[]v a, Pedo rmvee Pin FRIDAY, DECEMBER 6, 1996, CONFERENCE ROOM 2B3, TWO MEITE FLINT NORTH, ROCKVILLE, MARYLAND j
8) 8:30 -
8:35 A.M.
Ooenina Remarks by the ACRS chairman (Open)
(TSK/SD) 9)
8:35 -
9:15 A.M.
Brecaration for Meetina with the NRC Commissioners (continued) (Open)
SK, Se e 23.,,,
np et. ai,. /SD, et.al.)
Discus ion of the following i ms for meeting ith the NRC Commis oners:
9.1)
Di tal Instrument ion and Control Syst s (DWM/MTM 9.2)
Office f Nucl r Regulatory Research Plan for ding Thermal Hydraulic Codes (IC
)
9.3)
Risk-Info Performance-Based Regulat on an Related Matters (GA/
)
9.4)
Pot tial Use of E/IPEEE Results t
Compare the Risk f the current opulation of Plants th the Safety Goals (TSK/NFD) 9.
Use of Safety Goals on a lant-Specific Basis (TSK/NFD)
a J
e 4
l 9.6)
Use of RuleNet in the Regulatory
{
Process (WJS/AS) 9:15 -
9:3dA.M.
BREAK h-11:hdA.M.
{
- 10) 9:
Meetino with the NRC Commissioners.
Commissioners' Conference Room. One White Flint North (Open) l Meeting with the NRC Commissioners to discuss the matters identified under 2
i Item 9
)
i at 40 11: De - 11: P5 A.M.
BREAK l
yo il:lf 7.1)
- 1. 35 - 11:45 A.M.
Future ACRS Activities (Open) (TSK/SD) j Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings j
?
.2) 44:15 12.15 F.M.
r Recort of the Plannino and Procedures l
Subcommittee (Open/ Closed) (TSK/JTL)
Report of the Planning and Procedures l
Subcommittee on matters related to the conduct of ACRS business, and organizational and personnel matters p,g gj g relating to the ACRS l
sy y g:ss 9:Wo n.H.
i (Note:
A portion of this session may j
be closed to discuss organizational and r
personnel matters that relate solely to the
]
internal personnel rules and practices of this Advisory Committee, and matters the release of which would constitute a clearly
^
unwarranted invasion of personal privacy.)
12:15 -
1:30 P.M.
LUNCE 4
2 4
b it
1 1
5 1
hhabP.M.
13) 1:30 NRC Emeroency Resoonse Procram (Open)
(RLS/MME) 13.1)
Remarks by the Subcommittee Chairman ll 13.2)
Briefing by and discussion with representatives of the NRC staff l
regarding modifications to the NRC Emergency Response Program j
3: o 1
-3 :20 P. H,
3EEAd I
14) 2:t5 3.00 7.M.
Reconciliation of ACRS Comments and i
s 2[L 7s 3r 3:ss A. M.
Recommendations (Open) (TSK, et.al./
SD, et.al.)
Discussion of the responses from the NRC 4
i Executive ~ Director for Operations to comments and recommendations included in J
recent ACRS reports 4
l l
Election of Officers for CY 1997 (Open)-
' ^^
' ' ^ * "
Po6Tp.o s s va esly (TSK/JTL)
Election of Chairman and Vice-Chairman
+
for the ACRS and Member-at-Large for the Planning and Procedures Subcommittee t
3:30 -
3:45 P.M.
BREAK
)
3:Lo S: Yo 16) 31e6 -
he6 P.M.
Precaration of ACRS Recorts (Open)
' 5 : 3 0 4 9 ?. Z. ~~ E?_".)
Discussion of proposed ACRS reports on:
16.1)
Human Performance Program Plan (GA/RLS/NFD) 16.2)
NRC Research Program on Plant Aging (Tentative) (DAP/AS) 16.3)
NRC Research Program on Instrumenta-tion and Control Systems (Tentative) j (DWM/PAB) 16.4)
Annual ACRS Report to Congress on NRC Safety Research Program (tentative)
(RLS/MME) i SATURDAY, DEC m ER 7, 1996, CONF #8 NCE ENw 2B3 TWO WHITE FLINT NORTE.
I ROCKVILLE. MARYL..ND g: w q : 40 ge.
See n m nu-17)
P DC - 12:30 P.M.
Preparation of ACRS Renorts (Open)
~
8 (10:30 2 10:45 A.M. BREAK)
Continue discussion of proposed ACRS reports listed under Item 16.
s
6 Mr
- 18) 12:30 -
1:30 P.M.
