ML20206S683

Summary of 453rd ACRS Meeting on 980603-05 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda

ML20206S683
Person / Time
Site:	05200003
Issue date:	09/01/1998
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-3113, NUDOCS 9905210198
Download: ML20206S683 (47)

Text

7 q Date Issurd: 9/1/98 f SHS PDR l

TABLE OF CONTENTS MINUTES OF THE 453RD ACRS MEETING l

JUNE 3-5,1998  !

Page i

1. CHAIRMAN'S REPORT (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. AP6 00 (O pe n) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Ill. HUMAN PERFORMANCE PLAN (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 IV. CORE RESEARCH CAPABILITIES AT NRC (Open) . . . . . . . . . . . . . . . . . . . 4 l

V. BWR EXTENDED POWER UPRATE APPLICATION (Open) . . . . . . . . . . . . . 6 VI. AGENCY-WIDE PLAN FOR HIGH-BURNUP FUEL (Open) ... ......... 7 Vll. OPERATING PLAN FOR THE NRC TECHNICAL TRAINING P R OG RAM S (Ope n) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Vill. PROPOSED MODIFICATIONS TO 10 CFR 50.59. CHANGES. l TESTS. AND EXPERIMENTS (Open) . . . . . . . . . . . . . . . . . . . . . . . ......11 )

IX. PROPOSED FINAL STANDARD REVIEW PLAN (SRP) SECTION AND REGULATORY GUIDE FOR RISK-INFORMED INSERVICE INSPECTION OF PIPING (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 X. EXECUTIVE SESSION (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

'D y A. Reports, Letters, and Memoranda gS)C\

REPORTS C4 .0m t l

l

. Prooosed Final Draft of the NRC's Human Performance Plan r'-(T4 -

(Report to Shirley Ann Jackson, Chairman, NRC, from R. L.

'[ e J 0,} Seale, Chairman, ACRS, dated June 12,1998.)

9905210198 900901 ~ DgsIGNATr.D ORIGINAL '-

PDR ACRS 3113 PDR .

certified By -

Proposed Final Standard Review Plan Section 3.9.8 and

- Reaulatorv Guide 1.178 for Risk-informed Inservice insoection of Pinina (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 12,1998.)

The Safety Asoects of the Westinahouse Electric Comoany Aeolication for Certification of the AP600 Plant Dasion - Interim i Letter 3 (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 15,1998.)

+

NRC Reactor Fuels Research Proaram (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 15,1998.)

Review of SECY-98-076. " Core Ramaarch Canabilities"(Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dsted June 16,1998.)

Review and Evaluation of the Nuciaer Reaulatorv Commission Safety Research Proaram (Letter to Shirley Ann Jackson,  !

Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 24,1998, transmitting an advance copy of NUREG-1635,  ;

Volume 1, Review and Evaluation of the NRC Safety Research  !'

Program)

LETTER NRC Particioation in the CABRI Reedor Fuels Research Proaram (Letter to L. Joseph Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated June 9,1998) '

MEMORANDA ,

. Draft Advance Notice of Proposed Rulemakina Reaardina Amendina 10 CFR 50.72. "Immediate Notification Require-ments for Operatina Nuclear Power Reactors." and 10 CFR 50.73. " Licensee Event Reoort System" (Memorandum to L. l Joseph Callan, Executive Director for Operations, NRC, from '

John T. Larkins, Executive Director, ACRS, dated June 9, 1998) 1 ii I

1 J

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Safetv Evaluation Reoort on Electric Power Remaarch Institute Toolcal Report. TR-107330. Final Report. " Generic Reauire- .

ments Soecification for Qualifyina a Commercially Available PLC for Safetv-Related Anolications in Nuciaer Power Plants."

(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated June 9,1998)

B. Reconciliation of ACRS Comments and Recommen- I dations i

C. Report on the Meeting of the Planning and Procedures Subcommittee Held on June 2,1998 (Open)

D. Future Meeting Agenda iii l l

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I 1.

APPENDICES I. Federal Register Notice

11. Meeting Schedule and Outline l 111. Attendees i IV. Future Agenda and Subcommittee ^ctivities V. List of Documents Provided to the Committee 1

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' MINUTES OF THE FOUR HUNDRED FIFTY-THIRD MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS JUNE 3-5,1998 ROCKVILLE, MARYLAND The 453rd meeting of the Advisory Committee on Reactor Safeguards was held in Conference Room 283, Two White Flint North Building, Rockvhle, Mayland, on June 3-5, 1998. 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.

1 A tranceript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building,2120 QEye) Street, N.W., Washington, D.C.

[ Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd.,1250 l Street, N.W., Suite 300, N.W., Washington, D.C. 20005.]

ATTENDEES ACRS Members: Dr. Robert L. Seale (Chairman), Dr. Dana A. Powers (Vice-Chairman),

Dr. George Apostolakis, Mr. John Barton, Dr. Mario H. Fontana, Dr. Thomas S. Kress, Dr.

Don W. Miller (June 4 and 5 only), Dr. William J. Shack, Dr. Robert E. Uhrig, and Dr.

Graham Wallis (June 3 only). [For a list of other attendees, see Appendix ill.]

1. CHAIRMAN'S REPORT (Open)

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

Dr. Robert L. Seale, Committee Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting. He announced that Dr. Dana Powers had been reappointed to the Committee for another term. He also noted that a Senate Appropriations Subcommittee had proposed a major reduction in NRC resources.

He suggested that Members read the speech by Chairman Jackson to the Nuclear Energy Assembly on May 15,1998, and the report by Dr. Gail Marcus on the Regulatory Information Conference.

II. AP600 (Open)

[ Note: Mr. Noel F. Dudley was the Designated Federal Official for this portion of the meeting.)

Mr. John Barton, Chairman of the Advanced Reactor Designs Subcommittee, noted that there had been several ACRS Subcommittee meetings held since the last

m 453rd ACRS Meeting 2 June 3-5,1998 ACRS meeting. He stated that, during this session, the Westinghouse Electric Company (Westinghouse) planned to respond to questions raised during the previous Subcommittee meetings.

Mr. Michael Young, Westinghouse, responded to 10 issues associated with the l scaling analysis of thermal-hydraulic tests, data reduction, and application of the NOTRUMP code to the design of the AP600 reactor cooling system. He explained that the database for verification of the AP600 design included integral and single effects tests, and that the NOTRUMP code was used to evaluate small break, loss-of-coolant accidents.

l Mr. Young described the in-containment refueling water storage tank (IRWST) level i penalty that was applied to the NOTRUMP code to enable it to predict system ,

l responses observed during integral tests. Mr. Ralph Landry, Office of Nuclear i Reactor Regulation (NRR), stated that the advance Final Safety Evaluation Report '

specifies that the approval of the IRWST level penalty modification to the NOTRUMP code is contingent on the code being used only for the AP600 safety l analyses.

! Mr. Young explained the use of the drift flux model in horizontal piping, the I l differences between the NOTRUMP predictions of break flow rates and the observed test flows, multi-loop scaling analyses, and the resolution of noding inconsistencies. The Committee and Mr. Young discussed the safety significance of the differenceshetween calculated and observed minimum reactor vessel levels, how the NRC staff will assure that flow resistances in piping at plants will match the design assumptions, the drift flux model documentation, and the uncertainty in the timing of the core makeup tank drain down.

l Mr. James H. Scobel, Westinghouse, presented the results of evaluations of in-vessel retention of core debris and the analyses of ex-vessel severe accident phenomena. He summarized the results of the AP600 probabilistic risk assess-l ment. The Committee, NRC staff, and Westinghouse representatives discussed the meaning of " physically unreasonable," the possibility of intermetallic exothermic reactions, and the use of core damage frequency for screening severe accidents.

Dr. Shou-nien Hou, NRR, explained that the staff did not approve the application of the leak-before-break concept to feedwater piping because Westinghouse could not demonstrate that the probability of an unanticipated feedwater line rupture is extremely low. Mr. Robert Palla, NRR, presented the results of the staff evaluation of the AP600 containment performance during severe accidents. The staff concluded that the AP600 design meets the deterministic and probabilistic

n 453rd ACRS Meeting 3 June 3-5,1998 containment performance goals and the Commission's containment performance guid3line for large, early release frequency. Mr. Michael Snodderly, NRR, presented the results of confirmatory performance tests on passive autocatalytic recombiners (PARS). 1 The Committee and the staff discussed the following:

derivation of the bounding water hammer event, e

applicability of operating plant experience to the AP600 feedwater system design,  ;

. continuation of PARS testing, and e

shortcomings of the PARS environmental qualification criteria. I i

Mr. Brian A. McIntyre, Westinghouse, provided an overview of the AP600 quality assurance and the design of structures, components, equipment, and systems. Mr.

Michael M. Corletti, Westinghouse, provided an overview of the AP600 engineered J safety features, initial test program, technical specifications, design reliability l assurance program, and regulatory treatment of nonsafety systems. i Conclusion The Committee issued a report to Chairman Jackson, dated June 15,1998, on this l matter. .

lli. HUMAN PERFORMANCE PLAN (Open)

]

[ Note: Mr. Noel F. Dudley was the Designated Federal Official for this portion of the meeting.)

Dr. George Apostolakis, Chairman of the Human Factors Subcommittee, stated that the ACRS was first briefed on the Human Performance Plan over two years ago and that the ACRS last heard a briefing on the latest revision of the Plan during the April 30-May 2,1998 ACRS meeting. He noted that after the meeting, the ACRS submitted a list of questions to the staff regarding the Plan.

Dr. Julius Persensky, Office of Nuclear Regulatory Research (RES), explained that the staff had added a purpose, background information, operational experience data, and qualitative risk information to the Plan. He presented the modified framework used in the Plan and described the modified Delphi Technique, in response to the list of ACRS questions, Dr. Persensky described the problem the staff was trying to solve, and the structure and elements of the Plan. He presented

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453rd ACRS Meeting 4 June 3-5,1998 l

the staffs schedule for providing a revised Plan to the Commission by June 30, 1998.

The ACRS Members and NRC staff discussed the following:

the differsace between the purpose and mission statements,

! . a different title for the Plan, j .

the relationship between human error and risk, l .

performance-based regulation of human performance, and l

measunng the degradation of management performance.

l Conclusion l The Committee issued a report to Chairman Jackson, dated June 12,1998, on this l matter.

I IV. CORE RESEARCH CAPABILITIES AT NRC (Open) )

[ Note: Dr. Medhat El-Zeftawy was the Designated Federal Official for this portion of the meeting.]

t l

l Dr. Robert E. Uhrig, Chairman of the Safety Research Program Subcommittee,  !

l introduced the topic to the Committee. He stated that the Subcommittee previously I l met with the staff on June 1,1998, to discuss SECY-98-076.

