ML20059C886

"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.

Summary of 399th ACRS Meeting on 930708-09 in Bethesda,Md Re NRC Regulatory Review Group Rept,Application of PRA Methods for Ranking Movs,Draft RGs DG-1023 & DG-1025 & Debris Plugging of Emergency Core Cooling Suction Line Strainers

ML20059C886
Person / Time
Issue date:	09/08/1993
From:	Wilkins J Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2887, NUDOCS 9311020049
Download: ML20059C886 (40)

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{{#Wiki_filter:____ - G u s-a&T7 1. -fpb/bp1/43 Certified Bv: Date Issued: 08/18/93 J. Ernest Wilkins, Jr. 09/08/93 TABLE OF CONTENTS MINUTES OF THE 399TH ACRS MEETING July 8-9, 1993 Pace I. Chairman's Report 1 II. NRC Regulatory Review Group Report. 1 III. Application of Probabilistic Risk Assessment Methods for Ranking Motor-Operated Valves 3 IV. Draft Regulatory Guide DG-1023, " Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb." 4 V. Draft Regulatory Guide DG-1025, " Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" 5 VI. Debris Plugging of Emergency Core Cooling Suction Line Strainers. 7 ) VII. Reactor Operating Experience: Steam Header Rupture at Sequoyah Unit 2 10 VIII. Report on the Planning and Procedures Subcommittee Meeting. 11 IX. Plans for Completing the ACRS Review of the Advanced Boiling Water Reactors (ABWR) Standard Safety Analysis Report (SSAR) 13 X. Reconciliation of ACRS Comments and Recommendations 14 XI. Miscellaneous 15 XII. Executive Session 16 A. Reports, Memorandum and Letter B. Future ACRS Activities 02(r018 C. Future Meeting Agenda o Dnsid1TED ORIGINAL d Certiflod By _ 9311020049 930908 P \\ a PDR ACRS KI pyg y BB7

d t, -, ?.,1 \\ %p ( I t i j d Cd c.b d MINUTES OF THE 399TH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS l JULY 8-9, 1993 BETHESDA, MARYLAND \\ The 399th meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Maryland, on July 8-9, 1993. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. The meeting was open to public attendance, except for a portion that dealt with the election of a new Committee Officer and other matters of a personal nature. There were no written statements nor requests for time to make oral statements from members of the j public regarding the meeting. A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W., Washington, D.C. [ Copies of the transcript ) are available for purchase from Ann Riley & Associates, Ltd., 1612 K Street, N.W., Washington, D.C. 20006.) ATTENDEES l ACRS Members: Dr. J. Ernest Wilkins, Jr. (Chairman), Mr. James Carroll (Vice-Chairman), Mr. William Lindblad (Member-at-Large), Dr. Ivan Catton, Mr. Peter Davis, Dr. Thomas Kress, Dr. Harold

iewis, Mr. Carlyle Michelson, Dr. Robert Seale, and Mr. Charles Wylie.

[For a list of other attendees, see Appendix III.] I. CHAIRMAN'S REPORT (Open) 1 [ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.) Dr. J. Ernest Wilkins, Jr., Committee Chairman, opened the meeting at 8:30 a.m. and briefly reviewed the schedule for the meeting. Dr. Wilkins identified a number of items that he believed to be of interest to the Committee, including: e Dr. Wilkins introduced Dr. William J. Shack. Dr. Wilkins observed that, pending approval by the Commission, Dr. Shack can participate in this meeting as a Committee member, but cannot vote. II. NRC REGULATORY REVIEW GROUP REPORT (Open) [ Note: Mr. M. Dean Houston was the Designated Federal Official for this portion of the meeting.] Dr. Harold Lewis, Chairman of the Regulatory Policies and Practices Subcommittee, indicated that the Regulatory Review Group Report

g 399th ACRS Meeting 2 July 8-9, 1993 issued for public comment was the subject matter for discussion during this portion of the meeting. He further noted that the discussion would focus on one of their recommendations regarding proposed rulemaking for changes to 10 CFR 50.54. He stated that these matters had been discussed at the Regulatory Policies and Practices Subcommittee meeting on July 7, 1993. Mr. Frank Gillespie, Group Task Leader, NRR, indicated that the Regulatory Review Group (RRG) had been established to conduct a-comprehensive and disciplined review of nuclear power reactor regulations and related processes, programs, and practices with-special attention placed on the feasibility of substituting performance-based requirements and guidance founded on risk insights for prescriptive requirements and guidance. He reviewed the current licensing basis and the areas of regulations where changes were under the licensee control. He indicated that the RRG recommendation with the greatest impact is one that addresses the process for changes under 10 CFR 50.54, " Conditions of Licenses." Such aspects as quality assurance, safeguards, and emergency preparedness are currently in this category and the RRG is proposing to place fire protection into this category as well. Mr. Gillespie briefly discussed the examination of risk-based regulations. He discussed the status of current usage (both domestic and foreign), considerations and constraints, and categories of use of risk information. Mr. Gillespie summarized the presentation with a listing - of management insights, as follows: Many areas for improvement Staff must be receptive to changes Prescriptive rules should not be replaced with prescriptive guidance Inspectors, reviewers and industry staff need new guidance i Utilities have a major role in causing change: Identify specific problems Identify specific solutions i Be persistent Conclusior-l The Committee provided a report on this matter, dated July 15, 1993, to Chairman Selin. The report indicated that the RRG had-done well and provided comments on broader policy issues.

8 I g 399th ACRS Meeting 3 July 8-9, 1993 III. APPLICATION OF PROBABILISTIC RISK ASSESSMENT METHODS FOR RANKING MOTOR-OPERATED VALVES (Open) [ Note: Mr. Herman Alderman was the Designated Federal Official for this portion of the meeting.] Dr. Gerald Weidenhamer, Office of Nuclear Regulatory Research (RES), stated that this discussion concerns research on the topic of probabilistic risk assessment (PRA) based approaches for prioritizing motor-operated valves (MOV). The genesis of this activity was a request from the NRR Mechanical Engineering Branch for research support to determine whether MOVs could be prioritized on a risk-importance basis. This capability would assist the regulatory staff in its inspection efforts related to Generic Letter 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance." Mr. Weidenhamer noted that RES contracted Dr. Vesely, Science Applications International Corporation, to investigate whether the aging risk-based prioritization method that research previously developed under the Nuclear Plant Aging Research Program in 1990 could be used for this effort. After Dr. Vesely agreed that this could be accomplished, he was instructed to pursue a cost-effective approach for a short duration. In response to a question asking if the risk was public risk or core damage, Mr. Weidenhamer replied that it was both. He said that it is core damage frequency and level-2 PRA considerations. Dr. Vesely said that the objective of a PRA-based prioritization is to identify those critical MOVs that need to be tested and maintained to control the risk. An addj e ' onal objective is to evaluate different prioritization approa mae e at can be used and that have been proposed by industry and in the field. Some cases studied are as follows: e All MOVs in the PRA failed e Individual MOVs failed Groups of MOVs with common cause failure e I MOVs with increased failure rates e Dr. Vesely discussed some specific points of this work. The PRA only covers a limited set of MOVs. It does not cover all of the MOVs addressed in Generic Letter 89-10. The results will vary depending on whether you use a level 1 or level 2 PRA. Common cause failures interaction can include additional MOVs as.being important. Shutdown risk contributions, that are not identified in

.e s 399th ACRS Meeting 4 July 8-9, 1993 i a normal PRA, are identified. Because the PRA is incomplete, deterministic considerations have to be integrated to complete the prioritization. He noted that this PRA does encompass external risk contributions. In response to a question, Dr. Vesely said that this PRA does include internal floods. In response to a question whether this study had considered the cases of valves that had not totally closed or totally opened, Dr. Vesely replied that they had not addressed that level of subtlety. Dr. Vesely concluded that: PRA based approaches can support Generic Letter 89-10. o PRA-based approaches that use standard PRA techniques need e better validation. _ Conclusion This briefing was for information only. No action was taken by the Committee. IV. DRAFT REGULATORY GUIDE DG-1023, " EVALUATION OF REACTOR PRESSURE VESSELS WITH CHARPY UPPER-SHELF ENERGY LESS THAN 50 FT-LB." (Open) [ Note: Mr. Elpidio Igne was the Designated Federal Official for this portion of the meeting.) Dr. Robert L. Seale, Chairman of the Subcommittee on Materials and Metallurgy, noted that the Subcommittee met on June 29, 1993, to discuss these proposed draf t guides with representatives of the NRC staff. NRC Staff Presentation Mr. Michael Mayfield, RES, stated that the purpose of Regulatory Guide DG-1023 is to provide acceptance criteria and evaluation, e.g., numerical examples methods acceptable to the NRC staff for demonstrating margins equivalent to those of Appendix G of the ASME Code for those beltline materials whose Charpy upper-shelf energy falls below the regulatory limit provided in Appendix G to 10 CFR Part 50. He noted that publication of regulatory guidance at this time is necessary because no guidance exists, and there are nuclear power plants, both PWR and BWR, with upper-shelf energy calculated to be presently operating below the 50 ft-lb regulatory limit (15 plants) and three plants projected to fall below the regulatory limit before the end of the current license period. Without regulatory guidance, each affected licensee must submit a plant 1 j l