Stratecie Plannine (Open) (TSK/JTL)
Discussion of items of significant importance to NRC, including rebaselining of the Committee activities for FY 1997.
EQTE:
e Presentation time should not exceed 50 percent of the total I
time allocated for a specific item.
The remaining 50 percent of the time is reserved for discussion.
e Number of copies of the presentation materials to be provided to the ACRS - 35.
1
.. - ~ ~.-......-.
I-l APPENDIX III:
MEETING ATTENDEES 437TH ACRS MEETING DECEMBER 5-7, 1997 l
l l-NRC STAFF C. Antones
B. Boger NRR J.
l-F. Collins NRR S. Dinsmore NRR R. Echenrode NRR i
N. Eisenberg NMSS C.
Fairbanks RES J. Giitter AEOD B. Gleaues RES E. Hackett RES W. Hodges RES R.
Isasia NRR i
c D. Jackson RES J. Jackson-RES T. Jackson RES J.
Kramer RES P. Madden NRR G. Marcus NRR J. Mitchell OEDO A. Murphy RES J. Muscara RES G.
Parry-NRR j
J. Persebskt RES C. Regan NRR M'.
Rubin NRR S.
Salicup AEOD J. Strosnider NRR C. Thomas NRR M. Vagins RES J. Vora RES J. Wechtel RES
.G. Weldenhamer RES i
J. Wermiel NRR
)
D. Wessman NRR i
l
- ~ -... -. -. - -.... - -
i a
Appendix III 2
437th ACRS Meeting j
ATTENDEES FROM OTurn AGENCIES AND GENERAL PUBLIC J.
Conto TEPCO S. Floyd NEI
.J.
Gorford NUS-LLS K. Green NUS Information Services R. Huston NEI P. LaPlante CNWRA S. Mixen NUS/CIS R. Simard NEI M. Strani SCIENTECH T.
Sutler Bechtel J. Trotler Polestar Applied Technology P. Vergus GE
i i
1 W
APPENDIX IV:
FUTURE AGENDA The Committee agreed to consider the following during the 437TH ACRS Meeting, December 5-7, 1997:
THURSDAY, DECEMBER 5, 1997 1) 8:45 A.M. - 10:45 A.M.:Procosed Standard Review Plan (SRP) S-ections and Reculatory Guides Associated with Risk-Informed, Performance-Based Reculation (Open) - The Committee will hear presentations by and hold discussions with repre-3 sentatives of the NRC staff regarding the proposed SRP i
Sections and regulatory guides associated with risk-informed, performance-based regulation, and related matters.
i 2) 11:00 A.M.
12:30 P.M.:
NRC Research Procram on j
Instrumentation and Control Systems (Open) - The Committee will hear presentations by and hold discussions with i
representatives of the NRC staff regarding the ongoing and proposed research activities in the area of instrumentation 4
and control systems.
h 3) 1:30 P.M.
- 3:30 P.M.: Plant Aoino Research Procram (Open) -
The Committee will hear presentations by and hold discussions i
with representatives of the NRC staff regarding the ongoing and proposed research activities associated with plant aging.
l 4) 3:45 P.M.
- 5:15 P.M.: Human Performance Procram Plan (Ocen)
The Committee will hear presentations by and hold discussions 1
l with representatives of the NRC staff regarding ongoing and i
proposed activities associated with the NRC Human Performance Program Plan.
)
FRIDAY, DECEMBER 6, 1997 I
i 4
5) 9:30 A.M.
- 11:00 A.M. :Meetina with the NRC Commis_s_ioners, j
Commissioners Conference Room, One White Flint North (Open) -
i j
The Committee will meet with the NRC Commissioners to discuss the matters identified above.
6) 1:30 P.M.
- 2:30 P.M.:NRC Emeraency Response Procram (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the modifications to the NRC Emergency Response Program.
a 4
9 i
APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE i
[ 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 Openino Remarks by the ACRS Chairman 1.
Introductory Statement of the ACRS
- Chairman, dated December 5-7, 1996 [ Handout]
2.
Items of Interest [ Handout) 4 NRC Research Program on Instrumentation and Control Systems 3.
Overview of RES Activities on Advanced I &
C, dated December 5,
- 1996, presented by Franklin
- Coffman, Engineer, RES [Viewgraphs]
5.
Plant Aoino Research Procram 4.
Steam Generator Tube Integrity 6.
Human Performance Procram Plan 5.
Human Performance Program Plan, dated December 5,
- 1996, presented by, Cecil O.
- Thomas, Chief, Human Factors Assessment Branch 6.
Human Performance Event Database, dated December 5,1996, presented by AEOD Staff 11.
