ML20140H395

Minutes of 435th ACRS Meetings in Rockville,Md on 961009-12 Re Appropriate Action on Items Listed in Attached Agenda. W/Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provided to Committee

ML20140H395
Person / Time
Issue date:	01/28/1997
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-3033, NUDOCS 9705130112
Download: ML20140H395 (51)

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,.) !1 lg i TABLE OF CONTENTS l T.y , I'l UTES OF THE 435TH ACRS MEETING b b 'u "

• d b OCTOBER 9-12, 1996 Pace I. Chairman's Report (Open) . . . . . . . . . . . . . 1 II. Risk-Informed, cerformanc3-Based Reculation (Open) 1 III. Plant Acinc (Open) . . . . . . . . . . . . . . . . 5 I IV. ODerator Trainina/ Simulator Use (Open) . . . . . . 6 V. Dicital Instrumentation and Control Systems (Open) 8 i

VI. Status of NRC Stratecic Assessment and  !

Rebaselininc Effort (Open) . . . . . . . . . . . . 12 )

711. Draft Uodate of Standard Review FlaO Chaeter 7.

"lngtrumentation and Controls" ,pe n ) . . . . . . . 14 l

VIII. Control Room Back-Panel Fir 3 at Palo Verde Unit 2 (Open) . . . . . . . . . . . . . . . . . . . 16 IX. Thermal-Hydraulics Research Procram Plan (Open) . . 17 X. .necutive Session (Open) . . . . . . . . . . . . 19 A. Reports and Letter Canability of the NRC SCDAP/RELAPS Code to Predict ,

Temoeratures and Flows in Steam Generators under Severe-Accident Conditions (Report to Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated October 22, 1996)

A Thermal-Hydraulics Research Plan (Report to Shirley i Ann Jackson, Chairman, NRC, from T.S. Kress, Chair-man, ACRS, dated October 21, 1996) e i Draft Uodate of Standard Review Plan. Chapter 7.

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" Instrumentation and Controls" (Letter to James M.  !

Taylor, Executive Direct;or for Operations, NRC,

from T.S. Kress, Chairman, ACRS, dated October 23, A 00f 3

1996) Ik ' l I B. Reconciliation of ACRS Commente and Recommen-dations ,

C. Report on the Meeting of the Planning and Proce-dures Subcommittee Held on October 8, 1996 (Open) 120089 D. Future Meet hq Agenda } [,, y l 9705130117 970128 DESIdNATD ORIGINAL PDR ACRS 3033 PDR ,

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APPENDICES I. Federal Register' Notice II. Meeting. Schedule and Outline i III.. Attendees i IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee l

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MINUTES OF THE FOUR HUNDRED THIRTY-FIFTH MEETING OF THE l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS l OCTOBER 9-12, 1996 L ROCKVILLE, MARYLAND The 435th meeting of the Advisory Committee on Reactor Safeguards

. was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on October 9-12, 1996. The purpose of this

. meeting was to discuss and take appropriate action on the items

, listed in the attached agenda. The meeting was open to public attendance. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.

l A transcript of selected portions of the meeting was kept and is i 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 1 (Vice-Chairman), Dr. George Apostolakis, Mr. John Barton, Dr. Ivan l Catton (not present October 9) , Dr. Mario H. Fontana, Dr. Don W. l Miller, Dr. Dana A. Powers, and Dr. William J. Shack. [For a list of other attendees, see Appendix III.]

I. CHAIRMAN'S REPORT (Open)

[ Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.)

Dr. Thomas S. Kress, Committee Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting. He announced that the first' day.of the meeting would consist of a joint session with members of the Canadian Advisory Committee on Nuclear Safety (ACNS). 4 II. RISK-INFORMED. PERFORMANCE-BASED REGULATION _(Open)

[ Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.)

Dr. George Apostolakis, Chairman of the Probabilistic Risk Assessment (PRA) Subcommittee introduced the topic to the Commit- ,

tee. He stated that Dr. Dana Powers would be giving part of the presentation on defense-in-depth for the ACRS and that Dr. Terry Rogers would give a presentation on the role of risk in nuclear j regulation in Canada for the ACNS.

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.t y 435th ACRS Meeting 2 October 9-12, 1996 ACRS Presentation Dr. Apostolakis provided an overview discussion of the ACRS activities in the area of risk-informed, performance-besed regulation. He provided his view on several definitions and key elements of the regulatory approach and reviewed questions and issues he considers important for establishing a risk-informed decision-making process. He noted the following significant points in his discussion:

• Risk-informed regulation involves deriving insights from PRAs and is used in combination with deterministic system analysis to focus licensee and regulatory attention on issues commensurate with their importance to safety.

e The regulatory approach to performance-based regulation consists of four key elements: 1) measurable parameters to monitor plant and licensee performance; 2) ob4ective risk criteria to assess performance based on a combina-tion of risk insights, deterministic analysis, and performance history; 3) licensee flexibility to determine how to meet established performance criteria; and 4) failure to meet a performance criterion must not result in unacceptable consequences.

e Risk-informed, performance-based regulation includes a number of questions: 1) What is licensee performance?

Is it possible to define? 2) What " measurable" parame-

, ters can we define to monitor " performance?" What would be the difficulties in doing so? 3) What do we mean by

" objective criteria?" 4) What is the proper role of uncertainties in such a regulatory system? 5) What is the proper role of defense-in-depth?

e A number of issues remain to be resolved for licensee-initiated changes to licensing: 1) Should the Commis-sion's Safety Goals and subsidiary objectives be refer-enced or used to derive guidelines for plant-specific applications and, if so, how? 2) How are uncertainties to be accounted for? That is, how should uncertainty analysis be used when assessing against acceptance guidelines? 3) Should requested changes to the current licensing basis be risk-neutral or should increases be permitted? 4) How should performance-based regulation be implemented in the context of risk-informed regulation?

Dr. Apostolakis summarized his view on these issues and those taken ,

by the ACRS in their letter dated August 15, 1996. l l

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435th ACRS Meeting 3 October 9-12, 1996 Dr. Powers provided an overview of his perspective on " defense-in-depth," including a discussion of definitions and the historic roots of the term, views of the International Atomic Energy Agency as well as those of other noted experts, and several options for application to a risk-informed regulatory environment. He noted the following significant points in his discussion:

e Defense-in-depth is proclaimed as the cornerstone of today's prescriptive regulations, yet it is not defined, is not a ' design to' standard, and may be expensive to implement e Textbook definitions are by example but are always the same example e Defense-in-depth arose in the early days of the work to develop commercial nuclear power because it was found that:

Although risk was thought to be low, the analysis was most uncertain There was great phenomenological uncertainty There were low levels of operational experi-ence and no industrial standards An accident at any location was thought to jeopardize the entire effort to develop com-mercial nuclear power e Defense-in-depth can be a " structural" philosophy for the regulatory system to use successive barriers to prevent the release of radiation to the environment and exposure of the public. This concept, when properly applied, is intended to ensure that no single human or mechanical failure leads to injury of the public.

e The International Nuclear Safety Advisory Group example of defense-in-depth includes: 1) first barrier -a conservative design, quality assurance, and safety culture; 2) second barrier -

control of abnormal operation and failure detection; 3) third barrier -

safety systems; 4) fourth barrier - accident management and confineme t protection; and 5) fifth barrier -

offsite emergency response.

o Options available to ACRS for the treatment of defense-in-depth include: 1) Ignore the issue, 2) It is part of

, e 435th ACRS Meeting 4 October 9-12, 1996 the safety framework, 3) Use it to cap risk, and 4) It is a complement to rational, risk-informed regulation.

ACNS Presentation Dr. Rogers provided an overview of the Canadian approach to risk-based regulation. This included a discussion of early risk-based objectives, the evolution of safety requirements, prescriptive and deterministic requirements, proposed risk-based objectives, the current role of risk in regulation, and expectations for future activities in this area. He noted the following significant points in his discussion:

e The Atomic Energy Control Board (AECB) generally sets safety objectives rather than prescriptive requirements.

e The initial approach was largely driven by the AECB Siting Guide which had difficulties in that there was no distinction between single / dual failures, no explicit treatment of low-frequency  : toff, and no treatment of external events and beyond- sign-basis accidents.

e Recent initiatives have .b :luded a revision to the qualitative safety objectives, an update to the general safety requirements to consider risk and licensee initiatives in this area, and development of a proposed quantitative approach to safety.

e The ACNS has recommended general safety principles and requirements, including rules for meeting risk-based rationale and deterministic elements for defense-in-depth, and bases for detailed requirements.

e Elements of quantitative safety requirements include risk-based consideration of: risk to the public, workers, society, and the environment; nonradiological risks; I application of ALARA (to achieve occupational and public  ;

exposure to radiation as low as is reasonably achievable) '

with frequency limits for normal and accident conditions; and exemption levels based on "de minimus" risks.

• A three-region approach is used where one level in acceptable, one is unacceptable, and one is conditionally acceptable (via ALARA or other processee).

Dr. Rogers questioned whether the NRC approach to defense-in-depth was limited to the barriers for the control of the release of radiation. Dr. Seale stated that the industry also uses defense-in-depth for investment protection.

a e 435th ACRS Meeting 5 October 9-12, 1996 Dr. Powers questioned whether the Canadian approach to risk was limited to assessment of fatalities or whether there was some consideration given to biological detriment. ACNS representatives stated that the focus was on fatalities. They also stated that the potential risk from radiation was weighed against other industrial hazards in considering total risk.

Dr. Apostolakis questioned whether the ACNS was using core damage frequency (CDF) and large, early release frequency (LERF) as subsidiary objectives for their safety goals. ACNS representatives stated that they do not use CDF or LERF. They added that their Level 3 PRAs do not include consideration of external events or other modes of operation such as shutdown. Dr. Robertson, ACNS, expressed the view that CDF should be a means objective rather than a fundamental objective.

Dr. Apostolakis questioned whether the use of PRA was considered an additional regulatory burden. ACNS representatives stated that

, there was some initial resistance and that the early studies were not as useful as they could be. Mr. Antonio Natalizio, ACNS, expressed the view that PRAs are not very good at measuring risk but are very useful at enhancing safety.

Conclusion This briefing was for information only. No Committee action was required.

III. PLANT AGING Wpen)

[ Note: Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.]

ACRS Presentation Dr. William Shack, Chairman of the ACRS Materials and Metallurgy Subcommittee, summarized ACRS reviews of NRC activities related to the aging of United States nuclear plant components. He explained that the maintenance rule addresses plant aging concerns for much of the nuclear plant equipment and that the overall assessment of aging is formally considered as part of the license renewal process. Aging issues include reactor vessel radiation embrittle-  :

ment, cracking of reactor vessel internals and head penetrations, l metal fatigue, and steam generator tube degradation. Dr. Shack highlighted the differences between prescriptive and performance-based regulatory requirements for different types of component aging issues. He explained the background, objectives, risk j impact, performance criteria, and outstanding technical issues i 1

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435th ACRS Meeting 6 October 9-12, 1996 associated with the proposed risk-informed, performance-based steam generator integrity rule.

l ACNS Presentation Dr. Andre Biron, ACNS, summarized the status of the Canadian ,

regulatory document related to aging and the associated industry activities. He explained that the working group preparing the regulatory document was tasked tc review the policies and practices  ;

of Canadian and foreign nuclear utilities, to review the AECB staf f l progress on developing relevant policies, and to report on its I findings. No Canadian utility has identified how structures, l systems, and components (SSCs) important to safety will be defined l and included in aging management programs, nor how the program j elements will be integrated and managed. Dr. Biron noted that some !

identified aging-related ef fects include leakage through structural containment concrete and pressure tube creep. He stated that i Canadian utilities are reluctant to support a detailed regulatory l document on aging. Canadian research studies include the aging of '

cable insulation, elastomers, concrete, and valve diaphragms. Some i Canadian utilities are beginning age-related studies associated i with extension of plant life from 30 to 50 years.