L NRC Staff Presentation l

On April 2,1997, the NRC staff issued SECY-97-075 to obtain the Commission's  !

approval of a proposed methodology and criteria for evaluating the need for core  ;

l research capabilities, in a Staff Requirements Memorandum (SRM) dated June l 6,1997, the Commission approved the steits proposal in SECY-97-075 and l requested the staff to:

l l Ensure that the areas of research identified for assessment include those areas that are essential for the support of current and foreseeable future regulatory activities.

. In addition to the input provided from other NRC user offices, also consider areas of research suggested by the industry.

. Clarify how the recommended resource levels for each core research area were determined when documenting the core capabilities assessments.

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E 453rd ACRS Meeting 5 June 3-5,1998 Analyze the core technical capabilities residing in NRR, the Office for Analysis and Evaluation of Operating Data (AEOD), and the Office of l Nuclear Material Safety and Safeguards (NMSS), and incorporate the results L into the overall scope of activities and integrate the results with the core i research capabilities analysis.

1 l .

Review the level of resources being applied to research activities that are in a " sunset" state. -

Review the weighting of criteria for Support Area 5 (cooperative research) ,

and Support Area 6 (responses to oversight groups).

In SECY-98-076, the staff responded to the above Commission's requests. In addition, the staff discussed the " expertise-driven" part of the RES core capability assessment. In SECY-97-075, the staffidentified 39 areas of research where core capabilities might be needed. SECY-98-076 provides core capabilities evaluations for 29 areas of research. The original 39 areas of research were reduced to 27, as logical combinations were made during the assessment process (none of the original 39 areas was deleted). Two new areas were added: Fire Protection and Safety and Materials Criticality Safety.

1 The staff believes that, if the expertise-driven level of resources is maintained in the 29 areas, RES will have access to a full range of research expertise that can help respond to unanticipated technical issues that may arise. The staff believes that there is an important nexus between the availability of expertise / facilities and the pursuit of meaningful research. If NRC and its contractors are not pursuing relatively stable programs involving challenging work, talented personnel are likely to leave. Another result could be the loss of access to facilities and potential elimination of facilities due to lack of support.

Three major differences between SECY-98-076 and the previous SECY-97-075, are as follows: j l

SECY-98-076 states that core capabilities assessments are expertise driven.  !

RES recognized that resources to accomplish workload-driven requirements '

are ultimately determined by the annual budget process. The staff does not believe that a separate workload-based assessment, performed outside the budget process, would be meaningful.  ;

SECY-07-075 states that"afterthe Commission gave its preliminary approval to the core research capabilities, reviews by intemal oversight groups and i

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I 453rd ACRS Meeting 6 June 3-5,1998 i

extemal stakeholders would closely follow." The staff believes that, although  ;

these reviews will still be performed, RES plans to first complete three follow-on activities (intemal budget review for FY2000, prioritization of research ,

program components, and exploration of potentialfuture research). Because l these activities could result in changes to the RES core capabilities or the i resource levels for core capabilities, the staff recommends that these l activities be completed and core capabilities be updated as needed before i any further core capabilities reviews by stakeholders are solicited. J l

t SECY-97-075 states that " international cooperative research efforts would be prioritized during the core capability assessments." RES now proposes to perform this activity as it prioritizes its activities during the development and review of the FY 2000 budget.

In SECY-98-076, the staff did not address core expertise in the disciplines required for research to support licensing of the Department of Energy (DOE) high-level radioactive waste repository at Yucca Mountain.

1 Conclusion The Committee issued a report to Chairman Jackson on June 16,1998, on this matter.

l V. BWR EXTENDED POWER UPRATE APPLICATION (Open)

[ Note: Mr. Paul A. Boehnert was the Designated Federal Official for this portion of the meeting.]

Dr. Kress, Chairman, Thermal-Hydraulic Phenomena Subcommittee, introduced this topic to the Committee. He noted that most of the Committee Members were present at the June 2,1998 Subcommittee Meeting on this matter. He said that the presentations would address three topics: the GE Nuclear Energy (GE) generic boiling water reactor (BWR) power uprate program, the Monticello lead-plant power increase request, and the results of NRR's review of the above two matters.

GE discussed the scope of the uprate program guidelines, their impact on automatic scram rates (none), what changes and does not change with regard to plant l operations under uprate conditions, and its conclusions with regard to the results of the uprate program to date. GE believes that the uprate program will provide a path for implementation of significant plant power uprates.

E 453rd ACRS Meeting 7 June 3-5,1998 ~

Representatives of Northem States Power (NSP) discussed the results of the probability risk assessment (PRA) evaluation of the impact of power uprate on plant .

risk for Monticello. NSP noted that the guidance specified in Regulatory Guide l 1.174 had been used in performing the risk assessment. No new vulnerabilities were.found,'and the overall change in risk from uprate was determined to be )

acceptably small.' Dr. Apostolakis suggested that NSP perform an uncertainty analysis to quantify the change in core damage frequency seen as a result of the j power uprate, and to aid the NRC staffs evaluation of the methodology detailed in j Regulatory Guide 1.174. 1 At the request of Dr. Wallis, NSP discussed two issues: (1) by way of an example 1 ofits problem-solving ability, the approach taken to resolve the issue of assurance l

of adequate net positive suction head for the emergency core cooling system l (ECCS) pumps located in containment, and (2) demonstration of adequate margin in its accident analyses to ensure that the suppression pool temperature limit is not  ;

exceeded.

NRR summarized the results of its review of the .Monticello power uprate program by discussing the scope and background for the. lead-plant power increase application review and the results of selected review topics: ECCS/ loss-of-coolant accident (LOCA) evaluation, containment analysis, reactor overpressure protection, hardware capabilities, instrumentation and controls, human factors and the NSP l

individual plant examination. Two open items remained, but these were of a minor nature. Overali, NRR found the power uprate for Monticello acceptable, pending satisfactory closure of the two open items.

1 NRR noted that NSP referenced generic analyses'provided by GE in its topical report on this matter for three issues: anticipated transients without scram, GE l setpoint methodology, and evaluation of generic communications. Drs. Kress and i Seale noted that given the importance of these documents and the limited time provided for ACRS review, and owing to the fact that the Committee did not complete review of the GE topical report, the Committee would not be able to complete its review of this issue during this meeting. Rather, the Committee would consider the matter further and schedule time for review of this issue during its July Meeting.

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- Conclusion

' The Committee plans to continue its review of this matter during the July 8-10,1998 ACRS Meeting.

453rd ACRS Meeting 8 June 3-5,1998 VI. AGENCY-WlDE PLAN FOR HIGH-BURNUP FUEL (Open)

. [ Note: Dr. Medhat M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.] '

The purpose of this briefing was to hear a presentation by the NRC staff regarding an agency-wide plan for high-bumup fuel.

Dr. Ralph Meyer, RES, noted that the U.S. nuclear industry has tremendous economic incentives to extend the bumup of reactor fuel, due to the cost savings .

associated with less frequent refueling outages. He noted that there is also an economic and societal benefit in reducing the volume of radioactive waste that must be stored onsite in the near-term and for permanent disposal in the longer 1 term. Currently, the industry has been given approval at various plants to extend i burnups to 58 GWd/t. The industry plans to pursue approval of even higher j bumups.

1 Se' veral reactivity accidents were analyzed in plant safety analyses with emphasis on the rod-ejection accident (PWR) and the rod-drop accident (BWR). The NRC  ;

used two types of regulatory criteria to address these postulated accidents.- One

~ l is a limit of 280 cal /g on peak calculated fuel rod enthalpy. This limit was intended to ensure that the core could be cooled after such an accident and to preclude the

. energetic dispersal of fuel particles into the coolant. The other regulatory criterion consists of values that are used to indicate cladding failure. This criterion is used in calculating radiological releases for comparison with other limits. For PWRs, a

' critical heat flux value related to departure from nucleate boiling (DNB) is used. For BWRs, a similar value is used for high-power accidents, but for low-power and zero-power accidents, an enthalpy value of 170 cal /g is used.

In late 1993, a test performed in the CABRI test reactor in France produced cladding failure at an enthalpy of about 30 cal /g. Fragmented fuel particles were dispersed from the fuel rod in the test, and enhanced fission product release was observed. In 1994, a similar test in the NSRR test reactor in Japan produced cladding failure at an enthalpy of about 60 cal /g.' These values are far below the 170 cal /g failure criterion used by the NRC. NRR performed a review of the safety significance of this situation and concluded that there was no significant impact on '

public health and safety'because of the low probability of the event and the likelihood that core coolability would be maintained, although there might be some '

increase in the fuel damage fraction.

I 453rd ACRS Meeting 9

June 3-5,1998 Notwithstanding NRR's conclusion, there is still a question of the adequacy of NRC's regulatory criteria for this type of accident, and there are unanswered questions about the behavior of fragmented fuel particles and fission product release during such an event.

The NRC last tested fuel under conditions of these reactivity accidents in 1978 and does not have an active facility where further tests could be undertaken at a reasonable cost. The NRC's general method ofinvestigation is to closely examine L the results produced by the foreign test reactors. Other methods of investigation include more precise plant calculations, using three-dimensional neutronic models, to determine the potential fuel enthalpy rise during realistic plant transients. The NRC staff considers the foreign test data results to contain a large degree of uncertainty (e.g., test reactor pulse width).

In an SRM dated April 16,1997, the Commission instructed the staff to assess the effects of the high-bumup fuel on the adequacy of the regulatory guidelines and ,

licensing criteria. The Commission directed that this assessment should cover not l only reactivity insertion accidents but the design basis accidents such as LOCAs.

In addition, it stated: "The staff should identify the issues that would need to be

, addressed associated with transportation, storage, and long-term geologic burial of higher bumup fuels. The staff should ensure that the 10 CFR 50.59 and Millstone and Maine Yankee lessons leamed recommendations related to licensing bases are adequate to capture the necessary issues related to fuel design." The Commission also requested the staff to continue its cooperation with the industry and intema-tional research activities in order to establish appropriate limits for high-bumup fuels.

1 On July 15,1997, the EDO responded to the Commission SRM as follows: l

. The fuel system is not damaged as a result of normal operation and anticipated operational occurrences (10 CFR 50 Appendix A, Criterion 10)

. Fuel system damage is never so severe as to prevent control rod insertion when it is required (10 CFR 50 Appendix A, Criteria 26 and 27)

. The number of fuel rod failures is not underestimated for postulated accidents (10 CFR 50 Part 100.11)

. Coolability is always maintained (10 CFR 50 Part 46).