.b b 399th ACRS Meeting 5 July 8-9, 1993 specific analysis, including acceptance criteria and evaluation methods, and the staff must evaluate each submittal without benefit of noted acceptance criteria and approved evaluation methods. In response to a question from Mr. Michelson, Mr. Mayfield stated that the guide focuses on the beltline region of the reactor pressure vessel and not the vessel internals. Mr. Mayfield stated that the acceptance criteria proposed in the ASME Code case are identical with those proposed in this draft regulatory guide. Further the guide analysis procedures for Service Levels A and B (normal and upset) are taken from the code case. However, the guide provides procedures applicable to Service Levels C and D (transient and f aulted). In addition, the guide provides specific guidance on appropriate material properties and on the selection of transients for considerations, whereas the code case does not provide these procedures and guidance. Mr. Mayfield noted that the NRC staff has compared the proposed regulatory guide procedures to other procedures that are being developed by various organizations, e.g., the ASME Section XI. The comparison was very favorable, with the procedures proposed in the draft guide i predicting lower acceptable Charpy upper-shelf energy values than would be predicated by the other procedures that were less rigorous and, consequently, more conservative. In reply to a member's q2estion, Mr. Mayfield stated that the variability in the margins is about 10 percent. In reply to a question from Dr. Shack on the basis of plants calculating the Charpy energy for the 18 affected plants, Dr. Shah Malik, RES, stated that surveillance data and Regulatory Guide 1.99 were used. Mr. Mayfield asked for Committee endorsement to release the proposed guide for public comment. Mr. Lindblad mentioned that the presentation was very good and Dr. Shack agreed that the proposed 1 draft guide fills a need for providing guidance for more consistent j results. V. DRAFT REGULATORY GUIDE DG-102 5. " CALCULATIONAL AND DOSIMETRY METHODS FOR DETERMINING PRESSURE VESSEL NEUTRON FLUENCE" (Open) [ Note: Mr. Elpidio Igne was the Designated Federal Official for this portion of the meeting.) j Mr. Mayfield stated that the objective of this proposed draf t guide is to provide state-of-the-art calculation and measurement procedures that. are acceptable to the staff for determining pressure vessel fluence. He noted that.theLproposed guide is,not intended to replace methods that have already been accepted by.the staff.

n I g e 399th ACRS Meeting 6 July 8-9, 1993 Mr. Mayfield mentioned that current fluence calculational methods submitted by licensees vary widely in reliability, accuracy and conservatism. In some cases the staff mandates the use of bias factors (more conservatism) because of the need for uncertainty analysis. However, Mr. Mayfield noted that there is a concern about adding unnecessary levels of conservatism that can result in operational problems, e.g., restrictive pressure-temperature limits and low-temperature overpressure protection set points may potentially lead to adverse impact on safety, or unnecessarily approaching the PTS screening and Charpy upper-shelf energy criteria could force unnecessary reactor vessel annealing or plant closure. Mr. Michelson commented on the relative rupture strengths of the pressure vessel and connected piping, e.g., recirculation piping system, at the shutdown mode of operation when the pressure may be high and temperature low. Mr. Mayfield stated that the focus is on ductile failure and not brittle failure as alluded to by Mr. Michelson. Further, Mr. Mayfield noted that the data on brittle failure of piping system are not available. Mr. John Carew, Brookhaven National Laboratory, presented details of the calculation and measurement of pressure vessel fluence for the proposed draft guide. He mentioned that neutron fluence undergoes several decades of attenuation to the vessel.

Further, vessel fluence calculation is very sensitive to 1) material and geometry representations of the core and vessel internals, 2) space / energy neutron source, and 3) transport calculation numerical schemes.

Detailed multigroup/ multi-dimensional analysis is also required for an accurate fluence estimate. Best-estimate, rather than bounding, approach and absolute fluence calculation, rather than extrapolation of measurement, were used in the calculation of vessel fluence. Mr. Carew noted that fluence calculational methods must be qualified and fluence uncertainties and biased be deter-mined. Mr. Carew noted that the expected impact of the dosimetry guide is to reduce the fluence calculational uncertainty to less than 20 percent by improved nuclear and modeling data, benchmark compari-sons and performing calculation uncertainty analysis. Dr. Shack commented on the method of calculating the through-vessel-wall fluence by using the J flux curve and bypassing Regulatory Guide 1.99. Further, Dr. Shack noted that this method would be less conservative than the results obtained by using Regulatory Guide 1.99. Mr. Mayfield stated that the through wall fluence is obtained by calculating the fluence at the inner surface and attenuating it through the wall based on Regulatory Guide 1.99. Mr. Mayfield mentioned that the through wall attenuation issue is being discussed further by the staff.

i e 399th ACRS Meeting 7 July 8-9, 1993 Conclusion The Committee prepared and issued a report on these proposed draft regulatory guides to Chairman Selin. The Committee expressed interest in reviewing the public comments and the staft's resolu-tion of these comments before the release of these guides in final form. VI. DEBRIS PLUGGING OF EMERGENCY CORE COOLING SUCTION LINE STRAINERS (Open) [ Note: Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.] Mr. James C. Carroll, Chairman of the Plant Operations Subcommit-tee, introduced this topic to the Committee. He reviewed the recent events that occurred at the Barseb8ck Nuclear Power Plant-Unit 2 in Sweden and the Perry BWR-6 Nuclear Power Plant where the suction strainers to the ECCS pumps became clogged due to ingestion of debris from the containment suppression pools. Mr. Carroll said that NRR representatives were present to discuss both the details of these events and proposed regulatory actions stemming from same. NRC Staff Presentation Mr. Martin Virgilio, NRR, noted that the issue of containment emergency sump blockage was resolved via closecut of Unresolved Safety Issue (USI) A-43 in the mid-1980s. Resolution actions consisted of revisions to Regulatory Guide (RG) 1.83. However, the new provisions of RG 1.83 were not backfitted to current nuclear power plants. Following the Barseb8ck event on July 28, 1992, NRR began a reevaluation of A-43 to ensure the resolution positions are still valid. Specifically, the staff will perform a reexamination of the issue of blockage of suction strainers and debris ingestion by the ECCS pumps. New regulatory requirements may be prescribed, pending the results of the above reexamination effort. Recent Event Information Recent germane events occurring at U.S. BWR plants were noted by-Mr. John Hickman, NRR. In 1988, the Grand Gulf Nuclear Power Plant suppression pool ECCS suction strainers were found clogged with sediment. Due to a failure to maintain pool cleanliness, the problem recurred in 1989. Subsequently, cleanliness requirements were established and the problem has not recurred since. The-lesson learned was that normal debris generated during operations .j can result in clogging and (minor) reduction in pump suction capability. l .) i

i 399th ACRS Meeting 8 July 8-9, 1993 At the Perry Nuclear Power Plant, debris was identified on the floor of the suppression pool in May 1992. Following cleaning of the pool in January 1993, the suction strainers were found deformed and cracked. They were replaced. Subsequent to use of suppression pool cooling in March 1993, the strainers were again found coated with debris. Tests showed a significant drop in suction pressure (6 psi over nine hours). The strainers were replaced with larger (area) strainers, backflush capability was provided, the pool was cleaned and net positive suction head monitoring initiated. Mr. Carroll asked if the licensee evaluated the impact of hydrodynamic loads on the larger strainers. Mr. Richard Barrett, NRR, indicated that the staff will investigate this item. A video film was shown to the Committee that was made during the inspection of the Perry suppression pool (using a robotic camera device). The video showed the pool debris and the damaged strainers. The NRC issued Bulletin No. 93-02, dated May 11, 1993, subsequent to the Perry event. The debris of concern consisted of fibers from air filter material that had (somehow) fallen into the pool. Mr. Hickman indicated that the existence of fibrous debris in a suppression pool had not been recognized by the staff as a potential problem. Mr. Michelson noted that this problem was indeed pointed out to the staff during the ACRS review of the initially proposed USI A-43 resolution position. Bulletin No. 93-02 contained a request that all licensees identify sources of fibrous material subject to being introduced into the suppression pool / containment sumps, take actions to ensure the functional capability of the ECCS and promptly remove the offending material. Licensee responses to Bulletin No. 93-02 have been received. The majority of the licensees either do not have a problem or have committed to the removal of suspect material. Six licensees require review by the staff. Another 12 licensees will need to submit additional information. NRC will conduct audit inspections to ensure the problem is satisfactorily addressed. Reculatory Action to Evaluate Blockace Issue Mr. Barrett, NRR, noted that staf f actions are underway. The staf f plans to evaluate the implications of the above events and determine if the conclusions supporting resolution'of USI A-43 are still valid or whether additional regulatory action is needed. Mr. Barrett said that the staff conducted a survey to determine if the U.S. BWR plant designs are susceptible to the problems identified at Barseb8ck event. The conclusion was that this type of event cannot be ruled out, per se. In addition, the following points were noted:

399th ACRS Meeting 9 July 8-9, 1993 The lessons learned from the Perry event were that. the existence of sediment in the suppression pools is a reality and that complex interactions of fibrous material act to aggravate the extent of strainer blockage out of proportion to its volume. Tests conducted in Sweden following the Barsebuck event indicate that the assumptions specified in RG 1.82 for evaluation of the extent of debris blockage expected in U.S. plants may be nonconservative; i.e., based on these test results, such parameters as the amount of debris generated, transport of said debris to the sump / suppression pool, and resultant pump head loss expected appear to be worse than what was seen in the U.S. tests conducted to support resolu-tion of USI A-43. Given the above, the NRR staff has initiated the following actions: e RES will perform an analytical study, in cooperation with Olin Laboratories (the initial test contractors for the A-43 related tests noted above), to evaluate the amount of debris generated given a LOCA. Using an as-built' BWR plant configu-ration, a spectrum of break sizes and locations will be evaluated. A debris transport model will be developed that will evaluate the lessons learned from the recent U.S. and Swedish events, and will use additional relevant information available, including that from both the Swiss nuclear testing authori-ties and U.S. insulation vendors. The above work should take about six months to complete. Consider-ation of the need for backfitting additional regulatory require-ments will depend on the results of the transport model development effort. Mr. Carroll thanked the NRR staff Members for their efforts relative to the above matter. Mr. Barrett indicated, in response to Mr. Michelson, that the staff will keep the Committee fully informed regarding the outcome of this issue. Conclusion The NRC staff will keep the Committee informed regarding the outcome of its reevaluation of the. issue of containment emergency sump blockage and the decision regarding the need for~ additional regulatory action. Inquiry as to the status of the. staff's reevaluation effort appears timely after the first of the. year.