The members of the ACRS and ACNS discussed equipment covered by the NRC maintenance rule and the NRC use of risk in developing regulations. They also discussed the public perception of aging j concerns, length of plant licenses, research related to electrical '

cable aging, inservice inspection techniques and criteria, obsolescence of computer hardware and software, and plant design margins in relationship to SSC aging.

l Conclusion I This briefing was for information only. No Committee action waas required.

IV. OPERATOR TRAINING / SIMULATOR USE (Open)

[ Note: Mr. P. Boehnert was the Designated Federal Official for this portion of the meeting.)

ACRS Presentation Dr. Robert Seale noted the following points regarding the issue of operator training and simulator use in the U.S.:

o Post-Three Mile Island, NRC issued a rule that required all nuclear power plants to have a plant-specific simula-

435th ACRS Meeting 7 October 9-12, 1996 tor. Over the years, these simulators have become fairly sophisticated.

• NRC has deferred most aspects of operator training to the licensees, given the specificity of design for the plants. NRC used to prepare operator licensing exams; now, the exams are prepared by the licensees and NRC has taken a monitoring role.

e The Agency has assembled a suite of plant simulators, located at the NRC Technical Training Center in Chatta-nooga, Tennessee. There are six simulators representa-tive of the BWR/6, B&W, BWR/4, CE, and Westinghouse (Trojan-vintage) designs.

e The focus of simulator use has shifted to evaluation of plant emergency response; in particular, to a study of the effect of plant procedures on plant operations.

This, in turn, poses a significant challenge to, simulator modeling capability, as accident evaluation approaches core melt scenarios. To this end, there is a concerted effort to enhance the physics contained in the simulator models. 1 e Little in the way of this topic has been discussed by the Committee in the past couple of years.

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ACNS Presentation Mr. Natalizio presented the perspectives of the ACNS on this i matter. He noted the following points:

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e The issue of operator training is significant; the issue .

of human performance in the control room is at least as I important as good design to reactor safety. To this end, the ACNS established a working group (Working Group 19) to explore the issue of operator competence.

• For the past 30 years, operators have been subjected to an examination administered by the AECB that addressed five areas: nuclear (" general" and " specific"), conven-tional (" general" and " specific") and radiation protec-tion. Some shortcomings have been observed; e.g., tests focused on knowledge rather than skill level, and utility training focused on " teaching the exam."

e The AECB has now adopted the systematic approach to training, and all utilities are implementing it. The responsibility to ensure operators are well trained and competent to assume their duties is clearly defined to be

435th ACRS Meeting 8 October 9-12, 1996 that of the utilities. The AECB's role is to ensure that the utilities carry out this responsibility.

• Simulator training was introduced in the 1980s. For the future, the intent is to have the utilities prepare and administer licensing examinations, as in the U.S. It is expected that training examinations will be required for technicians and maintenance personnel as well.

• The role of the ACNS is to review the effectiveness of the training and certification process and make recommen-dations as appropriate. l In summary, the ACRS and ACNS indicated that the U.S. and Canadian l programs in this area are quite similar in scope and content.

Dr. Seale noted the existence of a paper written by Z. Pate, Institute for Nuclear Power Operations, that addresses the problems seen both in nuclear power plant control rooms and commercial aviation resulting from human error. (Copies of this paper were  ;

provided to all present.) Dr. Apostolakis raised the issue of the l impact of human error on plant safety; specifically, the concern with so-called circumvention behavior, where people intentionally violate procedures by taking "short-cuts." He indicated that this behavior results from the lack of a formal " safety culture." Dr.

Seale stated that licensees must enforce the discipline associated with a proper safety culture.

Conclusion This briefing was for information only. No Committee action was required.

V. DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS (Open)

(Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.]

Dr. Don Miller, Chairman of the Instrumentation and Control Systems and Computers Subcommittee introduced the topic. He noted that his presentation would focus on the study being conducted by the National Academy of Sciences / National Research Council (:NAS/NRC) and the NRC staff effort to update the Standard Review Plan (SRP) for digital instrumentation and control (I&C) systems. He also stated that Dr. Pearson would be lead the discussions for the ACNS regarding this matter.

ACRS Presentation

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435th ACRS Meeting 9 October 9-12, 1996 Dr. Miller reviewed the history of the ACRS involvement in digital I&C, including the Committee's recommendation to the Commission that an independent study be performed by the NAS/NRC. He summarized the results of the NAS/NRC Phase 1 study which defined important safety and reliability issues. He also summarized the ACRS views on the Phase 1 study and described the objectives and schedule for completion of the Phase 2 study. Dr. Miller described the staff's approach to updating the existing SRP Chapter 7 for I&C, ACRS involvement during the early stages of development, and its continuing review as items are completed. He also described the ACRS review of NRC research and training programs as well as plans for future activities in this area. He noted the following significant points in his discussion:

e The NAS/NRC Phase 1 study identified the following issues:

Technical: 1) software quality assurance, 2) common-mode software failure potential, 3) system aspects of digital I&C technology, 4) human factors and human-machine interfaces, 5) safety and reliability assessment methods, and 6) dedication of commercial off-the-shelf (COTS) hardware and software

, Strateoic: 1) case-by-case licensing process and 2) j adequacy of technical infrastructure e ACRS agrees that the Phase 1 issues will be important considerations as digital technology is used more i exter>sively in nuclear power plants. I e ACRS believes that environmental stressors (lightning and l smoke) are important issues for the NRC staff to address l but decided not to raise it to the level of a " key technical issue" for the Phase 2 study.

• ACRS believes it is important that the SRP Chapter 7 update and associated regulatory guidance benefit from the insights in the Phase 2 report.

e The NAS/NRC Phase 2 study is expected to: 1) identify criteria for review and acceptance in both retrofitted and new reactors of advanced design, 2) characterize and evaluate alternative approaches to certification or licensing, 3) recommend guidelines to regulate and certify (or license) digital I&C systems, and 4) identify and address new issues that may result from the future development of this technology.

l 435th ACRS Meeting 10 October 9-12, 1996 e The NRC staff approach to updating SRP Chapter 7 is to:

1) maintain existing regulatory bases, 2) revise most SRP sections and develop three new ones - all branch techni- I cal positions (BTPs) are new, 3) incorporate lessons learned from acvanced light water reactor reviews and from digital retrofits, and 4) use generally accepted U.S. software engineering practices and standards.

o ACRS involvement includes the following reviews: 1) draft SRP and associated guidance in the early stages of development - March, May, and October 1996, 2) NRC l

training and research programs for I&C technology, and 3) l the proposed final SRP update in April 1997 including integratia of public comments and the NAS/NRC Phase 2 l study, i

e The continuing ACRS review includes: 1) verifying the i relationship or communication of Chapter 7 to other SRP Chapters, 2) evaluating graded approaches relative to i importance to safety, 3) examining the emphasis on I process to ensure quality, and 4) reviewing provisions I for sof tware reliability, hardware and software obsoles- l cence, and for the use of COTS software.

l e Other ACRS activities include: 1) reviewing SER or BTP on  ;

COTS, when available; 2) reviewing digital vulnerability l to environmental stressors (lightning and smoke); 3) ensuring consistency between SRP Chapter 7, other SRP l Chapters and risk-informed, performance-based regulation; )

4) reviewing emerging technology and integration into NRC  ;

programs; and 5) continuing review of NRC training i programs. l ACNS Presentation Dr. Pearson reviewed the general background and history of applying digital I&C technology in Canadian nuclear facilities. He noted that their experience in applying computers to nuclear plants stretches over more than 30 years and their experience has been generally good. He noted the following significant points in his discussion:

o The software for the current systems was developed, installed, and implemented without being audited in detail by regulatory authorities. He noted that it would likely not meet the regulatory scrutiny now required.

Nevertheless, these systems have worked and continue to be used.

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435th ACRS Meeting 11 l October 9-12, 1996 e In applying computers and digital technology, there was i no intent to change the basic safety philosophy.

1 i e Regulatory ' review of sof tware became a very laborious 4

effort such that by the end of 1988,.it was the major

licensing problem.

4 e Software experts were consulted and it was . determined

that safety-critical software should be created using

" formal methods." ~

. e AECB directed Ontario Hydro to redesign the software to facilitate review and maintenance. The new design is expected to be complete in 1998.

e In 1992, ACNS presented the following recommendations to the AECB: 1) AECB should work with industry to develop standards and have them issued through a consensus process, 2) a schedule should be developed to mon. tor the

, progress of standards development, 3) AECB guidance docu-

ments should focus on ensuring sof tware is auditable, and

4) AECB should document, and encourage industry to

. document, failures.

The ACRS and ACNS ' discussed the reliability of software. Dr.

i Powers questioned the view that most errors are introduced'in the requirements phase (i.e. , functional requirements not being there) .

. Dr. Apostolakis agreed, but added that errors are also introduced

with complexity. Dr. Pearson stated that software can be very

reliable, but it is difficult to prove.

Dr. Apostolakis questioned the use of formal methods in assuring o

success. He noted that the British tried using formal methods and generally had poor expe rience. Dr. Fontana asked whether success could be fully demonstrated through testing. Drs. Apostolakis and Kress stated that you cannot always decide through testing alone j whether the software " failed" or not. Dr. Pearson stated that safety systems are designed to be simple, as should the software.

He emphasized that there is a need for standards to ensure the

! process is controlled and configuration is maintained.

Conclusion This briefing was for information only. No Committee action was l

required.

I j VI. STATUS OF NRC STRATEGIC ASSESSMENT AND REBASELINING (Open) 1 4

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. [ Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.) l Dr. Kress, ACRS Chairman, introduced Mr. James Milhoan, Deputy Executive Director for Nuclear Reactor Regulation and Regional Operations and Research, who, with other NRC staff, discussed the NRC strategic assessment and rebaselining effort.

Mr. Milhoan stated that Chairman Jackson initiated a strategic l assessment and rebaselining of the NRC in September 1995. This effort is being completed in four phases with the goal of finaliz- )

ing a strategic plan in early calendar year 1997. The development and implementation of this strategic plan will meet the require-ments of the Government Performance and Results Act (GPRA) of 1993.

To oversee this activity, a Strategic Assessment and Rebaselining j Steering Committee of senior NRC managers was formed. The Steering Committee is analyzing where the NRC is today and is developing options the Commission can use to determine the agency's future path. The overall objectives are to establish a strategic framework under which the NRC will continue to meet its responsi-bility for protection of the public health and safety; to provide a sound and well-rounded foundation for NRC direction and decision-making for the rest of this decade and into the twenty-first century; to ensure that the Commission, its staff, Congress, other Government agencies, and the public have a common understanding of the NRC's strategic goals; and to establish agency performance measures to determine the extent to which strategic or tactical objectives are being achieved.

Mr. John Craig, NRC, described the four phases of the Strategic Assessment and Rebaselining effort as follows :

Phase I: Strategic Assessment - the Steering Committee began with a bottom-up approach for assessing where the agency is today, with an examination of current NRC functions and activities. The staff assessment included approximately 4,500 activities. These activities were organized by major functions and lines of business.

Based on this information, the Steering Committee applied top-iiown strategic thinking to define those issues where a resolution would influence the future direction of the NRC. After identifying the strategic issues, the Steering Committee considered them in an integrated fashion. First, the individual strategic issues were arranged in logical groupings of related issues. The groups were then examined to determine if a predominant issue existed within each group. These predominant issues are referred to as " Direction Setting Issues" (DSIs) because their resolution would establish the NRC's strategic direction for the future.