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The ACRS Reactor Fuels Subcommittee met on April 23-24,1998 and discussed this matter with the NRC staff and industry. The NRC staffis proposing an agency-wide program plan to deal with issues related to utilization of fuel up to the current limit of 62 GWd/t burnup (average for the peak rod) and a strategy for assessing requests for bumups beyond that limit. This program plan addresses a wide range of issues and was prepared by RES, NRR, NMSS, and AEOD.

1 The program plan addresses the following nine issues:

Cladding integrity and fuel design limits l

. Control rod insertion problems Criteria and analysis for reactivity accidents i

. Criteria and analysis for LOCA Criteria and. analysis for BWR power oscillations (anticipated transient l without scram)

Fuel rod and neutronic computer codes Source term and core melt progression

. Transportation and dry storage e' High enrichments (greater than 5%)

The staff believes that the proposed program plan provides a licensing and research strategy for confirming the safety of currently approved bumup levels and for considering further bumup extensions that the industry is expected to request. The staff believes that there is no immediate safety concern at the current bumup limit of 62 GWd/t. Confirmatory research is underway where the basis involves large data uncertainties and analyses. The licensing and research strategy for bumup extensions involves a shift in responsibility to the industry for work that has traditionally been done by the NRC to establish regulatory criteria and guidelines.

Conclusion The Committee issued a letter to the Executive Director for Operations, dated June 9,1998, regarding NRC participation in the French CABRI reactor fuels research program, and a report to the Commission, dated June 15,1998, regarding the proposed fuels research program plan.

Vll. OPERATING PLAN FOR THE NRC TECHNICAL TRAINING PROGRAMS (Open)

[ Note: Mr. Paul A. Boehnert was the Designated Federal Official for this portion of the meeting.] -

V 453rd ACRS Meeting 11 June 3-5,1998

.Dr. Don Miller, cognizant Member for this issue, noted that the NRC Technical Training Center (TTC), located in Tennessee, has' responsibility for a broad variety of training programs. Mr. Kenneth Raglin of the TTC briefed the ACRS on the 1 Operating Plan for the Agency's technical training programs. l

' Mr. Raglin discussed.the technical training operating plans for reactors and materials, the Training Review Team effort, and provided summary remarks. With regard to the operating plans for reactors and materials training, actions are being ,

taken in anticipation of reduced resources. Some training is being converted to self-study format and some training duties are being transferred from Headquarters to  !

the TTC. Performance plan output measures have shown that reactors and  ;

materials training courses have been successful. The demand for probabilistic risk assessment courses is steadily increasing, due to the requirement that all Agency managers be trained in the rudiments of this discipline. Materials training prograrr s in the area of fuel cycle are evolving as a result of NRC's regulation of gaseous, diffusion plant activities and other work associated with DOE programs.

A Training Review Team has been formed. Led by Jack Roe, NRR, its charter is to review Agency training, activities, costs, processes, and future planning, with the goal ofimproving effectiveness and efficiency. A draft report on the Team's findings is to be completed on August 15, with the final report due to the Executive Council  ;

on October 15,1998. '

Dr. Seale suggested that the Agency evaluate the need for training people in the formation and use of Expert Panels, since nuclear utilities are making increasing use of them. During discussion, it was noted that all Resident inspectors and Headquarters Management Personnel will have taken PRA training by the end of FY99.

Dr. Miller noted that, with the reorganization of the ACRS subcommittee structure, the topic of training has been assigned to each individual subcommittee to be pursued via its area of cognizance. Dr. Seale also asked that the ACRS staff be informed when the Agency believes that briefings on this topic are timely.

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

Vill. PROPOSED MODIFICATIONS TO 10 CFR 50.59. CHANGES.

TESTS AND EXPERIMENTS (Open)

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453rd ACRS Meeting 12 June 3-5,1998

[ Note: Mr. Amarjit Singh was the Designated Federal Official for this portion of the

. meeting.]  ;

i Mr. John J. Barton, Chairman of the Subcommittee on Plant Operations, introduced l the topic to the Committee. He stated that the Committee has had a longstanding l Interest in the proposed changes to 10 CFR 50.59, Changes, Tests and Experi- l ments. He noted that the Committee had previously met in April, October, and i December 1997, and in February 1998, regarding these matters. He also noted i that the Committee issued a report in December 1997. Subsequently, the ,

Commission issued an SRM in March,1998 to the staff that contained most of the I Committee's recommendations, with the exception of the long-term, risk-informed approach to 10.CFR 50.59. The NRC staff presented the status and its response to the SRM.

NRC Staff Presentation  !

Ms. Eileen McKenna, NRR, led the discussion for the NRC staff. Messrs. Tom j Essig and Frank Akstulewicz, NRR, also participated. The staff presented the status of activities related to the SRM regarding the rulemaking for 10 CFR 50.59. l The key issues in the SRM include: '

The first item in the SRM is to prepare a proposed rulemaking package for revisions to 10 CFR 50.59 by July 10,1998 that will allow (a) minimal

' increases in probability, (b) minimal increases in consequences, and (c) minimal reductions in margin to be made without prior NRC approval.

One of the specific proposals the staff was asked to consider was changing the process to allow changes that create accidents of a different type with minimal safety impact. The staff responded to this issue and the others in a memorandum dated May 27,1998.

The Committee and staff extensively discussed the minimal consequences of an accident or malfunction of equipment important to safety. The staff stated that NEl proposed that the rule be revised so that a change would only require approval if the consequences of an accident or malfunction previously evaluated exceed the established acceptable limit. Although the staff would not be concerned about minimal increases in consequences or in cases that are not near the regulatory guidelines, the staff is concerned about allowing licensee changes without prior review which, 'vhen evaluated with licensee assumptions and methods, result in doses at or very close to the regulatory guidelines (e.g., Part 100).

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June 3-5,1998 )

Conclusion The ACRS wil'l hold a Subcommittee Meeting on June 19,1998, to discuss this issue.

IX. PROPOSED FINAL STANDARD REVIEW PLAN (SRP) SECTION AND REGULATORY GUIDE FOR RISK-INFORMED INSERVICE JNSEEQIlQtLQE_P_lP_ltiG_(Open)  !

[ Note! Mr. Michael T. Markley was the Designated Federal Official for this portion i of the meeting.)

Dr. George Apostolakis, Chairman of the ' Subcommittee on Reliability and Probabilistic Risk Assessment (RPRA), introduced the topic to the Committee. The i purpose of this meeting was to discuss the proposed final Standard Review Plan  !

- (SRP) Section 3.9.8 and associated Regulatory Guide 1.178 (formerly DG-1063) for risk-informed inservice inspection (ISI) of piping.

NRC Staff Presentation  !

1 Messrs. Thomas King, RES, and Gary Holahan, NRR, led the discussions for the i NRC staff. Mr. Goutam Bagchi, NRR, provided supporting discussion. Significant points raised during the discussion include: l

. The staff requested a Committee report supporting issuance of these i documents for ? trial use" by the industry and staff.

. The staff plans to incorporate the Appendices to DG-1063 into a draft NUREG for use during the trial period. Following trial use, the staff plans to ,

decide whether to keep the NUREG or incorporate the technical approaches l into a regulatory guide.

. The staff is scheduled to complete its review of the pilot applications for Surry, Vermont Yankee, and Arkansas Nuclear One Unit 2 by December 31, 1998.

i

. The staff recently met with the NRC Committee to Review Generic Require-ments (CRGR) to discuss these matters and had provided the draft Commission paper forwarding the proposed SRP Section and Regulatory Guide to the EDO for consideration.

453rd ACRS Meeting 14 i June 3-5,1998 Industry Presentation Mr. Biff Bradley of the Nuclear Energy Institute (NEI) led the discussions for the industry. Mr. Ken Balkey and Ms. Nancy Closky of the Westinghouse Owners Group (WOG) and Mr. Jeff Mittman of the Electric Power Research Institute (EPRI) provided supporting discussion. Messrs. David Garchow of Pacific Gas and Electric Company and Karl Fleming of ERIN Engineering also participated. Significant points raised during the discussion include:

The proposed final SRP Section and Regulatory Guide 1.178 for risk-informed ISI of piping should be issued for " final use." However, trial use is acceptable if it facilitates the expedient review of the topical reports and pilot applications. l Timely completion of the staff reviews of topical reports and pilot applications ,

is essential to reduce regulatory uncertainty regarding risk-informed ISI. '

Dr. Apostolakis questioned the basis for the staff proposal to issue the subject documents for " trial use." The staff stated that the major issue is the likelihood of changes to the proposed guidance based on experience with the pilot applications.

The staff stated that they may have to pursue backfit procedures per 10 CFR 50.109 if changes were needed and the documents had been previously issued for final use.

Dr. Apostolakis stated that Regulatory Guide 1.178 requires additional editing to clarify the application for risk-informed ISI. In particular, he noted the considerable redundancy with the guidance provided in Regulatory Guide 1.174 (General Guidance). The staff agreed to consider clarifying Regulatory Guide 1.178 but emphasized that significant delays would result if the Appendices were added to the document or if the proposed guidance required revision for use as final.

Conclusion The Committee issued a report to Chairman Jackson dated . lune 12,1998, on this matter. '

-X. EXECUTIVE SESSION (Open)

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

- meeting.]

r 453rd ACRS Meeting 15 June 3-5,1998 A. - Reports, Letters and Memoranda REPORTS Proposed Final Draft of the NRC's Human Performance Plan (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 12,1998.)

Prooosed Final Standard Review Plan Section 3.92 and Reaulatorv Guide 1.178 for Risk-Informed Inservice Inspection of Pioina (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 12,1998.)

. The Safety Asoects of the Westinahouse Electric Comoany Aoolica-tion for Certification of the APG00 Plant Desian - Interim Letter 3 (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 15,1998.)

NRC Reactor Fuels Research Proaram (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 15,1998.)

Review of SECY-98-076. " Core Research Caoabilities" (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated June 16,1998.)

. Review and Evaluation of the Nuciear Reaulatory Commission Safety l Research Proaram (Letter to Shirley Ann Jackson, Chairman, NRC, '

from R. L. Seale, Chairman, ACRS, dated June 24,1998, transmit- l ting an advance copy of NUREG-1635, Volume 1, Review and  !

Evaluation of the NRC Safety Research Program)

LETTER  ;

NRC Particioation in the CABRI Reactor Fuels Research Proaram (Letter to L. Joseph Callan, Executive Director for Operations, NRC, i from R. L. Seale, Chairman, ACRS, dated June 9,1998) l I

' 453rd ACRS Meeting 16 ,

- June 3-5,1998

]

d MEMORANDA  !