0 s 399th ACRS Meeting 10 July 8-9, 1993 VII. REACTOR OPERATING EXPERIENCE: STEAM HEADER RUPTURE AT SEOU'OYAH UNIT 2 (Open) [ Note: Mr. Douglas Coe was the Designated Federal Official for this portion of the meeting.) Mr. James C. Carroll, Chairman of the Plant Operations Subcommit-tee, introduced this topic to the Committee by noting that the Committee's interest was more on the effects of the steam release, as opposed to the erosion / corrosion aspects of it. NRC Staff Presentation Mr. Robert Dennig, NRR, introduced Mr. Jerome Blake, Region II. Mr. Blake was the Leader for the Sequoyah Nuclear Power Plant Unit 2 Augmented Inspection Team (AIT). He described the steam header rupture event that occurred on March 1, 1993, and is documented in AIT report 50-3238/93-10. The event was initiated when a techni-cian incorrectly pulled a feedwater control valve fuse during maintenance, causing the valve to close. The resulting feedwater system perturbation caused a minor water hammer that impacted the-extraction steam line, rupturing the piping that had already been severely weakened due to erosion and corrosion. The resulting steam release was drawn into the main generator voltage regulator cabinet by its cooling fans; causing a malfunction that overexcited the generator to about 20% above normal voltage output. This high voltage was present on all plant busses supplied from the main-generator for approximately three minutes and 38 seconds, including both divisions of safety-related Class 1E busses. However, the AIT determined that all safety-related equipment was rated for a minimum of 25% over nominal voltage; thus, no. such equipment exceeded its maximum rating. Mr. Peter Kang,

NRR, stated that Westinghouse was unable to-identify any lasting failure within the voltage regulator cabinet following the event.

He noted that some circuit cards had protective coatings on them, but some did not.- Mr. Michelson asked what type of testing was performed to verify that safety-related electrical equipment was not damaged. Mr. Blake. responded that testing included relay calibration checks, battery charger / inverter inspections, megger checks on motors, and motor operated valve time / current signature checks. In addition, the large transformers between the main generator and safety-i related busses were tested for gas content from overheating. Mr. Blake noted that the AIT found the erosion / corrosion detection program to be fragmented within the licensee's organization and given relatively low priority. This contributed to the omission, j in EPRI Checkmate (i.e., erosion / corrosion detection computer

l 399th ACRS Meeting 11 July 8-9, 1993 i program), of six three-inch diameter vent lines that enter the ten inch diameter extraction header just upstream of the rupture. The effect of this was to significantly underestimate the moisture content of the steam in the downstream extraction pipe, and therefore underestimate the aggressiveness of the erosion / corrosion that occurred. Mr. Carroll noted that the NRC had written a strong letter to NUMARC regarding the problems being found with implementation of erosion / corrosion programs. Mr. David LaBarge, Sequoyah Project Manager, NRR, answered that NUMARC had responded to the NRC letter by informing the industry of NRC concerns. The licensee's corrective actions include upgrading the erosion / corrosion program, small and large diameter piping replacement where needed, and installation of a high voltage trip on the main generator set at 15 percent overvoltage. j Mr. Thomas Koshy, NRR, discussed the NRC generic communications related to erosion / corrosion problems. In addition, responding to a question from Mr. Michelson, he noted that reactor protection systems are located in areas generally free from potential steam line breaks. Mr. Michelson pointed out that some plants, such as

BWRs, install electronic control equipment within secondary containment, much of it being for non-safety controls.

Mr. Koshy stated that safety-related equipment in such areas is environmen-tally qualified. Conclusion This briefing was for information only. No Committee action was taken. VIII. EEPORT ON THE PLANNING AND PROCEDURES SUBCOMMITTEE MEETING (open) (Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.] As a result of the Planning and Procedures Subcommittee meeting held on July 7, 1993, the following items were brought to the attention of the Committee: e The members were informed on the current status of Dr. Shack's appointment as a new committee member. i e +- - - - -. v g

399th ACRS Meeting 12 July 8-9, 1993 The members discussed a request to use two consultants for up e to 20 days to review the Probabilistic Risk Assessment (PRA) of the Advanced Boiling Water Reactor. Dr. Wilkins recom-mended that the Committee authorize up to 20 days total. The members concurred. As follow on to Dr. Wilkins' meeting with the NRR Director, e Dr. Thomas Murley, it was suggested that the ACRS Chairman meet with the NRC Office Directors (NRR, RES, and AEOD) and the Deputy Executive Director for Nuclear Reactor Regulation to discuss the relationship between the Committee and the NRC staff. Dr. Wilkins suggested that Messrs. Carroll, Lindblad and Larkins also attend the proposed meeting. This meeting will be scheduled at an appropriate time. An options paper on alternatives for the future of the Fellowship Program was discussed. The Ad Hoc Fellowship Subcommittee favored combining Options 3 (three Senior Fellows are appointed for two-year terms with optional reap-pointments to second two-year terms) and 5 (stipends to universities where individual members are employed). The merits of each option were examined in some detail. .l Dr. Larkins was directed to prepare a draft Manual Chapter '{ that defines the objectives, responsibilities, requirements, 1 and procedures to implement and operate a Fellowship Program along the lines recommended by the members. The draft Manual Chapter will be reviewed by the Ad Hoc Fellowship Subcommit-tee and the full Committee, As a result of his meeting with Dr. Murley on July 7,

1993, e

Dr. Wilkins indicated that meeting presenters should be I regarded as professionals and treated with courtesy. It is i each member's obligation not to denigrate meeting partici-pants. He further observed that meeting presenters should be willing to acknowledge any limitations in their expertise, if necessary. Dr..Wilkins reported that Mr. William Russell, Associate Director, NRR, offered to appear before the Committee in a-closed session to discuss information on digital instrumen-tation and control issues that was acquired'during several staff foreign trips. No action was taken by the Committee. 2 The members discussed the preparation of technical papers for e the Second Quadripartite Maeting of the Advisory Committees on October 11-15, 1993. Copies of the papers should be ready by the_ August meeting so that they can be forwarded to the French. At the suggestion of the French,.Mr. Carroll will change the subject of his paper from Individual Plant

a 399th ACRS Meeting 13 July 8-9, 1993 Examinations to the EPRI Utility Requirement Documents. Mr. Carroll requested assistance on preparation of his paper. Dr. Wilkins and possibly one or two members are expecting to meet with Dr. Birkhofer, German RSK, on July 21, 1993, to discuss the details of the Quadripartite Meeting. e Dr. Larkins and Mr. Michael MacWilliams, ACRS staff, an-nounced that the hardware and software necessary to provide access to the E-Mail portion of AUTOS should be installed by the end of July. Internet accounts will be available to the members by September, and new AT&T calling cards have been distributed to the members. Mr. MacWilliams also announced that three portable personal computers are available to the members during meetings. e The members discussed a letter from Mr. Steven Sholly that requests the Committee to investigate whether the process of issuing Information Notices can be expedited. The Committee authorized Dr. Larkins to forward this request to the NRC Executive Director for Operations for consideration and disposition. Subsequent to the meeting, a letter was sent to Mr. Steven Sholly on July 16, 1993, regarding this subject. Mr. Carroll proposed an amendment to the ACRS Bylaws. Discussion on the proposed amendment was postponed to the August or September meeting. e The members discussed what should be the level of ACRS resources expended on detailed reviews of thermal hydraulic codes, such as MAAP, RELAPS, MELCOR, TRAC G, and COBRA TRAC. Dr. Catton observed that several codes will be examined during three upcoming subcommittee meetings. No action was taken by the Committee. The Committee agreed to have a dinner to observe the occasion l of the 400th ACRS meeting. IX. PLANS FOR COMPLETING THE ACRS REVIEW OF THE ADVANCED BOILING WATER REACTOR (ABWR) STANDARD SAFETY ANALYSIS REPORT (SSAR) (open) [ Note: Dr. Medhat El-Zeftawy was the Designated Federal Official for this portion of the meeting.) Mr. Michelson summarized the discussions that took place during a meeting of the Subcommittee on Advanced Boiling Water Reactors on July 28, 1993.

399th ACRS Meeting 14 July 8-9, 1993 Mr. Douglas Coe, ACRS staff, briefly summarized the Quad Cities Nuclear Power Plant HPCI rupture event that occurred on June 9, 1993. He stated that during a routine surveillance test of the HPCI turbine, both in-series turbine exhaust line rupture disks rupturad, causing the room to fill with steam and blowing open three sets of doors, including one set blown off its hinges. Mr. Michelson noted that the steam was of modest pressure and mass flow rate relative to what would have happened had the high pressure steam inlet line to the HPCI turbine ruptured. He also pointed out how small a pressure increase is needed to cause significant challenges to doors and other room penetration seals. Mr. Coe noted that the NRC staff had not yet issued its inspection report and that the cause of failure was still under discussion. Mr. Mark Stella, ACRS Senior Fellow, briefed the Committee on the ABWR reactor water cleanup system evaluation and the outstanding issues that General Electric Corporation will be addressing. Mr. Michelson stated that eight subcommittee meetings will be scheduled during the next seven months to complete the review of the ABWR design. He asked selected members to concur on their proposed subject area assignments (as shown in Handout 6.1) for the ACRS draft final report on the ABWR design. During the discussion of the schedule for completing the ACRS review of the GE Advanced Boiling Water Reactor (ABWR) design, it was noted that the ACRS review schedule is based partly on the assumption that GE will provide the final Standard Safety Analysis Report by July 31, 1993. Also, the Committee decided to review the security aspects of the ABWR design, but not the technical specifications and SAMDA issues. X. RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS (Open) (Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.) The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows: EDO letter, dated May 19, 1993, responding to the ACRS report e dated April 26, 1993 (revised June 24, 1993), concerning Implementation Guidance for the Maintenance Rule. The above EDO letter satisfactorily addressed the Committee's comments. EDO letter, dated June 8, 1993, responding to the ACRS report dated April 23, 1993, concerning Prioritization of Generic Issue 152, " Design Basis for Valves that Might Be Subjected to Significant Blowdown Loads."