Phase II: Rebaselining and Issue Papers - this phase builds on the strategic issues and the DSIs identified in Phase I. The issue

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. 1 435th ACRS Meeting 13 October 9-12, 1996 papers are intended to obtain broad direction from the Commission.

The issue papers include descriptions of the background of 16 issues and the external as well as the internal factors that the Commission may wish to be aware of when considering options for resolution of the issue.

The 16 issues are:

e DSI #2 Oversight of the Department of Energy e DSI #4 NRC's Relationship with Agreement States e DSI #5 Low-Level Waste e DSI #6 High-Level Waste and Spent Fuel e DSI #7 Materials / Medical Cversight e DSI #9 Decommissioning, Nonreactor Facilities e DSI #10 Reactor Licensing for Future Applicants e DSI #11 Operating Reactor Program Oversight

• DSI #12 Risk-informed, Performance-Based Regulation e DSI #13 Role of Industry e DSI #14 Public Communication Initiatives

• DSI #20 International Activities e DSI #21 Fees e DSI #22 Research e DSI #23 Enhancing Regulatory Excellence e DSI #24 Power Reactor Decommissioning Prior to reaching final decisions on the issues, the Commission wants to have the benefit of stakeholders views. The stakeholders include Federal entities (e.g , Congress, Office of Management and Budget), NRC employees, States, Agreement States, licensees, industry groups and special interest groups, and the general public. There are three documents available to help the public make comments: 1) a stakeholder involvement process paper, 2) a set of direction-setting papers on 16 issues with Commission prelimi-nary views on each, and 3) a strategic planning framework paper which explains how the issues relate to the strategic plan and how the plan will be developed.

To help understand their viewpoints, stakeholders are asked to focus on the following in responding to the NRC:

1. What, if any, important considerations may have been omitted from the issue papers?

2. How accurate are NRC's assumptions and projections for internal and external factors discussed in the issue papers?

3. Do the Commission's preliminary views associated with each issue paper respond to the current environment and challenges?

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435th ACRS Meeting 14 l October 9-12, 1996 Additionally, the Commission is seeking comments on specific questions identified in the " Preliminary Commission View" section of each issue paper.

l The comment period on the issue papers closes November 15, 1396. )

Comments can be provided in writing, electronically, or at the public conferences.

The NRC will hold three public conferences to discuss the issue papers and to obtain comments from stakeholders. The conference dates and locations are:

Cctober 24-25, Washington, DC (Washington Hilton);

Octsber 31 - November 1, Colorado Springs, CO (Sheraton);

November 7-8, Chicago, IL (Ramada O' Hare).

Phase III: Production of a Strategic Plan - the Strategic Plan will be developed from the agency's mission statement, its strategic vision, general goals, and the Commission's decisions on the issue papers. The Stracegic Plan will be the agency's tool for setting priorities and allocating resources. It is anticipated that the Strategic Plan will be forwarded to the Commission by early "v 1997.

Phase IV: Implementation - this phase will begin as soon as the Commission makes final decisions on the issue papers. This phase will also include developing a framework that allows for updating the Strategic Plan and for integration into the budget process, performance monitoring, and reporting process.

Currently, the NRC Strategic Assessment effort is in the latter portion of Phase II where the Commission is considering a variety of options for key strategic issues facing the NRC. Work on Phase III has also begun.

4 Conclusion This briefing was for information only. However, some Committee j members may write individual comments regarding this matter prior to the closure of the comment period.

VII. DRAFT UPDATE OF STANDARD REVIEW PLAN, CHAPTER 7. "INSTRU-MENTATION AND CONTROLS" (Open)

{ Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.)

Dr. Don Miller, Chairman of the ACRS Subcommittee on Instrumenta- l tion and Control Systems and Computers, introduced this topic to

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the Committee. He stated that the purpose of this meeting was to continue the Committee's review of draft SRP sections and BTPs related to I&C systems. He noted that the ACRS had previously met ,

to discuss these matters in March and May 1996 and that the I&C l Systems and Computers Subcommittee had met on October 8, 1996. He I introduced Mr. Bruce Boger, Director, Division of Reactor Controls l

, and Human Factors (DRCH), NRR. I NRC Presentation l 1

Mr. Boger introduced Mr. Matthew Chiramal, Senior Level Advisor, l DRCH, who led the discussions for the NRC staff. Messrs. Jerry Wermiel, Chief, Instrumentation and Controls Branch, and Gary Johnson, Lawrence Livermore National Laboratory, provided support-ing discussion. Mr. Chiramal provided an overview of the SRP update including a discussion of the ground rules to maintain the current regulatory framework, endorsement of existing industrial standards, and proper use of the SRP and associated guidance for reviews of modifications (rrtrofits) and for future reviews of advanced reactor designs. de made the following significant points in his discussion:

e There are no fundamental changes in the SRP from the last update in 1981. The update includes several new SRP sections. All the BTPs are new, as are the regulatory guides.

e The SRP is intended to be a guide for use by NRC review-ers in evaluating licensee submittals. It is not a designer's guide although it is expected to be helpful in assisting licensees in understanding what the reviewer will consider in evaluating submittals.

• A graded approach will be applied by the reviewer in consultation with his/her supervisor based on importance to safety. The staff plans to integrate provisions of Graded Quality Assurance when the guidance becomes available.

Dr. Shack questioned whether environmental qualification was handled separately. The staff stated that it was not. Specific guidance is contained in the industrial standards and general design criteria. The staff also stated that most I&C systems are located in mild environments.

Dr. Shack also questioned whether the SRP/BTPs address the use of formal nethods. The staff stated that they do not and added that they do not believe they are necessary. They further stated that they would consider getting expert contractor support to evaluate formal methods if they were part of a licensee submittal.

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1 435th ACRS. Meeting 16 i

October 9-12, 1996 l

> l Dr. Apostolakis questioned the " general" nature of acceptance criteria. He expressed the view that stated acceptance criteria do i

not provide much guidance regarding what is acceptable and that the guidance should be more specific. The staff reiterated that the

, guidance . is intended for the reviewer and they do not want to constrain the licensee's design processes by being overly specific. )

Dr. Apostolakis expressed the belief that the judgment process for '

i_

NRC reviews should have more discipline and scrutability. -l Dr. Apostolakis reiterated ACRS concerns regarding the emphasis on process versus product as_ stated in its June 6, 1996 letter. He  ;

expressed the view that the SRP should also identify some analyti- )

cal tools which can be used in specific cases. The staff stated that its approach was to endorse generally accepted standards for l software development and it did~not want to inhibit innovation by  ;

prescribing acceptable methods. The staff stated that the methods l proposed in licensee submittals would be reviewed on a case-by-case i 5

basis. l

Overall, the ACRS had no objection to the staff issuing the draft I i

SRP and BTPs for public comment. However, the Committee decided to i continue discussing the matters identified in their June 6, 1996 j j letter, during future meetings with the staff.  !

i i Conclusion I

The Committee issued a letter to the Executive Director for

. Operations, dated October 23, 1996, on this matter.

VIII. CONTROL ROOM BACK-PANEL FIRE AT PALO VERDE UNIT 2 (Open)

I (Note: Mr. A. Singh was'the Designated Federal Official for this )

portion of the meeting.] l

, Introduction

~

Mr. John Barton, Chairman of the' Plant Operations Subcommittee, introduced the topic to the Committee. Mr. Barton stated that the j purpose of this presentation was to brief the Committee regarding j the results of the investigation of the April 4, 1996, event that ]

involved two related fires in-a back-panel of the control room at- '

Palo Verde Unit 2.

NRR Presentation Mr. Alfred Chafee, Branch Chief, Events Assessment and Generic 4

Communications Branch, NRR, introduced the NRR staff and Mr. Philip i Qualls, Region IV. Mr. Robert Dennig, NRR, presented the results

, of the special inspection.

l 435th ACRS Meeting 17 October 9-12, 1996 On April 4, 1996, an Alert was declared at Palo Verde Unit 2, due to two related fires in a back-panel of the main control room.

These fires were associated with a voltage regulating transformer l which supplied power to the train B essential lighting uninterrup-tible power supply panel. These fires affected one train of essential e.mergency lighting for the distribution panel in the l control room. The fires were promptly detected and extinguished '

and posed no apparent safety threat to the facility, which was shut down for a refueling outage at that time. l The licensee's root-cause investigation indicated that the core of the regulating transformer failed and contacted the transformer coils, causing a short circuit fault to station ground through the transformer's panel ground. The licensee determined that, because the neutral leg of the transformer was not grounded, the fault current propagated through the station grounding system into panels located in the control room. The overcurrent resulting from the fault caused the fires in the control room.

The licensee's corrective actions include modification to the  !

circuit by grounding the transformer's neutral leg and fusing the output of the transformer's secondary to protect the circuits supplied from the transformer from fault propagation.

Conclusion This briefing was for information only. No Committee action was required.

IX. THERMAL-HYDRAULICS RESEARCH PROGRAM PLAN (Open)  ;

1 Introduction Dr. Ivan Catton, Chairman, Thermal-Hydraulic Phenomena Subcommit-tee, introduced this topic to the Committee. He noted that RES had a Five-Year Plan for thermal-hydraulics (T/H) research. The centerpiece of this Plan is the revision of its T/H codes, via a j collapse of the current four codes into a single revised code. l This new code will be based on the TRAC-P code architecture. Dr.

Catton noted that the success of the use of TRAC-P for this effort is an open question at this point.

Dr. Catton said that the Subcommittee is pleased with the RES Plan.

This long-overdue effort will revitalize T/H research. The three test facilities utilized by RES (replicas of BWR, B&W, and AP600 designs), together with a proposed cooperative program with the French authorities will, in his opinion, comprise a sound program.

1 . .

a s

• N 435th ACRS Meeting 18

f. October 9-12, 1996 i Comments on T/H Code Users Needs Mr. Ralph Caruso, NRR, provided his perspective as an NRR T/H code i user. He discussed the uses made of these codes and the typical 4

analysis requests he receives. He defined three classes of users:

knowledgeable, occasional, and those who do systems analysis. The last two groups are - the fastest growing, and the new T/H code '

should be capable of being successfully operated by .these two

groups. He stated that the new code must be robust, be defensible l i

' by its author, be platform independent, and its limits of applica-bility and the uncertainty associated with its results must be well documented. He also recommended that RES work closely with the ]

7 user community and keep a living document of this community's  !

. experience.

i During discussion, Mr. Caruso noted that RES and NRR/AEOD have I agreed to establish a Working Group to facilitate interchange with l the users. Further, Mr. Caruso stated that RES has been very -

responsive to the needs of the Agency's users.

RES Thermal-Hydrdulics Research plan l An overview of the RES Five-Year Thermal-Hydraulics Research Plan  !

was presented by Dr. F. Eltawila, RES. Key points included:  !

e The goal of the Plan is to maintain a core competency in thermal-hydraulics, reactor physics, and plant transient l codes to support regulatory decisions and continuous international interactions.

e A revised state-of-the-art T/H code will be developed to perform accident analyses in both current and advanced reactor designs. An approach has been devised for ,

integrating / upgrading the existing capabilities into a l single code, consisting of three elements: 1 Development of code capability requirements I Consolidation of preferred models/ capabilities into a single code Assessment, parameter ranging, and scaling e Pilot studies will be conducted to develop both the data  :

base and associated two-phase and constitutive models for l improved two-fluid calculational capability. Likewise, pilot projects will be initiated to capitalize on advances in computational fluid dynamics (CFD) for multi-phase flows in complex geometries.

l l-435th ACRS Meeting 19 l October 9-12, 1996 l e The goals of the RES T/H test program are to conduct of separate-effects tests, maintain and develop technical skills, and use test data as a guid pro quo to obtain l similar data from international experimental programs.