Draft Advance Notice of Prooosed Rulemakina Reaardina Amendina 10 CFR 50.72. "Immediate Notification Reauirements for Operatina l

Nuclear Power Reactors." and 10 CFR 50.73. " Licensee Event Report  !

System" (Memorandum to L. Joseph Callan, Executive Director for i Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated June 9,1998)

. Safety Evaluation Report on Electric Power Research Institute Toolcal I Report. TR-107330. Final Report. " Generic Reauirements Specifica-tion for Qualifyina a Commercially Available PLC for Safetv-Related l Aoolications in Nuclear Power Plants." (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated June 9,1998)

B. Reconciliation of ACRS Comments and Recommendations

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

The Committee discussed the response from the EDO to ACRS comments and recommendations included in recent ACRS reports:

. EDO letter dated May 4,1998, responding to the ACRS report dated April 9, 1998, conceming the proposed Commission paper entitled, " Plans to increase Performance-Based Approaches in Regulatory Activities."

The Committee decided to discuss this issue at a future meeting after the staff has issued a White Paper on performance-based regulation.

. EDO letter dated May 20,1998, responding to the second interim ACRS letter, dated April 9,1998, conceming the safety aspects of the Westing-house Electric Company application for certification of the AP600 plant design.

The Committee decided that it was satisfied with the EDO response.

.- EDO letter dated May 28,1998, responding to the ACRS report dated March 16,1998, concoming SECY-98-001, " Mechanism for Addressing Generic Safety issues."

5 453rd ACRS Meeting 17 June 3-5,1998 The Committee decided that it was satisfied with the EDO response, but that

it would continue to discuss this issue at a future ACRS meeting.

EDO letter dated May 29,1998, responding to the ACRS report dated May 8,1998, concoming the proposed final amendment to 10 CFR Part 55, " Initial Licensed Operator Examination Requirements."

The Committee decided that it was satisfied with the EDO response.

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

The Committee heard a report from Dr. Seale and the Executive Director, ACRS, on the Planning and Procedures Subcommittee meeting held on June 2,1998. The following items were discussed:

1. ACRS/ACNW Budaet Review (Open)

On May 26,1998, the Chief of the Operations Support Branch and the ACRS/ACNW Executive Director met with the NRC's Performance Review Committee to discuss the ACRS/ACNW Office budget submittal. Although the agency is currently working on its budget i request for FY 2000, the FY 1999 budget has yet to be decided by Congress. There is a strong expectation that the NRC will incur a significant reduction in its FY99 requested budget. Each Office has been asked to consider the impact of a ten percent or greater reduction. .The ACRS staff is currently assessing the best way to absorb a reduction in travel, program support, and staff. 1 l

Recommendation Keep the Committee informed on Commission decisions on the ACRS/ACNW FY 1999 and 2000 budgets.

2. Anoointment of ACRS Members (Open)

- Dr. Larkins, ACRS/ACNW Executive Director, met with each of the  !

NRC Commissioners and the Chairman to discuss the ACRS Screening Panel's proposed slate of candidates for membership on the ACRS. The professional and technical backgrounds of all the 1 candidates were discussed as well as conflict-of-interest-issues.

L

^

-453rd ACRS Meeting . 18 June 3-5,1998 l

Committee activities in FY 1998 and beyond were discussed with the l Chairman and Commissioners and all felt there was a continuing  !

need for additional ACRS expertise in Operations /PRA. Although one l Commissioner felt the Screening Panel had done as good a job as I practical and should forward its top three candidates to the Commis-sion for consideration, it was clear that the majority had concerns )

regarding timing and other issues. The Screening Panel is consider-ing postponing a recommendation until November 1998 and continu-ing to solicit other candidates.

Recommendation i l

The Subcommittee had no objection to the proposal by the Screening Panel for a delay in making a recommendation on new members until later in the year.

3. ACRS Member Foreion Travel Plans for FY 1999 (Open) i As part of the planning for the ACRS budget expenditures for FY l 1999, the ACRS/ACNW Office is requesting that members assess their foreign travel plans for the next fiscal year. All members are  !

requested to provide to the Chief, Operations Support Branch, at the ,

i July 1998 full Committee meeting, a list of any proposed foreign travel for which they plan to request ACRS support.

4. ACRS Review of Pacers for the Quadricartite Meetina (Open)

The July 1998 ACRS agenda will provide scheduled time for the ,

review of and comment on the papers to be presented at the October '

1998 Quadripartite Meeting in Japan. Presenters should provide their papers to the ACRS staff prior to the July 1998 meeting, so that they can be copied and forwarded to all the members for review prior to the meeting. The ACRS has traditionally formally approved the papers prior to forwarding therraa its foreign counterparts. Members should provide draft papers to Sam Duraiswamy by June 22,1998.

Anyone requiring assistance in the preparation of papers should coordinate this assistance through Mr. Duraiswamy. The ACRS staff is still awaiting information from the Japanese on hotel accommoda-tions and related activities.

5. Revised Operatina Plan (Open)

l 453rd ACRS Meeting 19 June 3-5,1998 All NRC Offices were requested to update their Operating, Plans by May 22,1998. A draft revised Operating Plan for the ACRS and ACNW was forwarded to the EDO, noting that it was subject to review and comment by both Committees. All members have been provided a copy of the revised Operating Plan. Subcommittee Chairmen have been asked to review and comment on their sections of the revised Operating Plan by the end of the June 1998 full Committee meeting.

The final revised Operating Plan will be sent to the Commission.

Recommendation Subcommittee Chairmen should provide comments on the Operating Plan by June 5,1998, so the Plan can be reviewed by the Planning and Procedures Subcommittee and finalized prior to forwarding it to the Commission.

6. DPO Reaardina the Reaulatorv Acoroach to Steam Generator Intearity (Open)

Dr. Hopenfeld, RES, has presented his differing professional opinion (DPO) on the staff approach to steam generator integrity to the ACRS on two occasions. He has sent a memorandum dated May 20,1998, to Dr. Larkins identifying research results, which were presented at the May 4-7, 1998 CSARP meeting in support of his DPO. Dr.

Hopenfeld also sent a memorandum dated April 21,1998, to Mr.

Thadani, Acting Deputy EDO, providing comments beyond those  :

provided at the ACRS fall meeting. The NRC staff will send a memorandum to the ACRS in response to Dr. Hopenfeld's recommen-dation.

Epcommendation Review and comment on the staff resolution of the DPO. Take no additional action unless the NRC staff requests ACRS involvement.

7. Action Plan for Reviewina License Renewal Aoolications (Open)

Commissioner Diaz requested that the Committee review license renewal applications during the early stages of development.

l ,

453rd ACRS Meeting 20 June 3-5,1998 Dr. Fontana plans to meet with the staff informally on June 2,1998 to gather information on the status of the staff activities associated with l

license renewal. Subsequent to this meeting, he plans to prepare an

Action Plan for reviewing license renewal activities.

Recommendation Dr. Fontana should provide an Action Plan for ACRS review of the >

license renewal activities to the Committee for consideration.

8. NRC Instmmentation and Control (l&C) Strateaic Plannino Briefina (Open)

The NRC staff has invited Dr. Don Miller to attend a briefing by Dr.

Barry Johnson, Director of the University of Virginia's Center for Safety-Critical Systems, on the aftemoon of July 7,1998, at the NRC office in Rockville, Maryland. The briefing will cover work conducted under a cooperative agreement between the NRC and the University of Virginia. The work is entitled, " Embedded Rea!-Time Safety-Critical Digital Systems," and will be a key part of the NRC strategic research plan for digital l&C. Dr. Miller would like to attend the meeting as a reprecentative of the ACRS. He understands that he will be an observer at the meeting since the l&C research plan will be reviewed by the ACRS at a later date.

Recommendation Authorize Dr. Miller to attend the meeting as an ACRS observer.

9. ACRS/ACNW Survevs (Open)

A memorandum was sent to the Commission on June 1,1998, to forward the results of the ACRS and ACNW surveys.

D. Future Meetina Aaenda Appendix IV summarizes the proposed items endorsed by the Committee for the 454th ACRS Meeting, July 8-10,1998.

The 453rd ACRS meeting was adjoumed at 7:15 p.m. on Friday, June 5,1998.

I I I 1

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[ ,

PPENDIX-1 .

Federal Register / Vel. 63 ND. 94 / friday, May 15,1998/ Notices

' 27105 s

ound in the Government Printing OfBos 1:15 PM-5:00 PM

'PO) document entitled " General Waae Tentative Agenda:

Avenue, NW., Suite 530, Washington, etennisations Issued Under The Davfe .Modeling Task Force Paeontation DC 20506, Telephone: (202) 606-8322, Bacon and Related Acts."This TDD:(202) 606-6282.

rennminaion Discussion of Benents, Nemey E, weise, onis available et each of the SF Cost and EligibilityIssues +

analGovernment Depository haday,)une 2.1998 AdmoryCesiedem Mensposeerrt Ofscer, and many of the 1,400 IFR Doc sk12eu Fund 5-ms; s.45 am) -

Government Depository Libraries across 9:00 AM-11:00 AM Tentative Apode: suas esos sees.es.m the country.

De ons Commisalon Discussion of-- ~ - t Whetion and Finant'in NATIONAL SCIENCE FOUNDATION misia A= - avanabw by subscription to the FedWorld r *cimbau "

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Medicam e===l==In= anestings in um Federal Bagister. consent of the Senate, for six year terms,

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' OfRoe, Washington, D.C. 20402. (202) 512-1800. . . 7elle Booler, - in addition to b NSF Duector ex When hard Olfk'M'"88'r, Nosonefalpartisen Madismo' officio. Section 4(c) of the National subscripu caounksien Science Foundation Act of1950, as sum fy b ,

State (s) oflaterest, since su amended, states that:b persons ptions M Doc. e6-1302s Fund 5-14M48 an] . . nonnineted fw appointment as members '

may be ordered forany orallof the suae sous nesee.es seven a te volumn, arranged by of the Board (1) shall be eminent in the-Solds of the basic, medical, or social State. Su puonsinclude en annual sciences, engineering, agriculture, edition (issued in January or February) NATIONAL FOUNDATION ON TNE education, monarch management, or which includes all cunent general wage ARTS AND TNE NUMANITIES ,

Publi.c affairs; (2) shall be selected solely dot sminations for the States covesed by each volume. %roughout b :===I=<l., NeWonel CouneN en #m Numanless on e baals ofestaWahed moords of disunguished service; and (3 shall be so ef.,b year, regular weekly updates are Meeting selected as to pmvide represe)ntation of ,

tribund to subedbas. the views of scientlBc and engineering .

pod at Waahl=reaa D.C.his eth day of May st, sees. leaders in all areas of the Nation.