w, 399th ACRS Meeting 15 July 8-9, 1993 The Committee did not raise any objections to the EDO's response. However, Mr. Michelson believes that there are some uncertainties that still need to be discussed with the staff during the Mechanical Components Subcommittee meeting on August 17, 1993. If these uncertainties are not adequately resolved, Mr. Michelson will advise the Committee. e EDO letter, dated June 15, 1993, responding to the ACRS report dated May 20, 1993, concerning Proposed Resolution of Generic Issue 105, " Interfacing Systems LOCA in LWRs." The above EDO letter satisfactorily addressed the Committee's comments. EDO letter, dated June 28, 1993, responding to the ACRS report dated May 26, 1993 (revised June 16, 1993), concerning Staff Approach for Assessing the Consistency of the Present Regulations with Respect to the Commission's Safety Goals. The above EDO letter satisfactorily addressed the Committee's comments. e EDO letter, dated June 30, 1993, responding to the ACRS report dated June 18, 1993, concerning Material Relevant to a Number of International Meetings on Digital Instrumentation and Control. The Committee noted that the material provided did not seem to address the lessons learned. Dr. Lewis suggested that ' the - members would learn more from Mr. Russell, Associate Director, NRR, who offered to appear before the Committee in a closed session to discuss information on digital instrumentation and control issues that was acquired during several staff foreign trips. EDO letter, dated July 6, 1993, responding to the ACRS report dated May 20, 1993, concerning Draft Report of the PRA Working Group. The above EDO letter satisfactorily addressed the Committee's comments. Dr. Wilkins recommended, and the Committee agreed, that the EDO 1 add subject headings to its future response letters to assist the ACRS members and staff in tracking and handling the responses more effectively. XI. MISCELLANEOUS (Open) [ Note: Dr. John Larkins was the Designated Federal Official for this portion of the meeting.]

y 1 399th ACRS Meeting 16 July 8-9, 1993 i The Committee authorized Dr. Wilkins, with assistance from Dr. Larkins, to prepare and issue a letter to Chairman Selin from the Committee concerning the proposed ACRS/ACNW staff reductions. XII. EXECUTIVE SESSION (Open) [ Note: Dr. John Larkins was the Designated Federal Official for this portion of the meeting.] A. Reports, Memorandum and Letter Reculatory Review Group Recort (Report to the Honorable Ivan Selin, NRC Chairman, from J. Ernest Wilkins, Jr., ACRS Chairman, dated July 15, 1993) Proposed Draft Reaulatorv Guides. DG-1023, " Evaluation of Reactor Pressure Vessels with Charov Uoper-Shelf Enerav Less i Than 50 Ft-Lb," and DG-1025, " Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence" (Report to James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated July 15, 1993) Proposed Resglution of Generic Issue I.D.3. " Safety System Status Monitorina" (Memorandum for Warren Minners, Director, Division of Safety Issue Resolution, RES, from John T. Larkins, Executive Director, ACRS, dated July 16, 1993) Consistent with the Committee's decision, Dr. Larkins informed Mr. Minners that the Committee had decided not to review the proposed resolution of Generic Issue I.D.3. Process for Exceditina the Issuance of Information Notices (Letter to Mr. Steven Sholly, Senior Consultant, MHB Technical-Associates, from John T. Larkins, Executive Director, ACRS, dated July 16, 1993.) Consistent with the Committee's decision, Dr. Larkins informed Mr. Sholly that the Committee forwarded his request for an investigation of the process for expediting the issuance of Information Totices to the NRC Executive Director for Operations for consideration and disposition. B. Future ACRS Activities The Committee decided not to review the proposed resolution of Generic Issue I.D.3, " Safety System Status Monitoring." Subsequent to the meeting, a memorandum was provided to Mr. Warren Minners, Director, Division of Safety Issue Resolution, RES, regarding this decision. r t W -

399th ACRS Meeting 17 July 8-9, 1993 The SRM directed review of the proposed Branch Technical Position on Metal Fatigue was discussed. Dr. Shack recommended that the review be postponed until NRR has completed its analy-i sis. Since it was not clear when the Chairman wanted ACRS to review this BTP, the Committee recommended that Dr. Larkins poll the Chairman Selin's Technical Assistant. The Committee discussed the generic implications of the Salem Nuclear Power Plant Unit 2 shutdown due to the potential for a rod control system single f ailure. Mr. Carroll recommended that representatives of the NRC staff be invited to brief the Committee after the augmented inspection team report has been issued. The Committee concurred. i Dr. Kress noted that the Committee had just received copies of NUREG/CR-6075, "The Probability of Containment Failure by Direct Containment Heating in Zion," and asked that this matter be i considered at some future meeting of the Severe Accidents i Subcommittee. The Committee discussed the proposed staff action described in SECY-93-167, " Regulatory Analysis Guidelines," and decided not to pursue the matter further until after public comments had been received and resolved. C. Future Meetina Acenda Appendix IV summarizes the proposed items endorsed by the Committee for the 400th ACRS Meeting, August 5-7, 1993, and future Subcommittee meetings. The 399th ACRS meeting was adjourned at 2:50 P.M. on Friday, July 9, 1993. ,.m-r =

. t1 APPENDICES MINUTES OF THE 399TH ACRS MEETING JULY 8-10, 1993 I. Federal Register Notice II. Meeting Schedule and Outline III. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee i -l i

F"~ ~ l APPENDIX I l Federal Register / Vol. 58 No.123 / Tuesday, June 29,1993 / Notices 34831

5. Seating for the public will be on a A detailed agenda will be made will discuss prionties for preparation of rst-come, first served basis, available at the meeting.

ACKS reports. p,,([n) 'S ' 8 8 * -## " This meeting will be held in Oral statements may be presented by 3,j,, cmop p T accordance with the Atomic Energy Act members of the public with the Committee will review and comment on the of 1954, as amended (primarily section concurrence of the Subcommittee report of the NRC Regulatory Review Group. 161a);the Federal Advisory Act (5 Chairman: written statements will be Representatives of the NRC staff will U.S.C. App); and the Commission's accepted and made available to the participate. regulations in title 10. Code of Federal Subcommittee. Questions may be asked 20:30 a m -22:45 a.m.: Report of the Regulations, part 7-only by members of the Committee and Planning and Procedures Subcommittee sed e mminn Justification for Less Than 15 Days the staff. Persons desiring to make oral (Open p p p ed Notice statements should notify the Nuclear subcommittee on matters related to the egu at Commission staff member it Is necessarY to hold this mootin8 on named beiow as far in advance as is conduct of ACRS business, including matters related to the status of appointment of new an expedited basis in order to provide practicable so that appropriate members, and organizational and personnel a timely response to recent direction arrangements can be made, matters relating to ACRS staff members. e m n. During the initial portion of the Portions of this session may be closed to Dated: June 23,1993. meeting, the Subcommittee may public attendance to discuss matters that Mlate s Myi intemal enne% and P John C Iloyle, exchenge greliminary views regarding practices of this advisory committee pursuant Advisory Committee Management Officer. matters to De considered during the to 5 U.S.C. 552b(c)(2) and to discuss matters [FR Doc. 93-15176 Filed 6-28-93; 8:45 aml balance of the meeting. The the release of which would represent a e:LUNQ Coot rseo.c g Subcommittee will then hear clearly unwarranted invasion of personal presentations by and hold discussions privacy pursuant to 5 U.S.c 552b(c)(6). with representatives of the NRC staff 22:45 p.m.-2:45 p.m.: Application of Nuclear Safety Research Review regarding this review, Probabilistic Risk Assessment Methods for Committee; Severs Accident Further information regarding topics RankingM t r-opemted Valves (MOV) 8 Subcommittee, Meeting to be discussed

• the schedulin8 of by and hold discussions with representatives P'"

AGENCY: Nuclear Regulatory sessions, whether the meeting has been of the NRC staff on the preliminary results Commission. canceled or rescheduled, the Chairman's from a research program to prioritize the risk ACTION: Notice of meeting. ruling on requests for the opportunity to importance of MOVs. Representatives of the present oral statements and the time industry will participate, as appropriate. The NSRRC Severe Accident allotted therefore can be obtained by a J p.m.-3Jo p.m.: Implementation ubcommittee will hold a meeting on prepaid telephone call to Mr. George cuidancefor zhe Maintenance Rule (Open)-. i The mminee I d cuss t NRC staffs sugust 2-3,1993,in the Maryland Sege (tele hone 301/492-3904) between g g Room, Holiday Inn,8120 Wisconsin 8 a.m. an 4:30 p.m. (EST). Persons recommendations included in the April 26, Avenue, Bethesda, MD. planning to attend this meeting are 1993 report on the implementation guidance The entire meeting'will be open to urged to contact the above named for the Maintenance Rule. Representatives of public attendance. individual one or two days before the the NRC staff will participate. The agenda will be as follows: scheduled meeting 13 be advised of any 330 p m.-4:30 p.m.: Plans for Completing Monday, August 2.1993,8:30 a.m. to changes in schedule, etc., that may have the ACRS Review of the Advanced Boiling i 5:30 occurred. Water Reactor (ABWR) Standard Safety Tuerday,p.m. and August 3,1993. 8:30 a.m. to Analysis Report (SSAR)(Open)-The j Dated; june 22,1993. Committee will discuss the schedule for 4:30 p.m. The Subcommittee will review George Sege, completing its review of the SSAR for the .i accomplishments, status, and Technical Assistant to the Director. Office ABWR design. Representatives of the NRC completion plans for programs pursued f NuclearRegulatory Research. staff will participate, as appropriate, under the NRC's Severe Accident [FR Doc. 93-15228 Filed 6-28-93; 8 A5 aml 4 - 5 . F ture S Research Program Plan, focusing estumo coor rs'*' discuss topics proposed for consideration primarily on additions and changes during future ACRS meetings. underway or planned since October 5:2 5 p.m.-5:30 pm.: Reconciliation of _ _. Comasles on hacio 1992. Related aspects of Accident e W,Ns; Meeting Agende "N ACns Recommendations (Open)-The g Committee will discuss responses from the Management, Individual Plant Examinations (IPE), and Individual NRC Executive Director for Operations to In acc rdan a with the purposes of recent ACRS comments and Plant Examinations for External Events sections 29 and 182b. of the Atomic recommendations (IPEEE) will be included as pertinent. In addition, consideration of the following Energy Act (42 U.S.C. 2039,2232b), the 5Jo p. mad 5 p.m.: Preparation ofAGS willbe included: cooperative Advisory Committee on Reactor Reports (Open)-The enmmittee will discuss Safeguards will hold a meeting on July pmposed ACRS reports regarding items international s with NRC 8-10,1993,in room P-110,7920 mnsidered during this meeting. rf m, Be6esda, Maryland. Mday, July s. ma d t u of ri k analysis in P anning and terminating severe N tion of this meeting was published in l 8J0 cmA:35 am.: Opening Remarks by h8 8 'T8 I8 d'r CD IN 4 the ACRS Chainnan (Open)-h ACRS accident research, closure of research Projects and snaintenance of mroday, July a; sees k M Nd e,ogn remarks capabilitiasjnd performance criteria 830 ams om:Openy RmrMy 835 mad 5 amW Regulatoryw.. ed man,ngom t ovprpight to enhance ACRScaliman(OpenMb ACRS