• A number of steps have been taken to develop and maintain RES in-house expertise. These actions include hiring and training skillad T/H researchere, maintaining interac-tions (both U.S . and internatj anal) on codes and test data, and training the RES staf f to run and interpret T/H code results.

In response to Committee questions, RES indicated that they strongly believe that TRAC-P will be amenable to successful restructuring. RES is alsr investigating the use of parallel processing capability; they will require that the new code be able to utilize such capability. Dr. Catton urged RES to try to obtain information on the CFD work performed by the French. Dr. Eltawila also noted that RES is exploring cooperative research ventures with other countries (e.g., England, Germany, Korea).

Dr. Catton indicated that the RES T/H Research Program is proceed-ing in the right direction and should provide useful results, even if the TRAC code cannot be successfully overhauled.

Conclusion The ACRS issued a report to Chairman Jackson, dated October 21, 1996, on this matter.

X. EXECUTIVE SESSION (Open)

[ Note: Dr. John T. Larkins was the Designated Federal Of ficial for this portion of the meeting.]

A. Reports and Letter Cacability of the NRC SCDAP/RELAP5 Code to Predict Temperatures and Flows in Steam Generators under Severe-Accident Conditions (Report to Shirley Ann Jackson, Chairman, NRC, f rom T . S . Kress, Chairman, ACRS, dated October 22, 1996.)

Thermal-Hydraulics Research Plan (Report to Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated October 21, 1996.)

435th ACRS Meeting 20 October 9-12, 1996 Draf t Uodate of Standard Review Plan. Chanter 7. "Instru-mentation and Controls" (Letter to James M. Taylor, Executive Director for Operations, NRC, from T.S. Kress, Chairman, ACRS, dated October 23, 1996)

B. Reconciliation of ACRS Comments and Recommendations

[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.]

The Committee discussed the response from the IRC Executive ,

Director for Operations dated September 13, 1996, responding i to ACRS comments and recommendations included in the ACRS report dated August 15, 1996, concerning Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Stan-dardized Passive Reactor Design.

l C. Report on the Meeting of the Planning and Procedures Subcommittee (Open)

The Committee heard a report from Dr. Kress on the Planning and Procedures Subcommittee meeting held on October 8, 1996.

The following items were discussed: I

1. PROPOSED MEETING DATES Proposed meeting dates for CY 1997 were included in the Calendar. Members are requested to review these dates and prov 'de comments at the October 17- l 19, 1996 meeting in 3oston. Final dates will be 1 approved during the November ACRS meeting.

RECOMMENDATION The Subcommittee recommended that ACRS Members submit any proposed changes to these dates at the October 17 ? 9, 1996 meeting in Boston.

2. MEMBER SELECTION PROCESS Currently, only Warren Fujimoto has been endorsed by the Screening Panel and found acceptable to all the ACRS members. He could fill either the posi-tion of former members C. Wylie or W. Lindblad.

Candidates are still being sought for the remaining ACRS opening.

RECOMMENDATION

l 435th ACRS Meeting 21 October 9-12, 1996 The Subcommittee recommended that Dr. Larkins, ACRS Executive Director, send a letter to the Commission expressing the ACRS endorsement of Mr. Fujimoto. l

3. MEETING OF ACRS EXECUTIVE DIRECTOR WITH NEW COMMIS- l SIONERS Dr. Larkins, ACRS Executive Director, met with l Commissioner Diaz on October 2, 1996. The role of i the ACRS in the regulatory process, the technical i background of members, and current Committee activ-  !

ities were discussed. Dr. Larkins emphasized the l fact that the ACRS is a valuable resource for the l Commission and has be en asked by the Commission, as well as by individual Commissioners, to address a number of key techrical and regulatory issues. ,

Additionally, the Comnissioner was invited to meet 1 with the ACRS to provide hic viewo on priority I issues coming before the Commission or any issue he i might want to discuss. Dr. Larkins will meet with l Commissioner McGaffigan on October 10, 1996.

4. INTERNATIONAL MEETINGJ A. Dr. Yasumasa Togo, Chairman, Nuclear Safety Commission, Japan, sent a fax proposing that the next Quadripartite Meeting be held in October 1997.

B. The German RSK Committee sent a fax to suggest that the proposed meeting with ACRS on ad-vanced reactor research be postponed until spring 1997. Ms. Summers replied by fax to suggest that this topic either be added to the agenda for the Quadripartite Meeting (which at that time was tentatively scheduled for the same time frame), or that a separate meeting be arranged during one of the ACRS meetings in 1997. In light of the postponement of the Quadripartite Meeting, it is more likely that a separate meeting will be scheduled.

C. Ms. Summers is co-chairing a Panel Session at the Pacific Basin Nuclear Conference in Kobe, Japan, on October 20-25, 1996. During her trip to Japan, she also plans to discuss the Quadripartite Meeting dates and agenda with Dr. Togo. A previous letter to Dr. Togo proposed several topics for discussion. These topics should be reviewed by the Committee so

__m. _ _ _ _ .. ._ . _ _ _ > _ _ . _ _ _ . _ _ _ . _ . . _ _. . ._ .._, _ ._

j s

435th ACRS Meeting- 22

j. October 9-12, 1996  !

! that Ms. Summers can take an updated list to l i Japan. '

1 i-  !

I RECOMMENDATIONS 4 l

A. The Subcommittee recommended that ACRS Members -

4 review their schedules for October 1997 and

, indicate, during the October 17-19, 1996 meeting in Boston, any dates during that month that would not be suitable for them to attend 4

a Quadripartite = Meeting in Japan.

I B. The Subcommittee recommended that, after-the Committee determines the Full Committee meet-

ing dates for CY 1997, a fax be sent to the German ' RSK Committee suggesting that they choose a meeting date that would coincide with

'one of the scheduled ACRS meetings.

1 C. The Subcommittee recommended that the ACRS

Members review the topics listed in'the at-tached letter to Dr. Togo and make any addi-I^

tions or revisions during the : October 1996 meeting.

. 5. RETREAT a

! Dr. Seale has prepared a proposed schedule and outline for discussion during the October 17-19, i 1996 meeting in Boston. Members are requested to l provide their comments during this meeting.

j RECOMMENDATION i The Subcommittee recommended that Members provide Dr. Seale with comments on the proposed schedule and outline during the October 1996 meeting.

6. NRC'S REBASELINING/ STRATEGIC PLANNING ACTIVITIES ACRS Members were sent a package containing 'the Direction Setting Issue (DSI) Papers for their review and comment . Comments were requested by October 4. So far, comments have been provided by Dr. Powers, Dr. Fontana, and Mr..Barton. Subcom-mittee Chairmen should discuss their preference for Committee comments, individual comments, or no comments. Any proposed Committee comments would

_ . - ~ _ _ __ _ _ _ _ . _ _ - ..- . .. . - - . _ _ _ _ _ __ _

l

~

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l 435th ACRS Meeting 23 l October 9-12, 1996 have to be drafted this month for issuance next i

month. The ACNW will be provided copies of ACRS comments and vice versa. l RECOMMENDATION 4

The Subcommittee recommended that all Members read the DSI papers and make recommendations to the Committee for deciding:

i e should the Committee comment on any of these DSIs, and, if so, which DSIs?

e If the' Committee decides not to comment on certain DSIs, do individual Members want to

send their personal views on the DSIs?

The Members should provide their comments and i

' recommendations so that the Committee can make its 1 decision on Saturday, October 12, 1996. I

7. STATUS OF NRC FY97 BUDGET On September 30, 1996, the President signed the FY 1997 Energy and Water Development Appropriation

. Bill, which includes $476.8 millien for the NRC.

4- 8). TRAVEL A request was received from Dr. Kress to attend the International Atomic Energy Agency meeting in Vienna, Austria, on November 10-15, 1996.

Also, a request was received from Dr. Seale to attend the ANS winter meeting in Washington D.C. on November 10-13, 1996.

RECOMMENDATION The Subcommittee recommended that the requested trips be approved. .

9. MEMBER ISSUES Dr. Powers requested review of a letter from the Electric Power Research Institute (EPRI) to the NRC Chairman concerning the AP600 Advanced Reactor design.

RECOMMENDATION

.e <

1 1

435th ACRS Meeting 24 October 9-12, 1996 The Subcommittee recommended that Senior Staff Engineers or Fellows be assigned to review the transcripts and documentation pertaining to the two j issues raised in the EPRI letter and provide a 1 report at the November 1996 meeting.

D. Future Meetina Acenda Appendix IV summarizes the proposed items endorsed by the i Committee for the 436th ACRS Meeting, November 7-9, 1996.

Proposed Rule on Steam Generator Intecrity (Open) - The Committee will hear presentations by and hold discussions j with representatives of the NRC staff, Nuclear Energy l

, Institute (NEI), and EPRI regarding the proposed rule on  ;

steam generator integrity and an associated regulatory guide.

Other interested parties will participate, as appropri-ate.

Risk-Based Analysis of Reactor Operatina Exoerience (Open) - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the staff activities associated with risk-based analysis of reactor operating experience, including the i accident sequence precursor program, development of risk- '

based performance indicators, common cause failures, and related matters.

Representatives of the nuclear industry will participate, as appropriate.

Revised Source Term for Ooeratinc Reactors (Open) - The

. Committee will hear presentations by and hold discussions with representatives of the NRC staff, NEI, and Entergy operations, Inc. , regarding the use of the revised source term for operating plants and the NRC staff's proposed approach for reviewing applications for license amend-ments.

Other interested parties will participate, as appropri-ate.

Emeroency Plannino for Advanced Reactors (Open) -

The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding a simplified approach to emergency planning for advanced reactors.

g , b

E 435th ACRS Meeting 25 October 9-12, 1996-Representatives of the nuclear industry will participate, as appropriate.

Report of' the Plannina and Procedures Subcommittee (Open/ Closed) - The Committee will hear a report of the Planning and Procedures Subcommittee on matters related to the' conduct of ACRS business, and organizational and personnel-matters relating to ACRS.

A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules.and practices ci this Advisory - Committee, and matters the release of which would constitute a clearly unwarranted invasion of personal privacy.

Nitrocen Bubble in the Reactor Coolant System at the Haddam Neck Nuclear Power Plant (Open) - The Committee will hear presentations by and- hold discussions with representatives of the-NRC staff regarding the findings and conclusions of the Augmented Inspection Team which investigated the August 28, 1996 event at the Haddam Neck Nuclear Power Piant involving the inadvertant formation-of a nitrogen bubble in the reactor coolant system.

Representatives of the licensee Will participate, as appropriate.

.The 435th ACRS meeting was adjourned at 1:30 p.m. on Saturday, October 12, 1996.

(

i

Federd Register / Vd, 61,N.kb hedn:sday, Sept;mber 25, 1996 / Notices 50337

% 1 1

License Renewal Rule end Guidanca N:tional Academy cf Sciences / National reports, including thi EDO response to thi Development Overview Rcsearch Council (NAS/NRCl in the Phase 1 August 15,1996 ACRS report on SECY

• Draft Regulatory Guide and Industry study, status of the Phase 2 study, and the 128," Policy and Key Technical issues Guideline Content ACNS views on the use of digital pertaining to the Westinghouse AP600 License Renewal Demonstration instrumentation and control systems. Standardized Passive Reactor Design."