.y sees.

Pursuant to the visions of the b Board and the NSFDirector .'

Margoest J.Washisones Federal Advisory mittee Act (Pub. , solicit and evaluate nominations for pa..rW arench ofconstruction way subminion to b Pruident.

Deseregmeuses.

L von 92-483, as amended),

that a meeting of the Nationalnotice is hereby Nominations accompanied by IFR Dec. 96-12549 Filed 5-to-es; a:45 aml uncil on the Humanities willbe held biographicalinformation may be s u as sees e m in Washington, DC on May 27,1998. fcrwarded to b Chairman, National The purpou of this meetinals to Science Board,4201 Wilson Boulevard, advise the recently appointed ~ Chairman Arlington, VA. 22230, no later than June 15,1998 TNE NATIONAL. SIPARTISAN of the NationalEndowment for the Humanities with res Any cluestions should be directed to COMMISSION ON TNE F'JTURE OF to policies and Mrs. Susan E. Fannoney, StaH Assistant, MEDICARg q, Procedures for out nas .

functions. NationalSciencaBoard OfBee(703/

PulsoMeeung _ %e meeting willbe heldin the Old 306-2000). - -- -

Post Office Building 1100 Pennsylvania g,,,, g, y,,,,,,y, .

Establishment of the Medicare N ggggy,ygg,-

Commission included in Chapter 3, Avenue 10:00 a $n.W., Washington, DC fromM Doc. 96-12948 Fuod 5-14-44; 8:45 mal to 3:00 p.m. Because the Section 4021 of the Balanced Budget 8"888'*"'" * "

Act cf1997 Conference The Councilwillconsidwinformation relating to the internal practicos of the .

Medicare Commissionis with a hilding public meetings and blicidag andinformation the disclosure the date, time and location in ofen$ch wh would signi8cantlyaNect CLEAR REOULATORY Federal implementation of proposed esency COMMISSION _____1_. -

Noticeo Public~Mwtingstobeheld . action,b meeting wiu not be open to the public pursuant to subsections (c)(2) Advisory Committee on Reactor on Monday, June 1,1998 and Tuesday, and (9)(B) of Section 552b of Title 5, Standards; Meeting Notice June 2.1996 in Washington,DC.

b NationalBipartisan Commission United States Code.1 have made this la accordance with the purposes of determination under the authority Sections 29 and 182b. of the Atomic on b Future ofMedkare willhold tod to me by the Chairman's public meetings og June 1 and 2,1998; Energy Act (42 U.S.C. 2039,2232b), the ,

legation of Authority dated July 19, Advisory Committee on Reactor location to be determined. Please check 1993.

tb Commission's web site for the Safeguards willhold a mwting on June 8on of the meeting:http:// Furtherinformation about this 3-5,1998,in Conference Room T-283, meeting can be obtained from Ms. 17545 Rockville Pike, Rockville, care. Commission. Gov. Nancy E. Weiss, Advisory Committu udsy, June 1,1998 Maryland.De date of this meeting was Management OfBcor 1100 Pennsylvania previously publishedin the Federal y,.

I.

e ,

• 27208 Federal Register /Vol. 63, No. 94 / Friday, May 15,1998 / Notices Register on Thursday, November 20, committee will hear presentations by and be permitted only during 6 open portions 1997 (62 FR 62079). hold discussions with representatives of the of the meetina and questions may be asked NRC sta!! regarding the status of staff only b mem5m of the Committee,its Wednesday, June 3,1998 ^~

activities associated with the proposed consuftants, and staff. Persons desiring to ,

8Jo om.-8:45 a.m.: Opening Rernorks by modifications to 10 CFR 50.59. make oral statement should notify Mr. Sam the ACRS Chairman (Open)-The ACKS 2:30 p.m.-2:45 pm.: Proposed Final Duralswamy. Chief of the Nuclear Reactors Chairman will make opening remarks Standard Review Plan (SRP) Section and Branch, at least five days before the meeting' regarding conduct of the meeting. Regulatory Culde for Risk laformed laservice if possible, so that appropriate arrangements 8;45 a.rr>.-s 2:s 5 c.tn.: AP600 Design inspection of Piping (Open)-The Committee can be made to allow the necessary time (Open)-The Committee will hear will hear presentations by and hold . . during the meeting for such statements. Use presentations by and hold discussions with discussions with npresentatives of the NRC of still, motion picture, and television npresentatives of the Westinghouse Electric staff re6ardmg the proposed SRP Section and cameras during h meeting may be limited Company and the NRC staff regarding Regulatory Guide for risk. informed inservice to selected portions of the meeting as Chapters 3,6,14,16 and 17 of the AP600 inspection of piping at nuclear power plants, determined by the Chairman. Information Standard Safety Analysis Report, as ws!! as as well at the issues and concerns raised regarding the time to be set aside for this the PRA. regulatory treatment of the non. previously by the ACRS members on this purpose may be obtained by contacting the safety systems. Test and Analysis Program matter. Chief of the Nuclear Reactors Branch prior to performed by Westinghouse in support of the 2:45 pm.-3:2 5 p.m.: Future ACRS the meeting. In view of the possibility that AP600 desip, and the associated NRC staffs Activities (Open)-The Committee will the schedule for ACRS meetings may be evaluation. discuss the recommendations of the Planning adjusted by the Chairman as necessary to 22:25 a.m.-1220 Noon: Human and Procedures Subcommittee regarding facilitate the conduct of the meeting, persons Performance Plan (Open)--The Committee items proposed for considerstlot by the full planning to attend should check with the will hear presentations by and hold Committee during futum meetings. Chief of the Nuclear Reactors Branch if such discussions with representatives of the NRC 3:25 p.m.-3J0 pm: Reconciliation of rescheduling would result in major staff regarding issues / concerns raised by the ACRS Comments and Recommendations inconvenience.

ACRS members on the~ revised Human . (OpenbThe Committee will discuss In accordance with Subsection 10(d) Pub.

Performance Plan, responses from the NRC Executive Director L 92-463,I have determined that it is 20 p.m.-2Jo p.m.: Core Research for Operetions (EDO) to comments and necessary to close portions of this meeting Capabilities of NRC(Open)-The Committa recommendations included in recent ACRS noted above to discuss matters that relate will hear presentations by and hold reports, including the EDO response to the solely to the internal personnel rules and discussions with representatives of the NRC comments and recommendations included in practices of this Advisory Committee per 5 staff regarding core research capabilities at the April 8,1998 ACRS report regarding U.S.C 552b(c)(2), to discuss General Electric NRC Plans to increase the Performance-Based Company proprietary information per 5 2:45 p m.-4:45 p.m.:BWR Extended Power A PProaches in Reguletory Activities. U.S.C 552b(cM4), and to discuss information Uprote Application (Open/ Closed)-The 3:45 p.m.-720 p.m.: Preparation ofACRS the release of which would constitute a Committee will hear presentations by and Reports (OpenHThe Committee will clearly unwarranted invasion of personal hold discussions with representatives of the continue its discussion of proposed ACRS pri per 5 U.S.C 552b(c)(6).

General Electric Company (GE).the reports on matters considered during this F er information regarding topics to be '

.( Monticello Nuclear Generating Plant meeting. . discussed, whether the meeting has been licensee, and the NRC staff regarding the CE cancaled or rucheduled, the Chairman's yriday* june 8.1998 ruling on requests for the opportunity to

. power uprate plan for operating BWRs, and the application from the Monticello Nuclear #JO am.-940 om: Report of the Planning present oral statements and the time allotted Generating Plant for a power level increase and Procedures Subcommittee (Open/ therefor, can be obtained by contacting Mr.

of 6.3 percent. Closed)-The Committee will haar a report of Sam Dur:1swamy, Chief of the Nucleat Note:A rtion of'this session may be the Planning and Procedures Subcommittee Reactors Branch (telephone 301/415-7364),

closed to Neuss the General Electric nbusiness, matters related to the conduct of ACRS and organizational and personnel between 7:30 A.M. and 4:15 P.M. EDT.

Company proprietary information. . ACRS meeting agenda, meeting transcripts, matters relating to the ACRS. and letter reports are available for 5 20 p.m.. 720 .m.:Prepomtion o ACRS Note: A portion of this session may be downloading or reviewing on the internet at

"" closed

1. 1. 1. f3 P'

, ",* ners I to discuss organlaational and http://www.nic. gov /ACRSACNW.

rs noel matters that relate solely to the Dated: May it.1998.

considered during thiswillmeeticIso meeting. the Committee a discuss[temal aDuring penthis nnel rules and practices of thisAndrew L Bates, ns posed ACRS report on the NRC Safety searth Pmgrarn.

h, '

3p and Advisory Committee Management Officer.

- Information the release of which would [FR Doc. 96-12977 Filed 5-14-08; 8:45 am)

• thurodoy, June 4,1998 - . constitute a clearly unwarranted invasion of. satseo ccos rses.es.e 8 20 e x -8 25 c.m.: Opening Remarks by penocal privacy.

the ACRS Chairman (Open>The ACRS 9Do cA-320 pA (22D0-190 pa- .

Chairman will make opening remarks Iunch): Preparation ofACRS Reports . PENSION BENEFIT GUARANTY regarding conduct of the meeting. (Open)--The t'rmmittee will continue its CORPORATION 825 cm-9:45 ca: Asency. wide Planfor discussion of proposed ACRS reports on ~

High.Bumup Puel(Open)-The Committee matters considered during this mutingr - Interost Assumption for Determining will hear presentations by and hold . 320p.m.--4s0pa Miscellaneous . Variable-Rate Premium; interest discussions with representatives of the NRC (Open)-The Committee will discuss matters . Assumptions for Multlemployer Plan related to the conduct of Committee activities staff regardinbthe high-burnup et Agency wide plan for and matters and specific issues that were not Valuations Following Mass Withdrawal 2020 ca-2240 c.rn.: Operating Plan for - completed during previous meetings, as time AGENCYt Pension BeDeSt Guaranty the NRC Technical Training Progmms and availability of information permit.

Procedures for the conduct of and CoTPoration.

(Opea)--The Committee will hear presentations by and hold discussions with participation in ACRS meetings were ACTION: Notice ofinterest rates and representatives of the NRC staff regarding the published in the Federal Register on assumptions.