• Cuide. DG-1025. Calculational coderww e _.

. utions@e* Chairman willmake ' ing' remarks DosimetryMethodsforDeferm pessure Subcommittee will report to thIfull regarding condud of meeting and VesselNeutron Fluence (Open)- a. Committee on the facts and analyses comment briefly regarding items of current Committee will review and mmment on a developed at the meeting. interest. During this session, the Committee draft regulatory guide regarding the a

9 i 34832' Federal Register / Vol. 58, No.123 /' Tuesday, June 29, 1993 / Notices methodology for datanninin8 Fessure vosoel possibility that the schedule krACRS :. EDG had for 20 years not been tested at neutronfluence. Representatives of the NRC. meetings may be adketedbyitime h.w,, loads corisistent withlbe maximumW r staff andtadostrf 4rtilparticipsee. as necessary to facilitatatheronded of the ' expected ecc! dent Icedfhad(5)thedT k 9:15 a.nuto a.ast:Dm/tRegulatory GuMe, meeting. persons plantdag to attend should DG-1023, &ctuation of ficoctor Frenure check with the ACRS Executive Director if foreg&g raises a mnber of ions Venefs wtth Charpy Upper. Shelf Energyless such rescheduling would result In major that must be answered imm atelyif Than 50 Pt-Lb. (Openhno Committee will inconveniena. Vermont Yankee is going ta be allowed review and comment on a draft regulatory in have determined in occadance with to depend on these machines to ful811 guide regarding the evaloation of reactw rubsecuen to(d) Puhac Law 93-463,thet it the regulatory requirements for adequate pressure veessas with u -shelf is necessary to close portaons of this meeting onsite emergency backup power energy less than the 50 fbib noted above to d6cnan informadan that systems. Representatives of the NRC staff will involves the intamal personnel rules and Panicipata. procum of the og ocy per 5 USC. Petitioner's request for immediate

• 20:25 a.m-f 2:25 a.nr.: Debris Pfugging of 552b(cX2) and to discuss information the action was denied by the Regional Emergency Cbrw CooRag Suedon Un, release of which would represent a clearly Administrator for Region I in a letter Stminers (Openkne Committee will haar a unwarranted invasion of personal privacy per dem,d April 13,1993. The ba date I

briefing by and hold d9-* with 5 U.S.C. 552b(cX8), al of Petitioner's request for representattves of the NRC staff on the Purther information regarding topics to be immediate action are set forth with i potential fw debris plugging of emergency discussed, whether the meeting has been more specificity in a letter dated June core cooling saction line strainers. In cancelled or rescheduled, the Chairman's 2'1,1993, which acknowledges receipt of addition. the Committee will hear an update ruling on requests for the opportunity to the Petition. on the NRC staff activities to evaluate the present oral statements and the time allotted need far actions by U.S. licensees to address therefor can be obtained by a prepaid Pdionefs request is bei treated this issue as a result of the lessons learned telephone call to the ACRS Executive Pursuant,to 10 CFR 2.206 o e from the Barseback event in Sweden. Director, Dr. John T.1.arkins (telephone 301-Commisston,s regulations. The NRC will Representatives of the industry will 492-4516) between 8 am and 4:30 pm take eppropriate action on this request participate, as appropriate. EST. within a reasonable time. 11:25 am-!2:15 pm: Reoctor Operations Dated: June 23,1993. A copy of the Petition is ava&ble for Experience (Openkne Committee will hear John C. lloyle, inspection and copying in the a briefing by and hold discussion with representatives of the NRC staff on a remnt Advisory Committee Monogement Officer. Commission's Public Document Room, event at Sequoyah Nuclear Pcwer Plant, Unit (FR Doc. 93-15178 Filed 6-28-93: 8:45 aml 2120 L Street, NW., Washington, DC 20555 and in the Local Public 2 that involved a rupture of an extraction amo coes mo esa steam header line. Representatives of tbe Document Room, Brooks Memorial industry will participate, as appropriate. Library,224 Main Street, Brattleboro, 1:15 pm-5 pm: Prepamtion of ACRS ID**h*' N*' 00~2 11 Vermont 05301. Reports (Openh-The Committee will discuss Vermont Yankee Nuclear Power For the Nuclear Regulatory Commission. nhdered 8" n am Corporatiqn, Vermont Yankee Nuclear Dated at Rockville, Maryland this 21st day 5 pa-4 pm: Miscenaneous (open)--The Power Station; Receipt of Petition for I I""*' 1"3-Committee will discuss miscellaneous Director's Decision Under 10 CFR nmas F_ Murley, matters related to the conduct of Committee 2.206 Duector OfficeofNuclearReactor activities and complete discussion of topics Regulation. that were not completed during previous Notice is hereby given that by letter meetings as time and arallability of dated April 8,1993, to Thomas T. {FR Doc. 93-15224 Filed 6-28-93; 8.45 ami - coes nm information permit. Martin, Regional Administrator, Region ear %IaWy Qdsskn Saturday, July 10,1993 (NRC), as supplemented by letter dated 8:30 om-Close of Business: Prepamtion of April 11,1993, to Ivan Selin, Chairman Met Nom. WM and M) ACRS Reports (OpenhThe remittee will g ogen, rom Wgaeg J. Daley on discuss proposed ACRS reports regarding Items masidered during this meeting. behalf of the New England Coalition on Houston Ughting & Power Co. et al. Procedures for the conduct of and Nuclear Pollution, the NRC has received South Texas Project, Units 1 and 2; l participation in ACRS meetings were a Petition under to CFR 2.206 regarding Withdrawal of Amendments To Facility published in the Federal Register on October the Vermont Yankee Nuclear Power Operating Licenses g 16,1992 (57 FR 47494). In accordance with Station. The Petitioner requested the The U.S. Nuclear Regulatory these p hse. ca al or written statements NRC to take immediate action to require Commission (the Commission) has may be pmented by members of the public, that the reactor remain in cold granted a request from Houston Lighting recordings will be permitted only during

• @M*,

shutdown until plant management can & Power Company, et. al., (HL&P, the { 'h P'",Pj"," provide proof that the emergency diesel licensee) to withdraw HL&P's August 4, t,,, 1 i be ask only by members of the Committee, generators (EDC) at the plant are able to 1992, application for amendments to e its consultants, and staff. Persons desiring to meet their safety function. Petitioner Facility Operating License Nos. NPP-76 make oral statements should notify the ACRS seeks telle! based on assertions that (1) and NPF-80, issued to the licensee for Executive Director. Dr. John T. Larkins, as far diesel generator "A" was damaged by operation of the South Texas Project, in advance as practicable so that appropriate overload conditions suffered during Units 1 and 2, located in Matagorda arrangements can be made to allow the testing !n August through October of County, Texas. Notice of Consideration necessary time during the meeting for such 1990; (2) the "B" unit also suffered ofIssuance of this amendment was ,',Q,njs under the same testing regime;(3) one published in the Federal Register on e a ~ be limited to selected portions of the meeting e causes of the repeated failures of September 30,1992 (57 FR 45085). as determined by the Chairman. Information the,A unit in the summer of 1992 was The purpose of the licensee s regarding the time to be set aside for this the damage from thia testing:(4) the amendment request was to revise the purpose may be obtained by a prepaid overloading resulted from inappropriate Technical Specifications (TS) to reflect teicphone call to the ACRS Executive actions taken in response to an NRC-the results of a correction to the Director priar to the meeting. In view of the identified violation indicating that the containment free volume calculation. 1 l

pc-APPENDIX II '. [o ua o UNITED STATES NUCLEAR REGULATORY COMMISSION n -I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 'o, WASHINGTON, D. C. 20$55 June 30, 1993 SCHEDULE AND OUTLINE FOR DISCUSSION 399TH ACRS MEETING JULY 8-10, 1993 I lbursday, July 8, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md. 1) 8:30 - 8:45 A.M. Openina Remarks by ACRS Chairman (Open) 1.1) Opening statement (JEW /SD) 1.2) Items of Current Interest (JEW /JTL) 1.3) Priorities for preparation of ACRS reports (JEW /SD) 2) 8:45 - 10:15 A.M. NRC Reculatory Review Grouc Report (Open) (HWL/MDH) 2.1) Remarks by the Subcommittee Chairman 2.2) Briefing by and discussion with rep-resentatives of the NRC staff regard-ing the report of the Regulatory ) Review Group 10:15 - 10:30 A.M. BREAK 3) 10:30 11:45 A.M. Report of the Plannina and Procedures j Subcommittee (Open/ Closed) (JEW /JTL) 3.1) Report of the Planning and Procedures. i Subcommittee on matters related to -) the conduct of ACRS business, in-cluding matters related to the status of appointment of new members, and organizational and personnel matters relating to ACRS staff members (Note: A portion of this session may be closed to public attendance pursuant to 5 -U.S.C. 552b(c) (2) and (6) to discuss organi- { zational and personnel matters that relate-solely to the personnel rules and practices of this advisory committee cnd matters.the release of which would represent a clearly unwarranted invasion of personal privacy.)' i 11:45 - 12:45 P.M. LUNCH i