P 4:1 P m.-5:00 p.m.: Miscellaneous Matters 4:00 p.m.-7:00 p.m.:Prepantion of ACRS NRbem Overview (Open)-The ACRS and ACNS will discuss Reports (OpenHThe Committee will discuss ssons-learned j industry Lessons. Learned miscellane us ssues, including ALARA, proposed ACRS reports on matters '

c st-benefit considerations, safety culture. considered during this meeting as well as a Comments and Questions C' Summary and Conclusions proposed ACRS report on the suitability of

'Ihursday' Odober 10,1996 the NRC SCDAP/RELAPS Code to predict Dated at Rockville, Maryland, this 18th day temperatures and flows in steam genentors of September 1996. 8 30 a.m.-8:45 a.m.: Opening Remarks by during severe accidents.

For the Nuclear Regulatory Commission. the ACHS Gahr (Open)-The ACRS Chairman will make o ning remarks Friday October 11,1996 St*Ph en T. Man, regarding conduct of t meeting and '

Senior Project Manager, License Renewal 8 J 0 a.m.-8 25 a.m.: Opening Remarks by comment briefly regarding items of current the ACRS Chairman (OpenHThe ACRS l Project Directomie, Division ofReactor laterest. During this session, the Committee Chairman will make opening remarks l Progmrn Management, Office of Nuclear will discuss priorities for preparation of '

regarding conduct of the meeting.

Reactor Regulatson, U.S. NuclearRegulatory ACRS reposts-Commission. 825 a.m.-1030 a.m.: Activities Associated 8:45 a.m.-10:15 a.m.: Status ofNRC with the NRC Thermal Hydmulic Codes (FR Doc. 96-24412 Filed 9-24-96; 8:45 aml Stmfegic Assessment and Rebaselining Effort (Open)-The Committee will hear aume coos rees.w (OpenHThe Committee will hear a presentations by and hold discussions with presentation by and hold discussions with representatives of the NRC staff regarding the the Deputy Executive Director for Nuclear staff activities associated with the NRC l Advisory Committee on Reactor Reactor Regulation. Regional Operations and thermal hydraulic codes.  !

Research regarding the status of the NRC Representatives of the nuclear industry Safeguards; Hooting Notice strategic assessment and rebaselining effort. will participate, as appropriate.

In accordance with the purposes of 1030 a.m.-12:00 Noon: Digital 10:45 a.m.-t 1.D0 a.m.: Report by the Sections 29 and 182b. of the Atomic Instrumentation and Control Systems Human Factors Subcommittee Chairman Energy Act (42 U.S.C. 2039,2232b), the (Open)-The Committee will hear (OpenHThe Committee will hear a report by Presentations by and hold discussions with the Chainnan of the Human Factors Advisory Committee on Reactor representatives of the NRC staff regarding the Subcommittee regarding matters discussed Safeguards wtli hold a meeting on proposed Standard Review Plan Sections and during the September 20,1996 Subcommittee Octooer 9-12,1996, in Conference Branch Technical Positions usociated with meeting.

l Room T-2B3,11545 Rockville Pike, the digital instrumentation and control 11:00 a.m. *2:00 Noon: Preparation of  !

Rockville, Maryland. The date of this systems. ACRS Reports (OpenHThe Committee will meeting was previously published in Representatives of the nuclear industry discuss proposed ACRS reports on matters the Federal Register on Monday, will participate, as appropriate. considerad during this meeting as well as the November 27,1995 (60 FR 58393). 2 2 P m.-2;Jo p.m.: Control Room Back. report on the suitability of the NRC SCDAP/

Panel fire at Polo Verde Unit 2 (Open)-The REl.APS Code to pmdict temperatures and Wednesday, October 9,1996 Committee will bear presentations by and flows in steam generators during severe 8Jo a.m.-8:35 a.m.: Opening Remarks by hold discussions with representatives of the accidents. l the ACRS Chairman (Open>The ACRS NRC staff regarding the findings and 2:30 p m.-7.00 p.m.: Preparation of ACRS 1 Chairman will make opening remarks recommendations resulting from the Reports (Open)-The Committee will regarding conduct of the meeting. investigation of the April 4,1996 event that continue discussion of the proposed ACRS 8:35 a.m.-9 00 a.m.: Introduction (Openp involved two related fires in a back panel of reports on matters considered during this The ACRS Chairman willintroduce the the main control room of Palo Verde Unit 2. meeting as well as the other report noted ACRS Members to the Canadian Advisory . Representatives of the licensee will above.

Committee on Nuclear Safety (ACNS) and the participate, as appropriate.

ACNS Chairman willintroduce the ACNS 2:30 p.m.-J.W p.m.: Report of the Planning Saturday, October 1L 1M6 Members to the ACRS. Both Committees will and Procedures Subcommittee (Openf 8:30 a.m.-12:30 a.m.: Preparation of ACRS l discuss ACRS and ACNS missions, ClosedHThe Committee will hear a report of Reports (OpenHThe Committee will l regulatory environments, process / products, the Planning and Procedures Subcommittee continue discussion of proposed ACRS interactions, and independence. on matters related to the conduct of ACRS reports on matters considered during this l 9.00 a.m -11:JO a.m.: Risk-Informed and business, and organizationa.1 and personnel meeting. '

Performance Based Regulations (Open)--The matters relatiq w ACRA 11:45 a.m.-t:30 p.m.: Stmtegic Planning ACRS and ACNS will discuss prescriptive vs A portion cf tMs session may be closed to (OpenHThe Committee will continue its performance-based regulation, PRA methods discuss organizational and personnel matters discussion of items of significant importance and completeness, and defense-in-depth. that relate solely to the internal personnel to NRC, including rebaselining of the

! 00 p.m.-2:J5 p m.: Plant Aging (Openh rules and practices of this Advisory Cornmittee activities for FY 97.

The ACRS and ACNS will discuss issues Committee, and matters the release of which Procedures for the conduct of and associated with plant aging. would constitute a clearly unwarranted participation in ACRS meetings were 2:15 p.m.-J 00 p.m.: Operator Training / invasion of personal privacy. published in the Federal Register on Simulator Use(OpenHThe ACRS and ACNS 3.00 p.m.-3 30 p.m.: Future ACRS September 27,1995 (60 FR 49925). In will discuss the training of nuclear power Activities (Open)-The Committee will accordance with these procedures. oral or plant operators and the use of simulators for discuss recommendations of the Planning written statements rney be presented by training operators and other plant personnel. and Procedures Subcommittee regarding members of the public, electronic rwordings 3:f 5 p.m -4:25 p m.: Digital items proposed for consideration by the full will be permitted only during the open Instrumentation and Control Systems Committee during future meetings. portions of the meeting, and questions may (Open).--The ACRS and ACNS will discuss 3:45 p.m.-400 p.m : Reconciliation of t>e asked only by members of the Committee, the proposed Standard Review Plan Sections, ACRS Comments and Recommendations its consultants, and staff. Persons desiring to I Branch Technical Positions, and Regulatory (OpenHThe Committee will discuss make oral statements should notify Mr. Sam Cuides associated with digital responses from the NRC Executive Director Duraiswamy, Chief, Nuclear Reactors Branch.

instrumentation and control systems. They for Operations (EDO) to comments and at least five days before the meeting. if will also discuss the issues identified by the recommendations included in recent ACRS , possible, so that appropriate arrangements g

'A_ s

. .. 1

., 50938 Federal Register / Vol. 61, No.187 / WcAnsday, Sept:mber 25,1996 / N: tic:s can be made to cllow the nomesary time hoeday, Ocseber 7,1996-2:39 pm. Until Week of October 7-Tatathe s ,

(" during b mmting for such statements. Use of still, motion picture, and television cameras during this meeting may be limited 3:30 pm, The Suber.c@ oe will discuss proposed Monday Ocmkr 7 2 00 pm.-Briefing on Site Decommissioning ACRS activities and related matte s. It may Management Plan (SDMP)(Public

. ected po a emuu also discuss & quellScations of randidates

, Matinel(Contact: Mike Webber 301-re,a, ding h u. . be es, asa. fm sis ~ PP ~ ~ u ~ ^cns ~ a ~ n-purpose may be obtained by contacting t' ., this mwting is L gathe inimmahn, analyM Wedr#,de* setotper 9 relevant laeues and facts, and to foaulate Chief of the Nuclear Reactors Branch prica %, 1M : m.-Affirmation Session (Public the meeting. In view of the possibility the, PfDPoad P ositions and actions, as ,.y gg ,,gg),

the schedule for ACRS meetings may be 8PPropriate, for deliberstion by the full adjusted try the Chairman as necessary to Committee. M g Mr WTentoh facilitate ab conduct of the muting, persons Oral statements may be presented by Tuesoey October 15 planning to attend should check with the members of b public with the concurrence 1:00 pm.-Briefing by Executive Branch Chisf af the Nuclear Reactors Branch if such of the Suhmmmittee Chairman; written (Clood-Ex.1).

reacheduling would re, ult in me}or statements will be acoepted and made  !

taconvenience. ,, availe.ble to the mmmittee. Electronic Wednesda7' October 16  !

In acmrdance with Subsection 10(d) P.L mordings will be permitted only during 9:00 am.-Briefing on Containment 1 92-463,I have detennined that it is necosen thw portic"1s of the mating that are op.a Degradation (Public Meetini,). j to clow portions of this meetina nowd loove to the public, and questione may.be asked 2:00 p.m.-Briefing PRA Implementation i to discuss metters that inste solely to f.he only by members of the submmmittee, its Plan (Public Meeting).

internal personnel rules and practices cO,!* apnsultants, and etc5. Persons desiring to 3:30 p.m.-Affirms on Session (Public Advisory Committw per 5 U.S.C 552b(c)(2), make oral statements should notify the i and to discuss matters the release of which cognizant ACRS staff person named below Friday, Octobe 18 l would constitute a clearly unwarranted Sve deys prior to the meeting, if poselble, so 9:00 am.-Briefing on Integrated Mvv invasion of personal privscy per 5 U.S.C. that aj.propriate arrangements can be made. Assasement Team inspection (ISAT) at 552b(c)(6). Further information regarding topics to be Maine Yankee (Public Meetizd I

Further information regarding topics to be discussed, tue scheduling of sessions open to The Schedule for Commissior, Meetings ;s I discussed, whetkr the meeting has been the public, whether the mer ting has been Subjact to Change on Short Notic. To Verify cancelled or reocheduled, the Chairman's cancelld a ruchduld, e Chairman's b Status of Meetina Cul (h.:ording)-.-001) ruling on requmts for the opportunity to ruling on requests for b opportunity ta 415-1292. Cootect P. aeon for More present oral staternents and the time allotted 'uormou n: Bill Hill (301) 415-1661.

present oral statemente, and the time alloGed therefor can be obtained by contacting W. * * * *

• Sam Duraiswamy, Chief Nuclear 1%ctors eerek can Mubd WW ee Branch (telephone 301/415-7364, betwun engnizant ACRS staff person, Dr. John T. The NRC Commission Meeting Schedta 1,orkins (telephone:301/415-7360) between can be found on & Internet at: http://

7:30 am. and 4:15 pm. eat www.nrc. gov /SECY/sml/sched ule.htm ACRS meeting noticas, rsectf og transcripts, 7:30 a.m. and 4:15 p m. IEnT). Persons 3

plannbg to atund this meeng are urgd to This notice is distributed by mail to several contact the abcrve named individual one or un oYd th U. roos ve t w Id 1 to be a7ded o

• Dtreet Dial Acceu number to FedWorld is two working days prior to the inseting to be (soo) 303-9672; the local direct dial number advised n any changes in schedule, etc, dat ple mnw & OHW *% hw Attn: Operst!ans Branch, Washington. D.C is 703-321-3339. sp 5.re occurnd.