Operating Plan for the NRC technical training September 4,1997 (62 FR 46782). In accordance with these procedures, oral or . suuuARY:This notice informs the public programs and related mattera, j 2 iso on-2220 p.m.: Proposed written views may be presented by members of the interest rates and assumptions to .

d( Modifications to 10 CTR 50.59, Changes, Tests and Experiments (Open)-The of the public. Including representatives of the be used under certain Pension Benefit nuclear ladustry. Electmnic recordings will Guaranty Corporation regulations. These I

1 APPENDIX II l

/ e me:g g -

UNITED STATES '

/ n NUCLEAR REGULATORY COPAMISSION

,p

$ ADVISORY 00MMITTEE ON REACTOR SAFEGUARDS e

WASHINGTON, D. C. 20586 i *****

l May 11, 1998 SCEEDULE AND CUTLINE FOR DISCUSSION l 453rd ACRS MEETING l JUNE.3-5, 1998 WEDNESDAY. irNW 3. 1998. CONF 2W M CI R W 2B3. Tito iraitz FLINT NORTE.

ROCKVILLE. MARYLAND

/

1) 8:30.- 8:45 A.M. Onenina Remarks by the ACRS Chairman (Open) 1.1) Opening Statement (RLS/JTL/SD) 1.2) Items of current interest (RLS/NFD/SD) l 1.3) Priorities for preparation of ACRS  ;

reports (RLS/JTL/SD)  !

II:co

2) 8:45 --itses A.M. AP600 Desian (Open) (JJB/TSK/NFD/PAB) l (10:M -10:30 A.M. BREAK) 2.1) Remarks by the Subcommittee Chairman. '

2.2) Briefing by and discussions with representatives of the Westinghouse Electric Company and the NRC staff regarding chapters 3, 6, 14, 16 and 17 of the AP600 Standard Safety Analysis Report, as well as the PRA, regulatory treatment of the non-safety systems, Test and Analysis Program performed by Westinghouse in support of the AP600 design and associated NRC staff's evaluation. l n r.* oo 22 P. H.

l 3) 15:48 - 12:$9 Neon Human Performance Plan (Open) (GA/NFD) 3.1) Remarks by the Subcommittee Chairman.

3.2) Briefing by and discussions with representatives of the NRC staff i regarding issues / concerns raised by '

the ACRS members on the revised Human Performance Plan.

Representatives of the nuclear industry will j provide their views, as appropriate.

28  %  !

12:00 - 1:00 P.M. ***LUNCE*** i i

oo / \

4) 1:00 - 2:30 P.M. Core Research Canabilities at NRC (Open) l (REU/DAP/MME) 4.1) Remarks by the Subcommittee Chairman. l 4.2) Briefing by and discussions with I representatives of the NRC staff regarding core research capabilities at NRC T

(hscA6dpoch4*wu'd"j

2

.2! oo - 1: S o f, H. Ytconkn os Aesurcl Syraw Repcrt 2:30 - 2:45 P.M. *** BREAK ***

5) 2:45-4:h[P.M. BWR Extended Power Unrate Annlication (Open/ Closed) (TSK/PAB) 5.1) Remarks by the Subcommittee Chairman.

5.2) Briefing by and discussions with .

representatives of the General Electric Company (GE), Monticello Nuclear Station licensee, and the NRC staff regarding the GE extended power uprate plan for operating BWRs, and the application from the Monticello Nuclear Generating Plant for a power level increase of 6.3 percent.

[ Note: A portion of this session may be I closed to discuss General Electric Company Proprietary information.]

35 4:55 ~%

4:55 - 5T99 P.M. *** BREAK *** \

25 l

6) 91fnr

$sec - 7:80 P.M. Prenaration of ACRS Renorts (Open)

Discussion of proposed ACRS Reports on:

6.1) NRC Safety Research Program (DAP/MME) 6.2) AP600 Design Certification Application (JJB/TSK/NFD/PAB) 6.3) Human Performance Plan (GA/NFD) 6.4) Core Research Capabilities (REU/DAP/MME) 3 THUREDAY. JUNE 4, 1998. CONFWDRMCE ROOM 2B3. TWO WHITE FLINT mumin.

ROCKVILLE,. MARYLAND j

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

(RLS/SD) '

8) 8:35 - 9:45 A.M. Apenev-Wide Plan for Hich-Burnun Puel (Open)

(EA?/MME) 8.1) Remarks by the Subcommittee }

Chairman. )

8.2) Briefing by and discussions with representatives of the NRC staff regarding the Agency-wide plan for i high-burnup fuel. i Representatives of the nuclear industry will provide their views, as appropriate.

66 5 T 9:45 - 10:00 A.M. *** BREAK *** ,

l

. i l

1

3 ar og /

• i

9) 10:92 - 11:0@ A.M. Doeratine Plan for the NRC Technical Training Procrams (Open) (DWM/PAB) 9.1) Remarks by the cognizant ACRS member.

9.2) Briefing by and discussions with the representatives of the NRC staff regarding the Operating Plan for the

'nAC technical training programs and

' related matters.

of o3

10) 11:00 - 12:30 P.M. Pronosed Modifications to 10 CFR 50.59.

Chances. Tests. and Erneriments (Open)

(JJB/AS) 10.1) Remarks by the Subcommittee Chairman.

10.2) Briefing by and discussions with representatives of the NRC staff regarding the status of staff activities associated with the proposed modifications to 10 CFR 50.59.

• Representatives of the nuclear industry will provide their views, as appropriate.

12:30 - 1:30 P.M. ***LUNCE***

3 lo

11) 1:30 - 2 : 45 P.M. p/

Pronosed Final Standard Review Plan (SRP)

Section and Reculatorv Guide for Risk-Informed Inservice Inanection of Pinino (Open) (GA/AS) 11.1) Remarks by the Subcommittee Chairman.

11.2) Briefing by and discussions with representatives of the NRC staff regarding the proposed final SRP Section and Regulatory Guide for risk-informed inservice inspection of piping at nuclear power plants as well

• as the issues and concerns raised l previously by the ACRS members on this matter.

Representatives of the nuclear industry will

\

j provide their views, as appropriate.

3o 34 50 1 l

12) 2 :45 - itsWB P.M. . Future ACRS Activities (Open) (RLS/JTL/SD) i Discussion of the recommendations of the Planning and Procedures Subcommittee l regarding items proposed for consideration l

' by the full Committee during future  :

meetings.

{

l l

l 4

r .2 ro oo

.13) 2 25 - 3:30 P.M. Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et al./GHM/SD, et al.)

Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports.

3:N-3 NP.M. *** BREAK ***

3:M -

3 W S f. M . '12cw 15

14) 3: N - 7:18#DP.M. Prenaration of ACRS Renorts (Open)

Discussion of proposed ACRS reports on:

14.1) NRC Safety Research Program (DAP/MME) 14.2) AP600 Design Certification Application (JJB/TSK/NFD/PAB) 14.3) Human Performance Plan (GA/NFD) 14.4) Core Research Capabilities (REU/DAP/MME) 14.5) Proposed Modifications to 10 CFR 50.59 (JJB/AS) 14.6) Agency-Wide Plan for High-Burnup Fuel (DAP/MME) 14.7) BWR Extended Power Uprate Application (TSK/PAB) 14.8) Proposed Final SRP Section and Regulatory Guide for ISI of Piping at Nuclear Power Plants (GA/AS)

FRIDAY. JUNE 5. 1993. CONFr# NCE ROOM 233. TWO WHITE FL m munrn.

ROCKVILLE. MARYLAND 3l.2o 3: 45 Pn

15) 8904. - Su@@ A:46. Reeort of the Plannine and Procedures subcommittee (Open/ Closed) (RLS/JTL)

Report of the Planning and Procedures Subcommittee on er.atters 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, qualification of candidates for ACRS membership, and information the release of which would constitute a clearly unwarranted invasion of perscaal pivacy.)

jg

16) 8 *. 30-asse 4H Blurp,te P .M. Prenaration of ACRS Reeerts (Open)

(12:00-1:00 P.M. LUNCE) Continue discuccion of proposed ACRS reports listed under Item 14.

i i

5 l 17) 3:30 - 4:00 P.M. Miscellaneou.E (Open) (RLS/JTL/SD)

Discussion of matters related to the conduct of Committee activities and matters and specific issues that were not completed during previous meetings, as time and availability of information permit.

EQIE:

• 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.

e Number of copies of the presentation materials to be provided to the ACRS - 35.

O 1

i

APPENDIXlll: MEETING ATTENDEES i 453RD ACRS MEETING JUNE 3-5,1998 NRC Staff (June 3,1998)

J. Mitchell, OEDO R. Gramm, NRR T. Kenyon, NRR T. Scarborough, NRR R. Landry, NRR T. Collins, NRR R. Pettis, NRR M. Mitchell, NRR B. Huffman, NRR E. Adensam, NRR J. Sebrosky, NRR J. Raval, NRR E. Thom, NRR - R. Eckenrode, NRR G. Bagchi, NRR J. Schiffgens, NRR R. Caruso, NRR J. Bongarra, NRR J. Wilson, NRR C. Wu, NRR H.Li,NRR C. Carpenter, NRR M. Snodderly, NRR A. El-Bassioni, NRR T. Quay, NRR R. Guan, NRR J. Lyons, NRR R. Frahm, NRR S. Hou, NRR T. Ulses, NRR B. Palla, NRR R. Jolly, NRR H. Walker, NRR H. Garg, NRR i D. Scaletti, NRR S. Lee, NRR M. Reinhart, NRR V. Ordaz, NRR

)

D. Terao, NRR J. Costello, RES T. Cheng, NRR S. Basu, RES  !

G. Hsil, NRR A. Behbahani, RES l J.' Perau, NRR A. Malliakos, RES I C. Berlinger, NRR J. Persensky, RES l

o-Appendix ill 2

' 453rd ACRS Meeting NRC Staff (June 3,1998)

S. Arndt, RES J. Kramer, RES '

T. King, RES i

U. Shoop, RES -

i S. Bahadur, RES C. Nilson, RES l

M. Mayfield, RES '

ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC ;

C. Thompson, DOE J. Dozier, NUS J. Scobel, Westinghouse M. Young, Westinghouse T. Long, Southem Nuclear '

M. Hammer, Northern Statas Power G. Sozzi, GE Nuclear Energy E. Eckert, GE Nuclear Energy W. Barber, McGraw Hill J. Beves, Northern States Power S. Hammer, Northem States Power j

D. Pappine, GE W. Marquino, GE L. Conner, DSA .

l

1 I

i Appendix lll 3 l 453rd ACRS Meeting ]