F~7-l I 2 4) 12:45 - 2:45 P.M. Apolication of Probabilistic Risk Assessment Methods for Rankina Motor-Ocerated Valves (Open) (CM/EGI) 4.1) Remarks by the Subcommittee Chairman 4.2) Briefing by and discussion with rep-resentatives of the NRC staff on the preliminary results from a research program to prioritize the risk im-portance of motor operated valves. Representatives of the industry _will participate, as appropriate i 2:45 3:00 P.M. BREAK 5) 3:00 4:00 P.M. Plans for Comoletina the ACRS Review of the Advanced Boiling Water Reactor Standard Safety Analysis Reoort (Open) (CM/MME) l 5.1) Report by the Subcommittee Chairman 5.2) Discussion of the Committee plans and schedules for completing its review of the Standard Safety Analysis-Re-port for the Advanced Boiling Water Reactor ,) 4:00 4:45 P.M. Future ACRS Activities (Open) (JEW /RPS) 6.1) Discussion of the recommendations of the Planning and Procedures Subcom-mittee regarding items proposed for consideration by the full Committee during future meetings 7) 4:45 5:15 P.M. Reconciliation of'ACRS Comments and Recom-mendations (Open) (JEW, et al./SD) 7.1) Discussion of the responses from the NRC Executive Director for Operations l to comments and recommendations made in ACRS reports-8) 5:15 6:15 P.M. Discussion of ACRS Reoorts (Open)- 8.1) Discussion of proposed ACRS reports regarding: 8.1-1) Report of Regulatory Review Group (HWL/MDH) 8.1-2) Motor-Operated Valves (CM/EGI) (Tentative) 8.1-3) Plans and schedule for ACRS review of the ABWR (CM/MME) (Tentative)

p~ 3 . Friday, July 9, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md. 8:35 A.M. Openina Statement by ACRS Chairman (JEW /SD) 9) 8:30 (Open) 10) 8:35 9:15 A.M. Draft Reculatory Guide DG-1025, Calculation and Dosimetry Methods for Determinina Pres-sure Vessel Neutron Fluence (Open) (RLS/EGI) 10.1) Remarks by the Subcommittee Chairman 10.2) Briefing by and discussions with representatives of the NRC staff regarding the draft Regulatory Guide DG-1025 on the methodology for deter-mining pressure vessel neutron flu-ence 11) 9:15 - 10:00 P.M. Draft Reculatory Guide DG-1023. Evaluation of Reactor Pressure Vessels with Charov Uoner-Shelf Enerav Less Than 50 Ft-Lb. (Open) (RLS/EGI) 11.1) Remarks by the Subcommittee chairman 11.2) Briefing by and discussions with representatives of the NRC staff j regarding the draft Regulatory Guide i DS-1023 on the evaluation of reactor pressure vessels with Charpy upper-shelf energy less than the 50 ft.-lb. level 10:00 10:15 A.M. BREAK

12) 10:00 11:15 A.M.

Debris Pluacina of Emeraency Core Coolina Suction Line Strainers (Open) (IC/PAB) 12.1) Remarks by the Subcommittee Chairman 12.2) Briefing by and discussions with j representatives of the NRC staff on j the potential for debris plugging of emergency core cooling suction line strainers. In addition, the Commit-- i tee will hear an update on the NRC I staff activities to evaluate the need for actions by U.S. licensees.to address this issue as a result of the lessons learned from the Barseback event ~in Sweden. Representatives of' the industry will participate, as appropriate i

13) 11:15 12:15 P.M.

Reactor Ooeratina Experience (Open) (JCC/DC) 13.1) Remarks by the Subcommittee Chairman

a; ? 4 4 13.2) Briefing by and discussions with' representatives of the NRC staff on a recent event at Sequoyah-Nuclear Power Plant,-Unit 2 that involved a rupture of an extraction stema header-line 12:15 1:15 P.M. LUNCH 14) 1:15 5:00 P.M. Preparation of ACRS Reoorts (Open) (3:00-3:15-BREAK) 14.1) Discussion of proposed ACRS reports-regarding matters considered during. this meeting 15) 5:00 6:00 P.M. Miscellaneous (Open) 4 15.1) Discussion of matters considered during this meeting and matters con-sidered but not completed at previous meetings as time and availability.of information p~ermit Maturday, July 10, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md, .6) 8:30 - Close of Precaration of ACRS Reports (Open) Business 16.1) Discussion of proposed ACRS reportr, regarding matters considered dur3rg this meeting Presentation time should not exceed 50 percent of the total NOTE: o time allocated for a specific item. The remaining 50 percent of the time is reserved for discussions. Number of copies of the presentation materials to be provided to the ACR8 - 35. l l'

- 3 P APPENDI" III: MEETING ATTENDEES 399TH ACRS MEETING JULY 8-10, 1993 NRC STAFF Sher Bahadur RES R. Barrett NRR W. Beckner NRR J. J. Blake RII Bill Borchardt NRR H. L. Brammer NRR A. Buslik RES Patricia Campbell NRR Frank Cherry RES A. Corne RGN C. Craig RGN J. Craig RES Dennis Crutchfield NRR R. Denning NRR M. K. Dey RES M. Drouin RES Paul Gill .NRR W. Gleaves RES Tony Gody NRR Brian Grimes NRR E. Hackett NRR John dickman NRR N. P..Kadambi RES P. Kahn NRR T. Koshy NRR Gus Lainas NRR L. Lambros NRR S. Malik RES Me? ia Malloy NRR M. ,, 'telo RES Tir. v.. 't :ty NRR E. Mcsonna OCM J. Murphy. RES James Nerba"0 NRR H. Pastis NRR Owen Rothberg RES Thomas Scarbrough NRR M. Slosson-NRR-R. Stransky 'NRR Ted Sullivan NRR A. Taboada RES M. Taylor EDO C.. Thomas NRR

Jit Vora' RES G. H. Weidenhamer.

RLS Magga~tean Weston HNRR - rE

car ~ ( "_. 4 Appendix III 2 399th ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLI_C Stephen Additon Tenera Raymond Art ASME-Research Clive Callaway NUMARC John Carew BNL Stephanie Coffin BG&E Kurt Cozens NUMARC Stephen Floyd NUMARC Larry Gifford GE Bill Hopkins Bechtel Roger Huston TVA Y. S. Kim NUS Anthony Pfeffer Serch Licensing Bechtel Tony Pietrangelo NUMARC Jim Raleigh STS Inc. C. Wesley Rowley Rowley Consultants Judith Sikorski Serch-Bechtel Getachew Testaye BG&E Bill Vesezy SAIC Hirabi Yasui Tokyo Electric Power L. Zerr 1 I 1

2 7~n- .i j + NT80lX IV j I ACRS FULL COMMITTEE AND SUBCOMMITTEE MEETINGS. July 20, 1993 I Auxiliary and Secondary Systems, July 27 (8:30 a.m. until close of business) and 28, 1993 (8:30 a.m. - 10:30 a.m.), 7920 Norfolk-Avenue, Bethesda. MD (Alderman), Room P-110. The Subcommittee will review the La Salle Fire PRA and the proposed resolution of Generic Issue 57, " Effects of Fire Protection System Actuation on Safety-Related Equipment." Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the nights of July 26 and 27: Catton HYATT Farydas NONE Davis NONE Quintiere NONE i Michelson HYATT Siu NONE Wylie HYATT Advanced Boilina Water Reactors, July 28, 1993, 7920 Norfolk Avenue, Bethesda. MD (Alderman), 11:00 a.m., Room P-110. The Subcommittee will' discuss fire PIUN, fire hazards analysis, and fire barrier design associated with the Advanced Boiling Water Reactor design.... Attendance by the following is anticipated, i and reservations have been made at the hotels as indicated for the night July 27: i Michelson HYATT Karydas NONE ~ Davis NONE Quintiere NONE i Catton HYATT Siu NONE Wylie HYATT 1 ? Imoroved Licht Water Reactors, August 4, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will discuss NRC staff's response to ACRS comments and recommendations related to certain policy, technical, and licensing issues pertaining to evolutionary and advanced light-I water reactor designs. Also, the Subcommittee will discuss the staff positions on certain remaining policy issues for passive plant designs. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of August 3: Wylie HYATT Lewis RESIDENCE INN Carroll HOLIDAY INN Lindblad HYATT Catton HYATT Michelson HYATT Davis NONE Seale HYATT Kress RESIDENCE INN Ward NONE e - O

w,..

o 2

Plannina and Procedures, August 4, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organiza-tional and personnel matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would represent a clearly unwarranted invasion of personal privacy. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of August 3: Wilkins HOLIDAY INN Carroll HOLIDAY INN Lindblad HYATT 400th ACRS Meetina, August 5-7, 1993, Bethesda, MD. During this meeting, the Committee plans to consider the following: A. Eemainino Policy Issues for Passive Plant Desians - Review and comment on the draft Commission paper on the remaining policy issues related to the passive plant designs. Repre-sentatives of the NRC staff will participate. B. Proposed Resolution of Generic Safety Issue 57, " Effects of Fire Protection System Actuation on Safetv-Related Eauio-ment," and Lessons Learned from the La Salle Fire PRA - Review and comment on the proposed resolution of Generic Safety Issue 57, and the Lessons Learned-from the La Salle Fire PRA. Representatives of the NRC. staff will partici-pate. Representatives of the industry will participate, as I appropriate. C. Proposed Resolution of Generic Issue 1432 " Availability of Chilled Water Systems and From Coolina" - Review and comment on the NRC staff's proposed resolution of Generic Issue 143. Representatives of the NRC staff will participate. D. Advanced Licht Water Reactor Policy Issue on Emercency Plannina - Review and comment on a draft Commission paper related to emergency planning for Advanced-Light Water Reactors. Representatives of the NRC staff will partici-pate. E. Meetinc with Chairman Selin - Hold discussions with NRC i Chairman Selin on items of mutual interest. I F. Resolution of ACRS Comments and Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations. G. Prioritization of Generic Issues - Discuss proposed assign-ments for reviewing the priority rankings proposed by the' NRC staff for a group of generic issues. I 1 ,e

3-i ? 3 t

• H.