20555(301-415-1661).

l Deted: September 19,1996.  : SePurnber 18,1996. In addition, distribution of this meeting l

AMsow 1. h' f*ase Darstewsmy, notice over the internet system is evallable.

Chie,f , Nuef,,, Reactors Brunch. If you are interated in receiving this Advisory Cornmittee Mar . ament Officer. Commission meeting achedula electronically, (FR Doc. 96-24558 Filed 9- t 96; 8.45 aml IFR Doc. 96-24559 Filed 9-24-96; a:45 ami pleam send an electronic menage to museo coes rosa.es-, au.seo caos Foss-et-P wmhenrc. gov or dkwenrc. gov.

Deted: September 20,1996.

AOVIS0ry Committee On Reector SODSNne Act Meeting Williams M. Hill, Jr.,

Safeguards Subcommittee Meeting on SECT Trockfiig Officer, Office of the Planning and Procedursel Notice of AGENCY HOLDes0 THE h0EETW80: Nuclear 3,,,,,,,y, 09 * '

lFR Doc. 96-24693 Filed 9-23-96; 11:09 aml DATE: Weeks of Septembe- 23,30, aumo oces roops.as The ACRS Subcommittee on PlanninF October 7. and 14,18%. ,

and Procedures will hold a meeting on 4 October 8,1996, Room T-2B1,11545 Pl. ace:Chmmirloners' Conference '

Rockville Pike, Rockville, Maryland. Room,11r55 T.ockville Pike, Rockville, NUCLEAR REGULATORY l COMRSSSION The entire meeting will be open to M*'7 and.

public attendance, with the exception of status:Public and Closed. Blwookly Notice a portion that may be closed ursuant t) 5 U.S.C. 552b(c) (2) and (6ftoasATTERg discuss TO BE CON 88DERED: Applications and Amendments to otyanizational and personnel matters *Cilit7 Pneting Licenws lavolving Week of 3*P888'iber:3 No Significant Hazanis Considerations that relate solely to internal personnel l - rules and practices of ACRS, and nem am no nnemngs scheduld fw ee i

Week of September 23. 1. Background

. matters the release of which would constitute a clearly unwarranted Week of September 30-Tentott" Pursuant to Public Law 97-415 the U.S. Nuclear Regulatory Commission

( invasion of persons.1 privacy.

The agenda for the sub)ect meeting Thuredey, October 3 1:00 p.m.-A!!irmation Session (Public (the Commission or NRC staff)is publishing this regular biweekly notice.

. hall be as follows: Meetina)(if needed). Public Law 97-415 revised section 189 1

, APPENDIX II

. sce:u o,, ilNITED STATES

{  ! n NUCLEAR H5GULATORY COMMISSION l

l

~

$ I "

ADVISORY CMMi."!-?E ON REACTOR SAFEGUARDS 0 WA DUNGTON, D. C. 20555 September 19, 1996 SCREDULE AND OUTLINE FOR DISCUSSION 435th ACRS hE: TING OCTOBER 9-12, 1996 WEDNESDAY, OCTOBER 9, 1996. CONFERENCE ROOM 7,B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND J' +o J

1) 8:31r --

8:36 A.M. Qpgline Remrds by thy. ACRS Chairman (Open) 1.1) Opeping Stateme.nt (Kress/Larkins/

oc aiswamy) 40 3

2) 8:35 -

9:00 A.M. Introduction (Ope.0 ) (Kress/Pearson/Larkins) 2.1) Introductioc of ACRS Members 2.2) Introduction ef the Members of the Canadian Adviso q Committ.ee on Nuclear Safety (ACNS) 2.3) Discussion of ACRS and ACNS missions, regulatory environments, process /

products, interactions, and indepen- i dence 1 3 1:SS' -

3) 9 : 0 5 - H--so A . M . Risk-Informed. Performance-Based Reculation ,

35 go (Open) (Apostolakis/Powars/ Rogers / )

(10 : 0:0 - 10 : I:s A . M . BREAK)

Markley) -

3.1) Prescriptive vs Performance-based regulation 3.2) PRA Methods and Completeness 3.3) Defense-in-Depth 5

11:30 - 1:00 P.M. LUNCH 3:oo

4) 1:bs -

2:28 P . M . Plant Acina (Open) (Shack /Biron/Dudley) 4.1) Discussion of issues associated with plant aging 3:2o y*:

5) W - .t d>0SP.M. Operator Traininc/ Simulator Use (Open)

(Seale/Natalizio/Boehnert) 5.1) Discussion of training of nuclear power plant operators, and use of simulators for training operators and other plant personnel N

TR AVSc RlBe b ?o RTiOV S OF N HEE 7/NC

[

\; -

2 1 l

-3 00 - 3:15 7.M. BREAK

/

1 4 6: 00 i

! 6) 3:15 - **t6 P.M. Diaital Instrumentation and Control Systems I j (Open) (Miller /Pearson/Markley/Singh) l

6.1) Discussion of proposed Standard Re- l l view Plan Sections, Branch Technical 1 1 Positions, and Regulatory Guides l

associated with the digital instru- .

] nantatio- and control systems l i , 6.2) Discuszion of the issues identified

by ths National Academy of i Sciences / National Research Council

(NAS/NRC) in the Phase 1 study, sta-j tur, of the Phase 2 study, and ACNS

! views on the use of digital instru-

i. mentation and control systems.

i ' S:co  ?

7) **36 - J:eo P.M. Miscellaneous Matters (open) (Kress/Pearson/

Robertson/El-Zeftawy)

7.1) Discussion of miscellaneous issues, including ALARA, cost-benefit consid-

erations, safety culture, etc.

N 8

TEURSDAY, OCTOBER 10, 1996. CONFERENCE ROOM 2B3, TWO WEITE FLINT NORTE, i ROCIVILLE, MhRYLAMD

,/

8) 8:3h - 8:45 A.M. Onenina Remarks by the ACRS Chairman (Open) 4 8.1) Opening Statement (TSK/SD) 8.2) Items of current interest (TSK/JTL/SD) l 8.3) Priorities for preparation of ACRS reports (TSK/SD)

// : 01

9) 8:45 - 10:46 A.M. Status of NRC Stratecic Assessment and Rebaselinina Effort (Open) (TSK/MME) 9.1) Remarks by thm ACRS Chaizzan 9.2) Briefing by and, discussions with the Deputy Execut. " Director for Nuclear Reactor Regulation, Regional Opera-tions and Research, regarding the status of the NRC strategic assess-ment and rebaselining effort.

y o1 //:17  %

14sts - 10+90 A.M. LAUX

i 3

? II : 1 G' W ~ '

i 10) 19w40 - 12:06 Noen Dicital Instrumentation and Control Systemg '

l (Open) (DWM/MTM) 10.1) Remarks by the Subcommittee Chairman l 10.2) Briefing by and discussions with representatives of the NRC staff regarding the proposed Standard l Review Plan Sections and Branch Tech- '

nical Positions associated with the j digital instrumentation and control  !

. systems, l

Representatives of the nuclear industry will participate, as appropriate.

12:N - 1:M P.x. tuxCa to I : 65~ \

11) 1:00 - M P.M. Control Room Back-Panel Fire at Palo Verde Unit 2 (Open) (JJB/AS) l 11.1) Remarks by the Subcommittee Chairman )

11.2) Briefing by and discussions with )

representatives of the NRC staff <

regarding the findin s i and recommen-dations resultizg from the investiga- i tion of the April 4, 1996 event that involved two related fires in a back panel of the main coIntrol room of i Palo Verde Nuclear Power Plant, i Unit 2. i Representatives of the licensee will participate, as appropriate.

12) 2:30 - 3:90 P.M. Recort of the Planninc and Procedures Subcommitifgg (Open/ Closed) (TSK/JTL)

Report of the Planning and Procedures subcommittee on matters related to the conduct of ACRS business, 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 matters the release of which would constitute a clearly unwarranted invasion of personal privacy.)

~

4 2 1

13) 4: 00 - 3:30 P.M. Future ACRS Activities (Open) (TSK/SD)

Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.

Io 26 3:30 -

3:46 P.M. BREAK

14) bbbh 'k:00 P.M. Reconciliation of ACRS Comments and Recommendations (TSK, et.al./SD, et al.)

Discussion of the responses from the NRC 3

Executive Director for Operations to comments and recommendations included in recent ACRS reports.

3: 25 L: 53

15) W- " Ares P . M . Precaration of ACRS Reoorts (Open)

Discussion of proposed ACRS reports on:

15.1) Suitability of the NRC SCDAP/RELAPS Code to Predict Temperatures and Flows in Steam Generators During Severe Accidents (MHF/NFD) 15.2) Digital Instrumentation and Control Systems (DWM/MTM)

FRIDAY, OCTOBER 11, 1996, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

) 16) 8:30 - 8:35 A.M. Ocenino Remarks by the ACRS Chairman (Open)

(TSK/SD)

17) 8:35 - 10:3hA.M. Activities Associated with the NRC Thermal Hydraulic Codes (Open) (IC/PAB) 17.1) Remarks by the Subcommittee Chairman 17.2) Briefing by and discussions with representatives of the NRC staff regarding the staff activities asso-ciated with the NRC thermal hydraulic codes.

Representatives of the nuclear industry will participate, as appropriate.

1 10:3f-10:45A.M. BREAK

. . -- . . - - _ ~ . ~ ~ -

j

.'v -

5 -

18) 10:45 - 11:00 A.M. Recort by the Actina Chairman of the Human l Factors Subcommittee (Open) (RLS/NFD)

L '

Report by the Acting Chairman of the Human Factors Subcommittee regarding matters discussed during the September 20, 1996 Subcommittee meeting.

19) 11:00 -12:00 Noon Precaration of ACRS Reoorts (Op'en)

. Discussion of proposed ACRS reports on:

19.1) NRC Thermal Hydraulic Codes (IC/PAB) 19.2) Suitability of SCDAP/RELAP5 Code to

,. Predict. Temperatures and Flows in l Steam Generators During Severe Acci- l

dents (MHF/NFD) t l 19.3) Digital Instrumentation and Control Systems (DWM/MTM)

• 12:00 - 2:30 P.M. LUMCE  !

L:sr

20) 2:30 -  %=44 P . M . . Precaration of ACRS Reoorts (Open) l (3 :30-3 :45 P.M. BREAK) Discussion of proposed ACRS reports on:

20.1) NRC Thermal Hydraulic Codes (IC/PAB) 20.2) Suitability of SCDAP/RELAP5 Code to Predict Temperatures and Flows in Steam Generators During Severe Acci-dents (MHF/NFD) 20.3) Digital Instrumentation and Control Systems (DWM/MTM)

SATURDAY, OCTOBER 12, 1996, CONFERENCE ROOM 2B3, TWO NEITE FLIhT NORTE, ROCKVILLE, MARYLAND

21) 8:30 - 11:30 A.M. Precaration of ACRS Recorts (Open)

Continue discussion of proposed ACRS reports listed under Item 20 1

13 : 3 0 - 11: 45 A.M. BREAK

' 22) 11:45 - 1:30 P.M. Stratecic Plannina (Open) (TSK/JTL)

Discussion of items of significant importance to NRC, including rebaselining of the Committee activities for FY 97  ;

1 1 I

i

. ~ . . _ . ~ . . . . . . - . . . . . - . _ . - - . . - . . - - - - . . . . . . - - - . . - . - . - . - . - . - . . ,

~..... .

, s.

. j

~

, APPENDIX III: MEETING ATTENDEES

)' -435TH ACRS MEETING October 9-12, 1996 i

t'  !