1 NRC Staff (June 4,1998) ,

J. Mitchell, OEDO l R. Meyer, RES U. Shoop,RES  !

H. Scott, RES J. Guttman, RES i M. Chatterton, NRR l H. Richings, NRR R. Frahm, NRR E. Kendrick, NRR L. Kopp, NRR E. Weiss, NRR T. Collins, NRR E. McKenna, NRR F. Akstulewicz, NRR S. Magruder, NRR M. Malloy, NRR T. Essig, NRR  :

G. Parry, NRR S. Lavie, NRR '

J. Schiffgen, NRR G. Holahan, NRR G. Bagchi, NRR S. Ah, NRR S. Dinsmore, NRR M. Rubin, NRR D. .Terao, NRR T. Kenyon, NRR l J. Sebrosky, NRR

. Appendix lli 4 453rd ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC J. Butler, NEl l

A. Wyche, SERCH '

H. Fontecilla, VA Power N. Chapman, SERCH J. Trotter, Polestar App. Tech.

C. Brinkman, ABB Combustion Engineering P. Negus, GE i J. Werl, McGraw-Hill I J. Mitman, EPRI G. Smith, NYPA  !

F. Ammecan, EPRI B. Jaquith, ABB-CE l R. Greybeal, Enertech B. Bradley, NEl H. Fish, NYPA A. McNeill, VA Power R. Fougerousse, Entergy M. Paterak, Entergy R. West, NEU d D. Garchow, PSE&G/WOG N. Closky, Westinghouno S. Fowler, Westinghousa K. Baker, Westinghouse K. Fleming, ERIN J. Dozier, NUS NRC Staff (June 5,1998)

T. Kenyon, NRR J. Sebrosky, NRR I

(

l

APPENDIX IV: FUTURE AGENDA

/ 'o UNITED STATIS f n NUCLEAR REGULATORY COMMISSION

• I ADVISORY COMM11 TEE ON REACTOR SAFEGUARDS

/ WASHtNGTON, D. C. 20655 June 16, 1998 SCHEDULE AND OUTLINE FOR DISCUSSION 454th ACRS MEETING JULY 8-10, 1998 WEDNESDAY, JULY 8, 1998, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

1) 8:30 8:45 A.M. Onenina Remarks by the ACRS Chairman (Open) 1.1) Opening Statement (RLS/JTL/SD) 1.2) Items of current interest (RLS/NFD/SD) 1.3) Priorities for preparation of ACRS reports (RLS/JTL/SD)

2) 8:45 - 10:30 A.M. BWR Extended Power Ucrate Aeolication (Open/ Closed) (TSK/PAB) 2.1) Remarks by the Subcommittee Chairman.

2.2) Briefing by and discussions with representatives of the General Electric Nuclear Energy (GE), Northern States Power Company (NSP), and the NRC staff regarding the GE extended power uprate program for operating BWRs, and the NSP application for a power level increase of 6.3 percent for the Monticello Nuclear Generating Plant.

[ Note: A portion of this session may be closed to discuss GE Nuclear Energy proprietary information.)

10:30 - 10:45 A.M. *** BREAK ***

3) 10 :4 5 - 12 :15 P.M. Proposed Revisions to.1Q,CFR 50.59 (Chances.

Tests and Experiments) (Open) (JJB/MTM) 3.1) Remarks by the Subcommittee Chairman.

3.2) Briefing by and discussions with representatives of the NRC staff regarding proposed revisions to 10 CFR 50.59, resolution of issues identified in the March 24, 1998 Staff j

Requirements Memorandum related to SECY-97-205, " Integration and Evaluation of Results from Recent Lessons Learned Reviews," and related matters.

Representatives of the nuclear industry will ,

provide their views, as appropriate.

l I

I I

2

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

l 4) 1:15 - 3:45 P.M. AP600 Desian (Open/ Closed) (JJB/TSK/NFD/PAB)

! 4.1) Remarks by the Subcommittee Chairman.

l 4.2) Briefing by and discussions with representatives of the Westinghouse Electric Company and the NRC staff regarding Westinghouse's application for certification of the AP600 design and the associated NRC staff's l evaluation.

[ Note: A portion of this session may be closed to discuss Westinghouse proprietary and safeguards information related to the AP600 design.]

'3:45 - 4:00 P.M. *** BREAK ***

5) 4:00 - 5:30 P.M. Fire Barrier Penetration Seals and Related Matters (Open) (DAP/AS)

! 5.1) Remarks by the Subcommittee Chairman.

5.2) Briefing by and discussions with representatives of the NRC staff regarding Supplement 1 to NUREG-1552,

" Fire Barrier Penetration Seals at Nuclear Power Plants," an Information Notice on " Inadequate Identification and Analysis of Required and Associated I Electrical Circuits Resulting in the Potential Loss of Post-Fire Safe-Shutdown capability," and related matters.

Representatives of the nuclear industry and other interested groups will provide their views, as appropriate.  ;

5:30 - 5:45 P.M. *** BREAK ***

6) 5:45 - 7:00 P.M. Precaration of ACRS Reoorts (Open)

Discussion of proposed ACRS Reports on:

6.1) AP600 Design Certification Application l (JJB/TSK/NFD/PAB)  !

6.2) BWR Extended Power Uprate Application (TSK/PAB) 6.3) Proposed Revisions to 10 CFR 50.59 (JJB/MTM) 1 l THURSDAY, JULY 9, 1998, CONFERENCE ROOM 2B3. TWO WHITE FLINT NORTH.

ROCKVILLE, MARYLAND l

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

(RLS/SD)

3

8) 8:35 - 10:30 A.M. BWR Pressure Vessel Shell Weld Insoections t (Open) (RLS/NFD)

. 1) Remarks by the Acting Subcommittee 8

Chairman.

8.2) Briefing by and discussions with representatives of the NRC staff and the BWR Vessel and Internals Project (BWRVIP) regarding the BWRVIP-05 report, "BWR Pressure Vessel Shell Weld Inspection Recommendations," and the associated NRC staff's evaluation.

10:30 - 10:45 A.M. *** BREAK ***

9) 10:45 - 12:15 P.M. Ooeratinc Plan for the NRC Office of Nuclear Reactor Reculation (NRR) (Open) (RLS/MME) 9.1) Remarks by the ACRS Chairman.

9.2) Briefing by and discussions with the NRR Director and his staff regarding the NRR Operating Plan and related matters.

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

10) 1:15 - 1:45 P.M. Future ACRS Activities (Open) (RLS/JTL/SD)

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

11) 1:45 - 2:00 P.M. Reconciliation of ACRS Comments and Recommendations (Open) (RLS , et al./SD, et al.)

Discussion of the responses from the NRC Executive Direc' tor for Operations (EDO) to comments and recommendations included in recent ACRS reports.

12) 2:00 - 2:30 P.M. Reoort of the Plannino and Procedures Subcommittee (Open/ Closed) (RLS/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 I the internal personnel rules and practices I i

of this Advisory Committee, qualification of candidates for ACRS membership, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.)

l l

4

. 13) 2:45 - 7:00 P.M. Preoaration of ACRS Reoorts (Open)

Discussion of proposed ACRS reports on:

13.1) AP600 Design Certification Application (JJB/TSK/NFD/PAB) 13.2) BWR Extended Power Uprate Application (TSK/PAB) 13.3) Proposed Revisions to 10 CFR 50.59 (JJB/MTM) 13.4) Supplement 1 to NUREG-1552 and an Information Notice associated with Fire Protection (DAP/AS) 13.5) BWR Pressure Vessel Shell Weld Inspections (RLS/NFD)

FRIDAY, JULY 10, 1998. CONFERIENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

14) 8:30 - 3:00 P.M. Precaration of ACRS Reoorts (Open)

(12:00-1 00 P.M. LUNCH) Continue discussion of proposed ACRS reporte listed under Item 13. l

15) 3:00 - 4:30 P.M. Technical Pacers for the Ouadricartite Meetina (Open)

Discussion of Technical Papers on:

'15.1) Safety of Future Nuclear Power Plants l (TSK) 15.2) Safety of Aging Plants (RLS) 15.3) Steam Generator Operating Experience (RLS) 15.4) Assessment of Computerized Systems (REU) 15.5) Safety of High Burnup and Mixed Oxide Fuels / Fuel Behavior Under Reactivity Induced Accidents (DAP) 15.6) Risk Significance of Low-Power and Shutdown Events (DAP) 15.7) Probabilistic Safety Assessment and Risk-Based Regulation (GA)

16) 4:30 - 5:00 P.M. Miscellaneous (Open) (RLS/JTL/SD)

Discussion of matters related to the conduct of Committee activities and matters and specific issues that were not completed during previous meetings, as time and availability of information permit.

NOTE:

e' 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.

e Number of copies of the presentation materials to be provided to the ACRS - 35.

APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMl'ITEE

[ 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 HANDOUT 3 AGENDA DOCUMENTS ITEM NO.

1 Ooenina Remarks by the ACRS Chairman

1. Items of Interest, dated June 3-5,1998 2 AP600 Desian

2. AP600 Test and Analysis Program: Reactor Coolant System Remaining issues, dated June 3,1998, presented by M. Y. Young, Westinghouse Electric Company [Viewgraphs)

3. AP600 Level 2/3 PRA and Severe Accident Analyses, dated June 3,1998, presented by James H. Scobel, Westinghouse Electric Company

[Viewgraphs)

4. Why no leak-before-break for feedwater piping, dated, June 3,1998, presented by Shou-nien Hou, NRR [Viewgraphs)

5. AP600 Containment Design for Severe Accidents, dated June 3,1998,  ;

presented by Robert L. Pall, NRR [Viewgraphs)  !