ACRS Subcommittee Activities - Hear reports and hold discussions regarding the status of ACRS subcommittee i activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena, Advanced Boiling Water Reactors, and Computers in Nuclear Power Plant Operations. Portions of this session may be closed to discuss information deemed proprietary by the Westinghouse Electric Corporation per 5 U.S.C. 552b(c) (4).

• I.

Plannina and Procedures Subcommittee Report - Hear a report of the Planning and Procedures Subcommittee involving mat-ters related to the status of appointment of new members and organizational and personnel matters relating to ACRS' staff members. A portion of this session may be closed to public attendance pursuant to 5 U.S.C. 552b(c)(2) and (6) to dis-cuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS and mat-ters the release of which would represent a clearly unwar-ranted invasion of personal' privacy. J. Future ACRS Activities - Discuss topics proposed for consideration by the full Committee during future' meetings. K. Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of matters and specific issues that were not completed during previous meetings as time and availability of information permit. 1 J Materials and Metallurov, August 16, 1993, 7920 Norfolk Avenue, Bethesda, MD (Igne), 12:00 Noon, Room P-110. The Subcommittee will review proposed rulemaking on fracture toughness require-q ments for reactor pressure vessels - revisions to 10 CFR 50.61, i Fracture Toughness Requirements for Protection Against Pressur-ized Thermal Shock Events, Appendix G, Fracture Toughness Re- 'l quirements, Appendix H, Reactor Vessel Material Surveillance Program Requirements, and a new rule on reactor vessel thermal annealing (10 CFR 50.66). Lodging.will be announced later. Attendance by the following is anticipated: Seale Lindblad i Kress Shack Lewis Shewmon 1

• Open/ Closed i

'I l f

~ s 7 4 I Mechanical Components, August 17, 1993, 7920 Norfolk Avenue, Bethesda, MD - Postponed to October 5, 1993. Advanced Boilina Water Reactors, September 8, 1993, 7920 Norfolk-Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will discuss the status of resolution of the remain-ing open issues in the ABWR Standard Safety Analysis Report and i the resolution of USIs and GSIs. Also, it will discuss the NRC staff's schedule for submittal of the Final Safety Evaluation' I Report. Lodging will be announced later. Attendance by the -i following is anticipated: .l Michelson Kress Carroll Lindblad i Catton Seale Davis Wylie Plannina and Procedures, September 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related i matters. Portions of this meeting may be closed pursuant to 5 -t U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel. matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would repre- + sent a clearly unwarranted invasion of personal privacy. Lodging will be announced later. Attendance by the following is antici- -l pated: Wilkins Carroll Lindblad 401st ACRS Meetina, September 9-11, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110. Computgrs in Nuclear Power Plant Operations, September 15, 1993, Bethesda, MQ - Postponed. i Thermal Hydraulic Phenomena, September 20, 1993, Oreoon State University (OSU), Corvallis, OR (Boehnert). The Subcommittee will visit the OSU test facility. Lodging will be announced later. Attendance by the following is anticipated: Catton Dhir i Davis Wulff Kress Zuber Lindblad Seale Wilkins

j L.+. 1 + 5 Thermal Hydraulic Phenomena, September 21, 1993, Orecon State University (OSU). Corvallis. OR (Boehnert). The Subcommittee will' continue its review of the Westinghouse and NRC integral

t systems and separate effects test programs supporting the AP600 design certification effort.

The meeting discussion will focus on the OSU integral systems test facility program. Lodging will be announced later. Attendance by the following is anticipated: Catton Dhir Davis Wulff Kress Zuber Lindblad Seale Wilkins Severe Accidents, September 22-24, 1993, Sheraton Portland' Airport Hotel, 8235 N.E. Airport Way, Portland. OR (Houston),- 8:30 a.m., Room Columbian-D. The Subcommittee will continue its i review of the severe accident issues associated with the GE ABWR design certification effort. Attendance.by the following is anticipated, and reservations have been made at the Sheraton Portland Airport Hotel (telephone: 503-281-2500) for the nights of September 21, 22, 23: Kress Michelson Catton Seale i Davis Consultants - TBD i Lindblad Mechanical Components, October 5, 1993, 7920 Norfolk Avenue, Bethesda. MD (Igne), 8:30 a.m., Room P-110. The Subcommittee will discuss the status of the ongoing NRC and industry activi-ties associated with motor-operated' valves, check valves, butter-fly valves, and other related matters. Lodging will be announced i later. Attendance by the following is anticipated. Michelson Carroll Lindblad Wylie i f

'l i: R -e ) of 6 Imoroved Licht Water Reactors, October 6, 1993,.7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110.. The Elbcommittee will begin its review of the NRC staff's Safety .aluation Report for the EPRI passive LWR Utility Requirements document. Lodging will be announced later. Attendance by.the following is anticipated: Wylie Kress Carroll Lindblad .t Catton Michelson Davis Seale Plannina and Procedures, October 6, 1993, 7920 Norfolk Avenue, -i Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The' Subcommittee will discuss proposed ACRS activities and.related matters. Portions of this meeting may be closed pursuant to i 5 U.S.C. 552b(c) (2) and (6) to discuss. organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS and matters the release-of'which would represent a clearly unwarranted invasion of personal a privacy. Lodging will be announced later. Attendance by the following is anticipated: Wilkins Carroll Lindblad 402nd ACRS Meetina, October 7-9, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110. Thermal Hydraulic Phenomena, October 20-21, 1993 - (tentative), I 7920 Norfolk Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room j P-110. The Subcommittee will review selected aspects of the NRC-RES-sponsored ROSA-V confirmatory test program being conducted in support of the Westinghouse AP600 passive plant design certifica-tion effort. Specific review topics will include: facility i design modifications and additions, the. test matrix, and instru-mentation and controls. Also, the. Subcommittee will continue'its -{ review of the NRC RELAPS/ MOD 3 code. Attendance by the following is anticipated: Catton Dhir Davis Schrock Kress Wulff i Seale Zuber Wilkins i i h .e. ~

i i 7 Advanced Boilina Water Reactors, October 26-27, 1993, 7920 ~ Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m.,-Room P-110. The Subcommittee will begin its review of the NRC staff's Final Safety Evaluation Report for the GE ABWR design. Lodging will be announced later. Attendance by the following is anticipated: Michelson Kress carroll Lindblad Catton Seale Davis Wylie Computers in Nuclear Power Plant Operations, November 2,

1993, 7920 Norfolk Avenue, Bethesda, MD (Coe), 8:30 a.m., Room.P-110.

The Subcommittee will review the Chapter 7, " Instrumentation and Control Systems" of the Standard Safety Analysis Report for the ABWR design and associated DAC/ITAAC. Lodging will be announced later. Attendance by the following is anticipated: Lewis Michelson Carroll Wilkins Catton Wylie Davis Safeauards and Security, November 3, 1993, 7920 Norfolk Avenue, Bethesd> _JH2 ( Alderman), 8:30 a.m., Room P-110. The Subcommittee-will review the proposed SECY paper on Internal Threat-and the Rulemaking Associated with Staff Recommendation.for Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. Portions of this meeting may be closed to discuss safeguards information. Lodging will be announced later. Attendance by the following is anticipated: Lewis Wylie l Wilkins Plannina and Procedures, November 3, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. .The Subcommittee will discuss proposed ACRS activities and related i matters. Portions of.this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules.and practices of ACRS and-matters the release of which would represent a clearly unwarranted invasion of' personal privacy. Lodging will be announced later. . Attendance by the following is anticipated Wilkins Carroll i Lindblad a

e; l II 5 8 4vJrd ACRS Meetina, November 4-6, 1993, 7920 Norfolk Avenue,. Bethesda, MD, Room P-110. Advanced Boilina Water Reactors, November 16-17, 1993, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. 4 The Subcommittee will continue its review of the NRC staff's Final Safety Evaluation Report for the GE ABWR design. Lodging will be announced later. Attendance by the following is antici-pated: Michelson Kress Carroll Lindblad Catton Seale i Davis Wylie 1 1 Planninc.and Procedures, December 8, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 2:00 p.m. - 4:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Portions of this meeting may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational'and personnel matters that relate solely to internal personnel j rules and practices of ACRS and matters the release of which would represent a clearly unwarranted invasion of personal . i ] privacy. Lodging will be announced later. Attendance by the following is anticipated Wilkins Carroll Lindblad j i 404th ACRS Meetina, December 9-11, 1993, 7920 Norfolk Avenue, i Bethesda. MD. Room P-110. o Advanced Boilina Water Reactors, January 25-26, 1994, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m., Room P-110. The Subcommittee will review any residual issues,associateo with I the ABWR design and prepare a proposed:ACRS report on~ABWR issues for consideration by the full committee. Lodging will be an-nounced later. Attendance by-the following is anticipated. Michelson Kress Carroll Lindblad Catton .Seale Davis' Wylie

e 9 Decay Heat Removal Systems (tentative), Date to be determined (August), Bethesda, MD (Boehnert). The Subcommittee will con-tinue its review of the NRC staff's proposed final resolution of Generic Safety Issue 23, " Reactor Coolant Pump Seal Failures." Attendance by the following is anticipated: Catton Michelson Davis Wylie Lindblad Ward i Joint Individual Plant Examinations / Severe Accidents-(tentative), Date to be determined (August / September), Bethesda. MD (Houston). The Subcommittees will review the status and insights gained in regard to the Individual Plant Examination Program and Accident Management Guidelines. Attendance by the following is anticipat-t ed: Davis Michelson Kress Seale Catton Kerr Lindblad Ward Severe Accident 9, Date to be determined (November / December), Bethesda, MD (Houston). The Subcommittee will discuss the methodology developed and applied for assessing the effects of i direct containment heating (DCH) at the Zion Nuclear Power Plant (NUREG/CR-6075). Attendance by the following is anticipated: j l Kress Lindblad Catton Michelson 1 Davis Seale Consultants (TBD) ] Thermal Hydraulic Phenomena, Date to be determined (2-day meet-ing), San Jose. CA (Boehnert). The Subcommittee will continue I its review of both the GE analytical program (TRACG-code) and the experimental program supporting the certification effort for the Simplified Boiling Water Reactor design. Attendance by the following is anticipated: .{ Catton Dhir Carroll Wulff l Davis Zuber Kress Seale Wilkins i