Future ACRS Activities 7.
Future Activities - 438th ACRS Meeting, February 6-8, 1997 [ Handout 11.1]
12.
Report of the Plannina and Procedures Subcommittee 8.
Minutes of Planning & Procedures Subcommittee Meeting, dated December 4, 1996 [ Handout 12.1]
1 A'pendix V 2
p 437th ACRS Meeting 13.
NRC Emercency Resoonse Procram 9.
NRC Incident Response Program, dated December 6,
- 1996, presented by D.Ross, R.
Congel, and R.
Barrett 14.
Reconciliation of ACRS Comments and Recommendations 10.
Reconciliation of ACRS Comments and Recommendations
[ Handout 14.1]
l
)
i I
I
~ ~ -. -. -
1 Abpendix V 3
437th.ACRS Meeting MEETING NOTEBOOK CONTENTS
. TAR
' DOCUMENTS
)
2.
1.
Table of-Contents
'2.
Proposed Schedule 3.
Status Report 4.
Presentation at the ACRS Subcommittee on PRA by, G.
Holahan, NRR, and T. King, RES: Summary Regulatory Guides and Standard Review Plans for Risk Informed Decision Making on Plant Specific CLB Changes, dated November 22, 1996 [Viewgraphs) 5.
Memorandum f rom M. Hodges, RES, and G. Holahan, NRR to J.
Larkins, ACRS Executive Director: Transmittal of Draft Regulatory Guides DG-1062, 1064, and 1065 and Companion Standard Review Plans, dated November 15, 1996 6.
Memorandum from M. Hodges, RES, and G. Holahan, NRR to J.
Larkins, ACRS Executive Director: Transmittal of Draft Regulatory Guide DG-1061:
An Approach for Using Probabilistic Risk Assessment (PRA) in Plant Specific Risk-Informed'Decisionmaking: General Guidance and its Companion Standard Review Plan Section, dated November 8, 1996 7.
Memorandum from M.
Hodges, RES, to J.
Larkins, ACRS Executive Director: Transmittal of Pre-Decisional Draft NUREG-1602, Standards for Probabilistic Risk Assessment (PRA) to Support. Risk-Informed Decisionmaking, dated October 11, 1996 3.
Proposed Standard Review Plan (SRP) Sections and Reculatory Guides Associated with Risk-Informed, Performance-Based 1
Reculation 8.
Table of Contents 9.
Presentation Schedule 10.
Project Status Report 11.
Letter from T.
- Kress, ACRS Chairman, to J.
- Taylor, Executive Director for Operations:
Draft. Update of Standard Review Plan, Chapter 7,
' Instrumentation and Controls', dated October 23, 1996 12.
Letter from J. Taylor, Executive Director for Operations, to T.
Kress, ACRS Chairman: Draft Update of Standard Review Plan, Chapter 7,
' Instrumentation and Controls',
dated November 1, 1996 13.
Letter from T.
- Kress, ACRS Chairman, to J.
- Taylor, Executive Director for Operations: Regulatory Guidance Documents Related-to Digital Instrumentation and Control Systems, dated June 6, 1996
._m._..._....
4 I
Appendix V 4
437th ACRS Meeting I'
i 14.
Letter from J. Taylor, Executive Director for Operations, to T. -Kress, ACRS Chairman: Regulatory Guidance Documents Related to Digital Instrumentation and Control Systems, o
dated June 21, 1996 15.
Excerpt of 'RES Funding and
" FIN" Listing (FY-97)
Pertaining to Instrumentation and Control Systems Branch
- 16. ' Excerpt of Slides Presented to ACRS at September, 1996, Meeting by D.
- Morrison, RES, on Research Activities Pertaining to Control, Instrumentation and Human Factors 17.
Excerpt of Slides Presented to NAS at October 17, 1996 i
Briefing by L. Beltracchi, RES, on Digital I & C Research Programs 4.
NRC Research Procram on Instrumentation and Control Systems 18.
Table of Contents 19.
Proposed Schedule 20.
Status Report 5.
Human Performance Procram Plan 21.
Table of Contents t
'22.
Proposed Schedule l
23.
Status Report 24.
List of Questions raised at the September 20, 1996, ACRS Human Factors Subcommittee meeting and associated figures 25.
Memorandum from N. Dudley, ACRS Senior Staff Engineer, to ACRS Members : Certified Minutes of the September 20, 1996 Human Factors Subcommittee Meeting, dated June 1, 1996 12.
NRC Emercency Resoonse Procram 26.
Table of Contents 27.
Propsed Schedule 28.
Status Report
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