6. Staff Approval of PARS, dated June 3,1998, presented by Michael R. i Snodderly, NRR [Viewgraphs) i

7. AP600 SSAR, dated June 3,1998, presented by Michael M. Corletti, ,

Westinghouse Electric Company [Viewgraphs) l

8. SSAR Chapter 17, Quality Assurance, dated June 3,1998, presented by Brian A. McIntyre, Westinghouse Electric Company [Viewgraphs)

9. SSAR Chapter 3, Design of Structures, Components, Equipment, and Systems, dated June 3,1998, presented by Brian A. McIntyre,

. Appendix V 2 453rd ACRS Meeting Westinghouse Electric Company [Viewgraphs) {

-3 Human Performance Plan

10. Memorandum from Thomas King, RES, to John Larkins, Executive Director, ACRS, dated May 29,~ 1998: Briefing on NRC's Human Performance Plan.[ Handout) [ NOTE: PREDECISIONAL: Do not release without prior authorization)

11. Human Performance Plan, dated June 3,1998, presented by J. J.

Persensky [Viewgraphs) 4- Core Research Caoabilities at NRC i

12. Core Research Capabilities, dated June 3,1998, presented by Lloyd Donnelly, RES [Viewgraphs) j 5 BWR Extended Power Uorate Anniication  ;

13. GE BWR Extended Power Uprate, dated June 3,1998, presented by E.C.

Eckert [Viewgraphs)

14. Monticello presentation, undated, presented by Mike Hammer, Pat Riedel, and Steve Hammer [Viewg~raphs)

15. ACRS Meeting on Monticello Power Uprate Program, dated June 3,1998, presented by T. J. Kim, NRR [Viewgraphs)

S Aaencv-Wide Plan for Hioh-Bumun Fuel

16. Agency Program Plan for High Bumup Fuel, dated June 4,1998, presented by Ralph Meyer, RES [Viewgraphs) 9 Operatina Plan for the NRC Technical Trainina Proarams

17. Briefing for the ACRS on the Operating Plans for NRC Technical Training Programs, dated June 4,1998, presented by Kenneth A. Raglin, AEOD/TTD

_[Vienegraphs) 10 Prooosed Modifications to 10 CFR 50.59. Chanoes. Tests. and Exoeriments

... . Appendix V 3

' 453rd ACRS Meeting

18. Status of 10 CFR 50.59 Rulemaking, dated June 4,1998, presented by Eileen McKenna, NRR [Viewgraphs) 11 Pronosed Final Standard Review Plan (SRP) Section and Reaulatorv Guide for Risk-Ir'errre inservice insoection of Pining

19. Risk-informed Inservice inspection Programs for Piping, dated June 4,1998, presented Tom King, RES [Viewgraphs)

20. Industry Views on Risk-informed inservice Inspection, dated June 4,1998, presented by Biff Bradley, Nuclear Energy institute [Viewgraphs) 12 Future ACRS Activities

21. Future ACRS Activities - 454th ACRS Meeting, July 8-10,1998 [ Handout

1. 12.1]

13 Reconciliation of ACRS Comments and Recommendations 22.

Reconciliation of ACRS Comments and Recommendations [ Handout #13.1) 15 Reoort of the Planning and Procedures Subcommittee

23. Final Draft Minutes of Planning and Procedures Subcommittee Meeting -

June 2,1998 [ Handout #15.1]

. Appendix V 4 453rd ACRS Meeting MEFTING NOTEBOOK CONTENTS 188 DOCUMENTS 2 AP600

1. Table of Contents

2. Proposed Agenda / Schedule

3. Project Status Report, dated [Intemal Committee Use Only: Predecisional Material Attached]

4. Report from T.S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated August 15,1996: SECY-96-128, " Policy and Key Technical lasues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design"

5. Letter from R.L. Seale, Chairman, ACRS, to L. Joseph Callan, Executive Director for Operations (EDO), dated February 19,1998: Interim Letter on the Safety Aspects of the Westinghouse Electric Company Application for Certification of the AP600 Plant Design

6. Letter from R.L. Seale, Chairman, ACRS, to L. Joseph Callan, Executive Director for Operations (EDO), dated April 9,1998: Safety Aspects of the Westinghouse Electric Company Application for Certification of the AP600 Plant Design -Interim Letter 2

7. Memorandum from P. Boehnert, Senior Staff Engineer, ACRS, to T. Kress, Chairman, Thermal Hydraulic and Severe Accident Phenomena Subcommittee, dated May 18,1998: Minutes of the Thermal Hydraulic and Severe Accident Phenomena Subcommittee Meeting, May 11-12, 1998 -

Rockville, Maryland

8. Letter from Chang Chen, Apollo Consulting Inc., to Noel Dudley, Senior Staff Engineer, ACRS, dated May 21,1998: Westinghouse AP600 Standard Analysis Report, Revision 22, April 6,1998, and the ACRS Subcommittee l Meeting at the NRC Rockville MD Office, on May 14,1998

9. Letter from Robert J. Budnitz, Future Resource Associates, Inc., to Noel Dudley, Senior Staff Engineer, ACRS, dated May 10, 1998: Consultant Report on the Extemal Events Portion of the AP600 Probabilistic Risk l Assessment 3 Human Performance Plan

10. Report from R.L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated February 13,1997: Human Performance Program

E I

'

• Appendix V 5

. ~

.453rd ACRS Meeting l

I Plan' l

11. Letter from R.L. Seale, Chairman, ACRS, to L. Joseph Callan, Executive  :

Director for Operations (EDO), dated October 8,1997: Human Performance j

. and reliability implementation Plan i

12. ACRS Questions Concoming the Human Performance Plan, May 10,1998  !

4 Core Research Canabilities at NRC I

13. SECY-98-076, " Core Research Capabilities, dated April 9,1998 '[ NOTE: i PREDECISIONAL: Do not release without prior authorization)

14. Staff Requirements Memorandum dated June 6,1997: Methodology and Criteria for Evaluating Core Research Capabilities

15. SECY-97-075, dated April 2,1997: Methodology and Criteria for Evaluating Core Research Capabilities 5 BWR Extended Power Uorate Aeolication

16. ACRS letter from David Ward, Chairman, ACRS, to James Taylor, EDO, dated September 17,1992: General Electric Nuclear Energy Power Uprate Program / Fermi, Unit 2 Power increase Request 4

17. Memorandum from E. Adensam, NRR, to J. Larkins, ACRS, dated May 14, 1998, transmitting: NRC Staff Safety Evaluation Related to Northem States Power Company Amendment Request to Monticello Nuclear Generating  :

Plant - [ NOTE: PREDECISIONAL: Do not release without prior I authorization)

18. Memorandum from E. Adensam, NRR, to J. Larkins, ACRS, dated May 18, 1998, transmitting: NRC Staff Position Related to General Electric Licensing ;

Topical Report NEDC-32523P, Generic Evaluations of General Electric BWR Extended Power Uprate [ NOTE: PREDECISIONAL: Do not release without '

- prior authorization] .  !

8 - Acency-Wde Plan for Hioh-Bumun Fuel

19. Staff Requirements Memorandum, dated April 16,1997: Briefing on High-l Bumup Fuelissues

E Appendix V 6 l 453rd ACRS Meeting

20. Memorandum from L. Joseph Callan, EDO to the Commission, dated July 15,1997: Regulatory Guidelines and Licensing Criteria for High Bumup Fuel (M970325)

21. Memorandum from Thomas L. King, RES, to J. Larkins, ACRS, dated May l 22,1998: Transmittal of Advance Copy of Agency Program Plan for high  ;

Bumup Fuel [ NOTE: PREDECISIONAL: Do not release without prior {'

authorization]

9 Ooeratina Plan for the NRC Technical Trainina Proarams i

22. Memorandum from L. Joseph Callan, Chair, Executive Council, to Jack W.

Roe, NRR, undated: Training Activities

23. Excerpt from SECY-98-096, addressing NRC Staff Training, dated May 1,  !

1998: Quarterly Status Report on the PRA implementation Plan l

24. Excerpt from Annual Report of the AEOD Technical Training Division (TDD) for Fiscal Year 1997, K. Raglin, Director, TTD 10 Prooosed Modifications to 10 CFR 50.59. Chanoer. Tests. and Exoeriments

25. Staff Requirements, dated March 24,1993: SECY-97-205-integration and Evaluation of Results from Recent Lessons Leamed Reviews [ NOTE:

PREDECISIONAL: Do not release without prior authorization)

26. Letter from R. Beedle, Nuclear Energy Institute (NEI), to Shirley Ann Jackson, Chairman, NRC, dated April 16, 1998: 10 CFR 50.59 Safety Evaluations and 10 CFR 50.71 (e) FSAR Updates

27. Letter from S, Collins, NRR, to R. Beedle, NEl, dated May 12,1998: 10 CFR 50.59 Safety Evaluations and 10 CFR 50.71 (e) Final Safety Analysis Report Updates

28. Staff requirements Memorandum dated January 20, 1998: Briefing on integration and Evaluation of Results from Recent Lessons-Leamed Rev'ews (including 50.59 Process improvements) (SECY-97-205)

29. Comments from S. Jackson, Chairman, NRC, to J. Hoyle, SECY, dated January 5,1998: SECY-97-205, Integration and Evaluation of Results from l Recent Lessons Learned Reviews [ NOTE: INTERNAL ACRS USE ONLY:

n i j

i Appendix V 7 {

453rd ACRS Meeting '

l Do not release without prior authorization]

30. Letter from S. Collins, NRR, to R. Beedle, NEl, dated January 9,1998: NEl Guidelines for 10 CFR 50.59 Safety Evaluations 1

31. Letter from R. Beedle, NEl, to S. Collins, NRR, dated January 16,1998:

NEl 96-07 .

1

32. Letter from L. Joseph Callan, EDO, to R.L. Seale, Chairman, ACRS, dated January 8,1998: Proposed Revisions to 10 CFR 50.59 (Changes, Tests, i and Experiments) J l

33. Report from R. . L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated December 12,1997: Proposed Revisions to 10 CFR 50.59 (Changes, Tests, and Experiments)

34. Report from R. L.' Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated October 9,1997: Proposed Changes to 10 CFR l

50.59 and Proposed Revision 1 to Generic Letter 91-18 '

35. Report from R. L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated April 8,1997: Proposed Regulatory Guidance Related 'to implementation of 10 CFR 50.59 (Changes,. Tests, and l Experiments)

/

36. Summary of the Proposed Rule 10 CFR Parts 50,52, and 72 and Complete Text of Revised Rule Language as proposed including the Regulatory Analysis 11 Prooosed Final Standard Review Plan ERN Section and Reaulatorv Guide for Risk-Informed Inservice insoection of Pinina

37. Report from R. L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated July 14, 1997: Proposed Regulatory Guide and Standard Review Plan Chapter for Risk-informed, Per'ormance-Based inservice inspection

38. Letter from L. -Joseph Callan, EDO, to R. L. Seale, Chairman, ACRS, dated August 6,1997: Proposed Standard Review Plan Section 3.9.8 and Regulatory Guide DG-1063 for Risk-Informed inservice inspection of Piping

[-

L l.

c Appendix V 8 453rd ACRS Meeting l

, I

39. Memorandum from J. Larkins, ACRS, to L. Joseph Callan, EDO, dated May l

12,1998: Proposed Human Performance Plan and Proposed Final Standard Review Plan Section and Regulatory Guide for Risk-informed Inservice ,

inspection of Piping l 40. Memorandum from Noel F. Dudley, ACRS Staff, to ACRS Members, dated May 22,1998: CRGR meeting to review proposed SRP Section 3.9.8 and ,

l regulatory Guide 1.178 for risk-informed inservice inspection of piping ;

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