.s-

g-APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE MEETING HANDOUTS I

AGENDA DOCUMENTS ITEM NO. 2. NRC Reaulatory Review Grouc Report 1. Comments on Regulatory Review,

undated, Prepared by William Kerr [ Official Use Unly) 2.

Memorandum to Hal Lewis from David Ward, consultant, dated July 7, 1993, 'regarding Comments on Regulatory Practices and Procedures Subcommittee meeting on July 7, 1993 [ Official Use Only] 3. Regulatory Review

Group, undated, Frank Gillespie (Viewgraphs) 3.

Report of the Plannina and Procedures Subcommittee 4. Draft memorandum to.ACRS Members from John Larkins and Richard Savio, dated July 7,

1993, regarding ACRS Fellowship Program [ Handout No. 3.1] -

5. Draf t Minutes of the Planning and Procedures Subcommittee Meeting on July 7, 1993 [Handoute No. 3.2) 4. Acolication of Probabilistic Risk Assessment Methods for Rankino Motor-Operated Valves 6. PRA Based Approaches for Prioritizing MOVs in Response to Generic Letter 89-10, dated July 8, 1993, by Gerald H. Weidenhamer, RES [Viewgraphs) j 7. PRA Based Approaches for Prioritizing MOVs in Response to Generic Letter 89-10: PRA Considerations, dated-July 8, 1993, by W.E. Vesely, SAIC [Viewgraphs] 5. Recongiliation of ACRS Comments and Recommendations 8. Six ACRS Reports and the EDO's Response Letters [Handocc { 5.1) 6. Plans for~Comoletino the ACBS Review of the Advanced Boilinc Water Reactor Standard Safety Analysis Report 9. Proposed Plan of Action to Complete Review of ABWR Design [ Handout 6.1) 10. Quad Cities HPCI Exhaust Piping Rupture Event of June 9, 1 1993,~ including Data Summary Sheet and Various Diagrams of System and Components [ Handout No. 6.2) i 11.- ACRS Review of ABWR Reactor Water Cleanup System j Evaluation, undated, Prepared by Mark Stella, Senior ACRS i Fellow 7. Future ACRS Activities 12. Memorandum to ACRS Members from Medhat El-Zeftawy, ACRS, dated July 8, 1993, regarding " Policy, Technical',- and i s +

~ ~ 4 j+- ..t .e 1 \\ l Appendix V 2 1 399th ACRS Meeting

j Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs," with enclosure 13.

Memorandum to ACRS Members from R. P. Savio, ACRS, dated i July 8, 1993, regarding Future ACRS Activities - 400th J ACRS Meeting, August 5-7, 1993, with enclosures 14. Memorandum to Harold Lewis from Herman Alderman,' dated July 7,

1993, regarding SECY-93-166,

" Staff Recommendation for Protection Against Malevolent Use'of Vehicles at Nuclear Power Plants," with enclosures 10. Draft Reculatory Guide DG-1025. Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence 15. Proposed Draft Regulatory Guide, DG-1025, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, dated July 9, 1993, Prepared by Michael ? Mayfield [Viewgraphs) 11. Draft Reculatorv Guide DG-1023. Evaluation of Reactor Pressure-y_epsels with Citarov Upper-Shelf Enerav Less Than 50 Ft-Lb. 16. Proposed Draft-Regulatory Guide DG-1023, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb, dated July.9, 1993, Prepared by_ Michael Mayfield (Viewgraphs)- 17. Package of. graphs, charts, and diagrams, undated 12. Debris Pluccina of Emeroency Core Coolina Suction Ling'

s. trainers 18.

Strainers Used in Emergency Core Cooling Systems,. dated. 1 July 9, 1993 [Viewgraphs] 13. Reactor Operatina Experience 19. Extraction Steam Header Rupture at Sequoyah Unit 2, dated July 9,

1993, Prepared by Alfred Chaffee etal

[Viewgraphs) t 'f

[.- u [. b. Appendix V 3 399th ACRS Meeting MEETING NOTEBOOK CONTENTS TAB DOCUMENTS 2. NRC Reculatory Review Grcuo Report 1. Status Report 2. Memorandum for the Chairman and Commissioners from James Taylor, EDO, dated January 4, 1993, regarding COMIS 025 Regulatory Review 3. Memorandum for Frank Gillespie etal from James Sniezek, EDO,' dated February 4, 1993, regarding Revised Charter for Regulatory Review Group, with enclosure 4. Regulatory Review Group Summary and Overview, Volume 1 5. Memorandum for John Larkins, ACRS, from Frank Gillespie, NRR, dated June 25, 1993, regardj..g Proposed Rulemaking to Implement the Regulatory Revie, Group Recommendation on 10 CFR 50.54, without enclosure [ Draft Predecisional] 6. Note for ACRS Members from Dean Houson, ACRS, dated June 28, 1993, regarding Proposed Rulemaking to Implement the j Regulatory Review Group Recommendation on 10 CFR 50.54, without attachment 4. Application of Probabilistic Risk Assessment Methods for Rankina Motor-Ocerated valves 7. Status Report 8. Handout on "Prioritization of Valves Based on a Preliminary Probabilistic-Risk Assessment (PRA)," by G. Weidenhan.er, RES, that was presented during the MOV User Group meeting in Phoenix, Arizona, on February 23-24, 1993 6. Elans for Completino the ACRS Review of the Advanced Boiling Water Reactor Standard Safety Analysis Report 9. Status Report 10. SECY-93-041, " Advanced Boiling Water Reactor (ABWR) Review Schedule," dated February 18, 1993 11. ACRS Report, dated March 18, 1993, regarding Advanced Boiling Water Reactor (ABWR) Review Schedule 12. Letter for Paul Shewmon, ACRS, from James Taylor, EDO, dated April 7, 1993, regarding ABWR Review Schedule 3 13. SECY-93-097, " Integrated Review Schedules for the Evolutionary and Advanced Light Water Reactor Projects," dated April 14, 1993 14. Proposed Schedule for the ABWR Subcommittee Visit to GE Facility 15. Proposed Agenda Items for the ABWR Subcommittee Meeting in San Jose, California, on. Tune 17, 1993.

(A: g + / 3 1 Appendix V 4 399th ACRS Meeting 10/11. Draft Reaulatorv Guide DG-1025, Calculational and Dosimetry Methods for Determinino Pressure Vessel Neutron Fluence and Draft Reculatory Guide DG-1023. Evaluation of Reactor Pressure Vessels with Charov Uoner-Shelf Enerav Less Than 50 Ft-Lb. 16. Status Report 17. Draft Regulatory Guide DG-1025, " Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated June 1993 [Predecisional] 18. Draft Regulatory Guide DG-1023, " Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb," dated June 1993 [Predecisional) 12. Debris Pluccina of Emeroency Core Coolina Suction Line Strainers 19. Agenda 20. Project Status Report 21. NRC Bulletin No. 93-02 " Debris Plugging of Emergency Core Cooling Suction Strainers, dated May 11, 1993 22. NRC Information Notice 93-34, Supplement 1, " Potential For Loss of Emergency Cooling Function Due to a Combination of Operational' and Post-LOCA Debris in Containment," dated May 6, 1993 23. NRC Information Notice 93-34, " Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment," dated i April 26, 1993 j 24. NRC Information Notice 92-71, " Partial Plugging.of Suppression Pool Strainers at a Foreign SWR," dated September 30, 1992 25. Memorandum from A. Thadani to T.

Murley,

Subject:

" Program Approach to Resolution for Sump Clogging," dated j October 19, 1992, with BWR Owners Group response 26. SECY-85-349 Resolution of Unresolved Safety Issue A-43, " Containment Emergency Sump Performance," dated October 31, 1985 27. Regulatory Guide 1.82, Revision p5 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident, November 1985 28. ACRS letter from David Ward, ACRS, to. William Dircks,; EDO,

Subject:

ACRS Review of Proposed' Resolution for USI A-43' and Regulatory Guide 1.82, Revision 1, dated September 16, 1985 13. Reactor Operatina Experience 29. Agenda-30. Project Status Report

31.. Licensee Event Report 50-328/93001

" Extraction l

i s 'o I . a s-Appendix V 5 399th ACRS Meeting j l 1 Steam Line Rupture Causes High Generator output Voltage and Manual Reactor Trip," dated March.31, 1993 32. NRC Inspection Report No. 50-328/93-10 (AIT report) dated April 7, 1993 i o i 1 1 h 4 d we r e =}}