-NRC STAFF

^

i I

C. Bajwa- NRR D. Bessette RES 1 l S. Black NRR i j' B. Boger NRR i

.R.-Brill RES j S. Campbell Reg.IV i R. Caruso NRR 2

. M.: Case NRR

A. Chaffee NRR

' M. Chiramal NRR 1 1

J..Clifford NRR C. Defino NMSS.

) - B. Dennig NRR T. Eaton NRR D. Edert' NRR F. Etawila RES

-'J . Funches. OC J. Gallagner' NRR T. Hiltz NRR C. Hinson NRR W. Hodges RES .l'

.E. Holahan, RES C. Holden NRR R~..Jenkins NRR  ;

M.' Johnson -NRR '

N. Kececi NRR J. . Kelly RES T.-King- RES T. Koshy NRR M. .Kotzalas NRR J. Kramer RES t R.-Kursch AEDO M. Knapp- NMSS C. Lauran NRR T. Lee RES P. Madden NRR S. Malik RES J.'Mauch NRR G. McPherson NRR R. Meyer RES J. Milhoan DEDR V. Mousseau RES F. Odar RES J. Persensky RES P. Qualls Reg.IV C. Regan NRR J. Rosenthal AEOD

> .~. . . _ .. . _ _ _ . _ _ _ _ _ . . _ _ _._ ... _ .._ _ . _.. _ _ . _ _ _ _._ _ _

i =

fL 1

i i . Appendix III 2 ,

7 435th ACRS Meeting l r

- M. Rubin RES ,

H. Scott RES

?

S. Smith ^ RES ,

! J. Tappert NRR '

i G. Uyeda RES J. Vora- RES  :

J. Wermiel NRR ,

' ' S. West NRR l s

ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC L. Allenbach . Arthur Anderson  !

A. Carson Bechtel l S. Crawford SAIC  ;

L. Enscand EOI

S. Floyd NEI

H. Fontealk VA Power F. Garrett APS - Palo Verde i- M. Gvace Winston & Strawn j J. Holmes APS - Palo Verde i- G. Johnson LLNL

• i L. Jordan U.S. Senate - Environment Committee l S. Katradis SCIENTECH

E. Kleinsorg Duke Engineering & Services A._Murrary ANSTO P. Negus GE j

H. Renner SCIENTECH <

I M. Stand SCIENTECH l

. T. Sutter- Bechtel N. Turley APS - Palo Verde j A. Wyche SERCH Licencing /Bechtel

, T. Zama TEPCO 1

+

4 l

m . ,, e , .e

APPENDIX IV: FUTURE AGENDA The Committee agreed to consider the following during the 436th ACRS Meeting, November 7-9, 1996:

THURSDAY, NOVEMBER 7, 1996. CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

1) 8:30 - 8:45 A.M. Openino Remarks by the ACRS Chairman (open) 1.1) Opening Statement (TSK/SD) 1.2) Items of current interest (TSK/JTL/SD) 1.3) Priorities for preparation of ACRS reports (TSK/SD)

2) 8:45 - 10:45 A.M. Proposed Rule on Steam Generator Inteority (Open) (RLS/NFD) 2.1) Remarks by the Acting Subcommittee Chairman 2.2) Briefing by and discussions with repre-sentatives of the NRC staff, Nuclear Energy Institute (NEI) and Electric Power Research Institute (EPRI) regarding the proposed rule-on steam generator integrity and an associated regulatory guide.

Other interested parties will participate, as appropriate.

l 10:45 - 11:00 A.M. BREAK j

3) 11:00 - 12:15 P.M. Risk-Based Analysis of Reactor Operatina Exoerience (Open) (GA/MTM) 3.1) Remarks by the Subcommittee Chairman 3.2) Briefing by and discussions with representatives of the NRC staf f regarding the staff activities associated with risk-based analysis of reactor operating experience, accident sequence precursor program, development of risk-based performance indicators, and rela;ed matters.

Representatives of the nuclear industry will participate, as appropriate.

12:15 - 1:15 P.M. LUNCH

4) 1:15 - 3:15 P.M. Revised Source Term for Operatino Reactors (Open) (MHF/AS) i

Appendix IV 2 418th ACRS Meeting 4.1) Remarks by the Subcommittee Chairman 4.2) Briefing by and discussions with representatives of the NRC staff, NEI, and Entergy Operations Inc., regarding the use of revised source term for operating plants and the NRC staff's proposed approach for review-it.g applications for license amendments. l 1

Other interested parties will participate, as i appropriate.

i l

3:15 - 3:30 P.M. BREAK I i

l

5) 3:30 - 4:30 P.M. Emeroency Planninc for Advanced Reactors (Open) (RLS/MME) 5.1) Remarks by the Subcommittee Chairman 5.2) Briefing by and discussions with  ;

representatives of the NRC staff regarding a ]

simplified approach to emergency planning for advanced reactors.

Representatives of the nuclear industry will ,

participate, as appropriate. '

l

6) 4:30 - 7:00 P.M. Preparation of ACRS Reoorts (Open) l Discussion of proposed ACRS reports on: '

6.1) Proposed Rule on Steam Generator Integrity and an associated Regulatory Guide (RLS/NFD) 6.2) Risk-Based Analysis of Reactor .

Operating Experience (GA/MTM) 6.3) Revised Source Term for Operating Reactors  ;

(MHF/AS)  !

6.4) Plant-Specific Application of Safety Goals 1 (ISK/NFD)

FRIDAY, NOVEMBER 8, 1996, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

7) 8:30 - 8:35 A.M. Openina Remarks by the ACRS Chairman (open) .

(TSK/SD) l l

8) 8:35 - 9:00 A.M. Future ACRS Activities (Open) (TSK/SD)

\

. Appendix-IV 3 418th ACRS Meeting i I Discussion of the recommendations of the Planning

and Procedures Subcommittee

regarding items proposed for consideration by the i full Committee during future i l

a meetings'.  !

! 9) 9:00 - 9:15 A.M. Reconciliation of ACRS Comments and Recommendations (Open) (TSK, et.al./ l SD, et.al.)

. Discussion of the responses from the NRC Executive

! -Director for Operations to i comments and recommendations included in ,

3 recent ACRS reports.

R10) 9:15 - 9:45 A.M. Reoort of the Plannina and Procedures

• Subcommittee (Open/ Closed) (TSK/JTL).

Report of the Planning and Procedures 1 Subcommittee on matters related to

the conduct of ACRS. business, and  ;

organizational and personnel matters 5 relating to the ACRS.

t

[ Note: A portion of this session may be closed to discuss organizational and personnel matterG that relate solely to the internal person-nel rules and practices of this Advisory Committee, '

and matters the release of which would constitute a i clearly unwarranted invasion of personal privacy.]

I 9:45 - 10:00 A.M. BREAK I

11) 10:00 - 11:00 A.M. Nitrocen Bubble in the Reactor Coolant System at the Haddam Neck Nuclear Power Plant (Open) (JJB/PAB) 11.1) Remarks by the Subcommittee Chairman 11.2) Briefing by and discassions with representatives of the NRC staff regarding the findings and recommendations of the Augmented Inspection Team which in-vestigated the August 28, 1996 event at the '

j Haddam Neck Nuclear Power Plant that involved creation of a nitrogen bubble in the reactor coolant system.

Representatives of the licensees will i

I

s l

Appendix IV 4 418th ACRS Meeting

, participate, as appropriate.

12) 11:00 - 12:30 P.M. Annual ACRS Report to Congress (Open)

(RLS/MME)

Discussion of the format and content of the annual ACRS report to Congress on the NRC Safety Research Program.

l 12:30 -

1:30 P.M. LUNCH l

l

13) 1:30 - 7:00 P.M. Precaration of ACRS Reports (Open) )

(3:30-3:45 BREAK) Discussion of proposed ACRS reports on: i 13.1) Proposed Rule on Steam Generator l Integrity and an associated Regulatory Guide (RLS/NFD) 13.2) Risk-Based Analysis of Reactor Operating Experience (GA/MTM) 13.3) Revised Source Term for Operating ,

Reactors (MHF/AS) l 13.4) Plant-Specific Application of Safety j Goals (TSK/NFD) l SATURDAY, NOVEMBER 9, 1996. CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND l 1

1

14) 8:30 -

12:30 P.M. Preparation of ACRS Reports (Open) i Continue discussion of proposed ACRS l reports listed under Item 13.

15) 12:30 - 1:30 P.M. Strateoic Plannino (Open) (TSK/JTL)

Discussion of items of significant importance to NRC, including rebaselining of the Committee activities for FY 97 i

l 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.

.. . _ . _ . ~ _ _ . . . _ . _ . . . _ _ - ~ - - . _ _ . _ . _ _ . . . _ _ _ . . _ . _ _ _ . _ . _ _ . . _ . _ . . . _ _ _ _

, . - '. 1 APPENDIX V

-LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE 1 (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. <

2 Introduction

1. History of Advisory Groups at the Atomic Energy Control Board, presented by Dr. Albert Pearson, Chairman, ACNS, Canada '

[Viewgraphs) 3 Risk-Informed, Performance-Based l Reculation

'2. Advisory Committee on Reactor

, Safeguards Meeting - with Canadian Advisory . Committee on Nuclear Safety: Risk-Informed, Performance-Based Regulation, dated October 9, 1996, presented by Dr. G. Apostolakis (Viewgraphs)

3. Role of Risk in Nuclear Regulation in Canada, dated October 9, 1996, presented by J.T. Rogers, ACNS, Canada [Viewgraphs) 4 Plant Acino

4. Plant Aging, dated October 9, 1996, presented by Dr. William Shack (Viewgraphs)

5. Advisory Committee on Nuclear Safety, Working Group on Aging &

Backfitting, Interim Report, dated October 1996, presented by Andr6 Biron, ACNS, Canada [Viewgraphs]'

5 Operator Traininc/ Simulator Use

6. Utility Staff Training and l

Certification, Working Group 19 of

3 ..... .

l l

l . Appendix V 2 j 418th ACRS Meeting

! the Advisory Committee on Nuclear Safety, presented by Tony Natalizio, ACNS, Canada

[Viewgraphs) 6 Dicital Instrumentation & Control Systems

7. Digital Instrumentation & Control Systems, dated October 9, 1996, presented by Dr. Don W. Miller

[Viewgraphs)

8. Digital Computers in Nuclear Power Plant Control Systems, presented by' Dr. Albert Pearson, ACNS, Canada [Viewgraphs)

9. INPO CEO Conference, dated November 3, 1995, speech by Zack T. Pate [ Handout) 7 Miscellaneous Matters

10. ALARA/DE MINIMIS, presented by Dr.

Albert Pearson, ACNS, Canada 8 Openina Remarks by the ACRS Chairman

11. Items of Current Interest 9 Status of NRC Strateoic Assessment and Rebaselinina Effort

12. Status of NRC Strategic Assessment and Rebaselining Effort: Overview and Status Briefing, dated October 10, 1996, presented by John Craig, Task Manager, Strategic Assessment Coordination Task Group

[Viewgraphs) 10 Dicital Instrumentation and Control Systems

13. Update of Chapter 7: Standard Review Plan, dated October 10, 1996, presented by Matthew Chiramal, NRR [Viewgraphs]

11 Control Room Back-Panel Fire at Palo Verde

1 Appendix V 3 I 418th ACRS Meeting l Unit 2 ]

14. Palo . Verde Unit 2, Simultaneous Fires in Control Room and DC l Equipment Room, April 4, 1996,  ;

presented by Robert Dennig, NRR

[Viewgraphs) l 12 Reoort of the Plannina and Procedures Subcommittee  ;

i

15. Final Draft Minutes of Planning and Procedures Subcommittee Meeting - October 8, 1996 (Handout

1. 12.1]

l 13 Future ACRS Activities j

16. Future ACRS Activities -

436th ACRS Meeting, November 7-9, 1996 )

(Handout #13.1) 14 Reconciliation 'of ACRS Comments and ]

Recommendations

17. Reconciliation of ACRS Comments I and Recommendations (Handout

1. 13.1]

15 Precaration of ACRS Reoorts

18. Preparation of ACRS Reports:

Letter from Dr. Vishanta, Purdue University, to Dr. Khatib-Rahbar, Energy Research, Inc: SCDAP/RELAPS Code Modeling, dated September 11, ,

1996; and Memorandum from Dr.  !

Zuber, ACRS Consultant, to Dr.  !

Fontana, Severe Accident i Subcommittee ' Chairman: ACRS Meeting on Steam Generator Tube Temperatures, dated October 9, 1996 [ Handout #15.1]

17 Activities Associated with the NRC Thermal Hydraulic Codes

19. NRC-RES Thermal Hydraulic Research Program Plan: Reports of Dr. V.K.

Dhir, dated September 24, 1996,

. - - - . - . _ - . - - . . . . - . . - - . . . . .~..- . . - . - - . - . - . . - . . . . _ . - - . - - . . . _ -

t . ..

l l 9-i

- Appendix V 4 )

418th ACRS Meeting.  ;

l and comments of Dr. N. Zuber at the September 18-19, 1996, Thermal-Hydraulic Phenomena Subcommittee [ Handout #17-1]

20.- Thermal-Hydraulic Computer Codes -

A Regulator's Perspective, dated l October 11, 1996, presented by i Ralph Caruso, NRR [Viewgraphs) l 1

21. Thermal-Hydraulics Research Plan, ]

7 dated October 11, 1996, presented by Farouk Eltawila, RES ]

[Viewgraphs) '

18' Recort by the Actino Chairman ' of the Human Factors Subcommittee I j

l I

l

)

1 1

I

a s

.,,~s Appendix V 5 435th ACRS Meeting MEETING NOTEBOOK CONTENTS TAB DOCUMENTS 1 Introduction

1. Table of Contents

2. Proposed Schedule

3. Status Report, dated October 9, 1996

4. ACRS Membership List

5. ACRS Biographies

6. Advisory Committee on Nuclear Safety (ACNS) (Canada) Membership List

7. ACNS Biographies

8. NRC Organizational Chart: NUREG-0325, Pages 1 and 4

9. ACRS Charter

10. Atomic Energy Control Board (AECB)/ACNS Terms of Reference

11. Nuclear Safety article: " Canadian Approach to Nuclear Power Safety, a ,

by R. Atchison, F. Boyd, and Z. l Domaratzki, July-August 1983 2 Risk-Informed. Performance-Based Reculation

12. Table of Contents

13. Proposed Schedule

14. Status Report, dated October 9, 1996

15. Letter from J. Taylor, Executive Director for Operations (EDO), to T.S. Kress, Chairman, ACRS, dated September 6, 1996: Riek-Informed, Performance-Based Regulation and Related Matters

16. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairr. tan, ACRS, dated August 15, 1996: Risk-Informed, Performance-Based Regulation and Related Matters

17. Letter from J. Taylor, EDO, to T.S. Kress, Chairman, ACRS, dated July 18, 1996: Potential Use of IPE/IPEEE Results to Compare Risk

,; < , . .o Appendix V 6 435th ACRS Meeting of the Current Population of Plants with the Safety Goals

17. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairman, ACRS, dated June 6, 1996: Potential Use of IPE/IPEEE Results to Compare Risk of the Current Population of Plants with the Safety Goals '

18. Letter from Shirley Ann Jackson, Chairman, NRC, to T.S. Kress, Chairman, ACRS, dated June 3, 1996: ACRS Letter dated April 23, 1996, Regarding PRA Framework, Pilot Applications and Next Steps to Expand the Use of PRA in the Regulatory Decision-Making Process

19. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated April 23, 1996: PRA Framework, Pilot Applications and Next Steps to Expand the Use of PRA in the Regulatory Decision-Making Process

20. Memorandum from J. Taylor, EDO, to Shirley Ann Jackson, Chairman, NRC, dated January 3, 1996:

Improvements Associated with Managing the Utilization of Probabilistic Risk Assessment (PRA) and Digital Instrumentation 1

& Control Technology l

21. Memorandum from Shirley Ann Jackson, Chairman, NRC, to J.

Taylor, EDO, dated November 30, l 1995: Follow-Up Requests in  !

Probabilistic Risk Assessment and ,

Digital Instrumentation l 3 Plant Aoina

22. Table of Contents

23. Discussion Schedule

24. Status Report, dated October 9, 1996

25. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated June 16, 1995: Proposed Final Rule and Regulatory Guide for

. . . _. .. . . . ~ . . . - . _ _ - - - .-... - -. . . . . . . - - . - - . . .

c.*. . ,

l 1

l Appendix V .

7 435th ACRS Meeting Fracture Toughness Requirements for Light Water Reactor Pressure Vessels l 26. Letter from T.S. Kress, Chairman, l ARCS, to J. Taylor, EDO, dated l December 20, 1994: Proposed' Final Draft Regulatory Guide, DG-1023, l " Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf i Energy Less Than 50 FT-LB"

27. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated i March 14 ., 1996: Resolution of i Generic Safety Issue 78,

" Monitoring of Fracture Transient Limits for the Reactor Coolant System"

27. Report from T.S. Kress,. Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated October 16, 1995: Fatigue Action Plan

28. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated September 15, 1995: Development of Improved Nondestructive Examination (NDE) l Techniques  ;

29. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated May 15, 1995: Proposed Final Generic Letter 95-XX, " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes"

30. Report from T.S. Kress, Chairman, ACRS, to Ivan Selin, Chairman, NRC, dated September 12, 1994:

Proposed Final' Generic Letter 95-XX, " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes" 5 Operator Trainina/ Simulator Use

31. Table of Contents

32. Discussion Schedule

33. Status Report, dated October 9, 1996

34. Paper by F. Collins, NRC, undated:

" Optimizing the Nuclear Power

2 .

1 Appendix V 8  !

435th ACRS Meeting i Plant Simulator: A Regulatory I Perspective" l

35. Paper by K.A. Raglin, NRC, l' undated: "Use of Simulation for USNRC Staff Training"

36. Presentation Slides from Dr. C.L. '

Jen, Executive:Vice President, GSE Systems . Inc. : " Evolution of Real-Time Nuclear Power Plant Simulator Development

,i . 37. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated i February 22, 1996: Revision 2 to i

) Regulatory Guide 1.149, " Nuclear

- Power Plant Simulation Facilities for Use in Operator License Examinations"

38. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated December 15, 1994: NRC Technical

. Training Program

.39. Report from J. Ernest. Wilkins, Jr., Chairman, ACRS, to Ivan

Selin, Chairman, NRC, dated j October 14, 1993

Proposed Final  ;

Amendments to 10 CFR Part 55 on l Renewal of Licenses and

Requalification Requirements for l

! Licensed Operators 1

40. Letter from David A. Ward, i Chairman, ACRS,.to J. Taylor, EDO, i dated October 19, 1992: Proposed Amendments to 10 CFR Part 55 on Renewal of Nuclear Power Plant Operator Licenses and Requalification

41. Report from David A. Ward, Chairman, ACRS, to- Kenneth M.

! Carr, Chairman, NRC, dated March 12, 1991: Proposed -Rule on i

Selection, Training, and Qualification of Nuclear Power

Plant Personnel

'. 6 Diaital Instrumentation and Control Systems

42. Table of Contents

43. Proposed Schedule 6

f

._7 _ _ _ _ _

1, - -

l- Appendix V 9 435th ACRS Meeting i-

44. Status Report, dated October 9, )

1996

45. Letter from J. Tr.ylor, EDO, to T.S. Kress, Chairman, ACRS, dated' June 21, 1996: Regulatory ,

Guidance Documents Related to i

Digital Instrumentation and Control Systems

46. Letter from T.S. Kress, Chairman, ,

ARCS, to J. Taylor, EDO, dated  !

June 6,1996

Regulatory Guidance l Documents Related to Digital l Instrumentation and Control  !

Systems l

47. Letter from J. Taylor, EDO, to  ;

T.S. Kress, Chairman, ACRS, dated i October 31, 1995: The National Academy of Sciences' Report on Digital Instrumentation and Control, Safety and Reliability Iseues

48. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, 1 Chairman, NRC, dated October 13, j {

1995: National Academy of l Sciences / National Research Council I l Study on " Digital Instrumentation l and Control, Safety and Reliability Issues"-Phase 1

) 7 Miscellaneous Matters i

I

49. Table of Contents

50. Proposed Schedule 4 51. Status Report

52. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated July 20, 1995: Health Effects Valuation

, 53. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated September 13, 1995: Health Effects Valuation

54. Letter from Paul Shewmon, Chairman, ACRS, to J. Taylor, EDO, dated November 12, 1992, Revised Regulatory Analysis Guidelines

55. Report from T.S. Kress, Chairman, ACRS, to Ivan Selin, Chairman, j NRC, dated September 14, 1994:

d

s t ' AY Appendix V- 10 435th ACRS Meeting Revised Regulatory Analysis Guidelines 9 HLptus of NRC Stratecic Assessment and Rebaselinino Effort

56. Table of Contents

57. Proposed Schedule

58. Status Report 4

59. Memorandum from S. Duraiswamy to ACRS Members, dated September 23, 1996: Assignment for Reviewing of Issues Stemming from NRC Strategic Assessment and Rebaselining Initiative 10 Ricital Instrumentation and Control Systems

60. Table of Contents

61. Proposed Schedule

62. Status Report

63. Letter from J. Taylor, EDO, to T.S. Kress, Chairman, ACRS, dated June 21, 1996: Regulatory Guidance Documents Related to Digital Instrumentation and Control Systems

64. Letter from T.S. Kress, Chairman, ARCS, to J. Taylor, EDO, dated June 6, 1996: Regulatory Guidance Documents Related to Digital Instrumentation and Control Systems 11 Control Room Back-Panel Fire at Palo Verde Unit 2

65. Table of Contents

66. Proposed Schedule 4

67. Status Report 17 Activities Associated with the NRC Thermal Hydraulic Codes

68. Table of Contents

69. Presentation Schedule

70. Project Status Report

71. Memorandum from J. Taylor, EDO, to NRC Commissioners, dated September

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ki i Appendix V 11 435th ACRS Meeting-l 6, 1996: Thermal-Hydraulic Five-  !

Year Research Plan 1 l

72. Report from David A. Ward, Acting I Chairman, ACRS, to Lando W. Zech, I l Jr. , Chairman, NRC, dated June 15,  :

1989: NRC Thermal-Hydraulic Research Program ,

73. Report from David A. Ward, Acting l Chairman, ACRS, to Lando W. Zech, l Jr., Chairman, NRC, dated June 7, l 1988: NRC Research Related to Heat l Transfer and Fluid Transport in '

Nuclear Power Plants

74. Memorandum from P. Boehnert, ACRS ,

Senior Staff Engineer, to I. I Catton, Chairman, Thermal- l Hydraulic Phenomena Subcommittee, i dated June 3, 1996: NRC-RES Meeting: Thermal-Hydraulics /Neutronics Code Experts Group, May 20-21, 1996 -

Rockville, Maryland '

75. Letter from Dr. James A. Lake, i Manager, Advanced Nuclear Energy )

Products, Idaho National ]

Engineering Laboratory, to Dr. F. 4 Eltawila, NRR, dated March 8, 1995: Transmittal of Final Report: Long-Term Plan for NRC Thermal-Hydraulic Code Development, Glen A. Mortensen,

, March 1995 l

1

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