IR 07100203/2006447
| ML20217A977 | |
| Person / Time | |
|---|---|
| Site: | 07100203 |
| Issue date: | 02/05/1998 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-3084, NUDOCS 9803250312 | |
| Download: ML20217A977 (61) | |
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Date signed: 2/19/98 i
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' ' Og M -368 4 TABLE OF CONTENTS .
MINUTES OF THE FOUR HUNDRED FORTY-SEVENTH ACRS MEETING DECEMBER 3-6,1997 Page j i Chairman's Reoort (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l 1 Emergency Core Cooling System Strainer Blockage (Open) . . . . . . . . 1 j ll Assurance of Sufficient Net Positive Suction Head for Emergenev Core Cooling and Containment Heat Removal Pumps (Open) . . . . . . . 2 I NRC Performance Plan (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ACRS Reoort to Conaress on the NRC Safety Research Program (O pe n ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .4 I
V Prooosed Revisions to 10 CFR 50.59 (Changes. Tests and 1 Exoeriments) (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .5 Vi Pronosed Generic Letter on Interim Guidance for Uodating Final Safety Analysis Reoorts (Open) . . . . . . . . . . . . . ................ 8 Vil Meeting with Commissioner Dieus (Open) . . . . . . . . . . . . . . . . . . . . 10 j i
I Prooosed Revision 1 to NUREG-1022. " Event Reoorting Guideline CFR 50.72 and 50.73 (4/@) . . . . . . . . . . . . . . . . . . . . . . ..... 11 l Prooosed Final SRP Chaoter 19 General Guidance) and Reaulatorv '
Guide DG-1061 for Risk-Informed. Performance-Based Reculatio including Use of Uncertaintv Versus Point Values in the PRA-Related Decisionmakino Process (Open) . . . . . . . . . . . . . . . . . . . . . . 12 f Ooerating Events at Oconee Nuclear Power Plant Units 1 and 2 (Ocen)15 / I
!\>b,uf 1 X Caoability and Acolication of the EPRI CHECWORKS Code (O p e n) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 XI Executive Session (Open) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 Reports, Letters, and Memoranda 9803250312 980205 PDR ACRS 3084 PDR
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REPORTS
. Proposed Final Reaulatorv Guide 1.174 and Standard Review _
Plan Chanter 19 for Risk-Informed Performance-Based Regulation (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 11, 1997.)
. Pronosed Revisions to 10 CFR 50.59 (Changes. Tests and Experiments) (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 12, 1997.)
. Credit for Containment Overoressure to Provide Assurance of Sufficient Net Positive Suction Head for Emeroency Core QQgjing and Containment Heat Removal Pumos (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 12,1997.)
. Treatment of Uncertainties Versus Point Values in the PRA-Related Decisionmaking Process (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 16,1997.)
LETTER
. Prooosed Final Revision 1 to NUREG-1022. " Event Reoorting Guidelines 10 CFR 50.72 and 50.73 (Letter to L. Joseph Callan, Executive Director for Operations, NRC, from R. Seale, Chairman, ACRS, dated December 10,1997)
MEMORANDA
= Procosed Generic Letter. " Augmented Insoection of Pressurized-Water Reactor Class 1 High-Pressure Safety iniedton Pioing"(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 9,1997)
. Draft Regulatorv Guide DG-1071. " Standard Format and Content for Post-Shutdown Decommissioning Activities Reoort"(Memorandum to L. Joseph Callan, Executive Director ii
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for Operations, NRC, from John T. Larkins, Executive Director, }
ACRS, dated December 9,1997)
. Year 2000 Comouter lasue (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 10,1997)
. Prooosed Generic Letter on Interim Guidance for Undating Final Safety Analysis Reoorts (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John Larkins, Executive Director, ACRS, dated December 10,1997)
B. Reconciliation of ACRS Comments and Recommendations C. Report on the Meeting of the Planning and Procedures Subcommittee Held on December 3,1997 (Open)
D. Future Meeting Agenda
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APPENDICES 1. Federal Register Notice 11. Meeting Schedule and Outline Ill. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee
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. Utn11ritu MINUTES OF THE FOUR HUNDRED FORTH-SEVENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS DECEMBER 3-6,1997 ROCKVILLE, MARYLAND The 447th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on December 3-6,1997. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. The meeting was open to public attendance. There were no written statements nor requests for time to make oral statements from members of the public regarding the meetin A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building,2120 I (Eye) Street, N.W., Washington, [ Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd.,1250 i 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 (December 5-6 only), Dr. Mario H. Fontana, Dr. Thomas S. Kress, Dr. Don W. Miller, Dr. William J. Shack, and Dr. Robert E. Uhrig. Dr. Graham Wallis, a proposed ACRS Member, attended on December 3-4,1997. [For a list of other attendees, see Appendix lli.) 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. Gail Marcus is Acting Deputy Executive Director, ACRS/ACNW. He also mentioned upcoming meetings with Chairman Jackson and Commissioners Dicus and Diaz and recent speeches by Chairman Jackson, Commissioner Diaz, and Senator Domenic I Emergenev Core Cooling Svstem Strainer Blockage (Open)
[ Note: Mr. Amarjit Singh was the Designated Federal Official for this portion of the meeting.)
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447th ACRS Meeting 2 December 3-6,1997 1 Introduction Dr. Robert E. Uhrig, Acting Chairman of the Plant Operations Subcommittee, stated that the purpose of this session was to hear a briefing regarding the staff's draft Safety Evaluation Report (SER) on the BWR Owners Group (BWROG) Utility Resolution Guidance (URG) for Emergency Core Cooling System (ECCS) Suction Strainer Blockage, and the staff's review of licensee responses to NRC Bulletins to address strainer blockage, research associated with debris generation and transport, and proposed actions taken by the staff to resolve these issue NRC Staff Presentation The staff presented an overview and updated the Committee on the status of the staff's activities to resolve the BWR ECCS strainer clogging issue. The staff performed an independent assessment of the BWROG URG report and concluded that, overall, it provides good guidance that the staff considers acceptable. Further, the staff stated that, where it has identified concems, licensees should address those concems when applying the URG. The staff is expected to issue a final SER by February 199 Conclusion The Committee decided not to issue a letter until the final SER has been issue The Committee also requested a briefing from the staff after the issuance of the final SE Il Assurance of Sufficient Net Positive Suction Head for Emeraency Core Coolina and Containment Heat Removal Pumos (Open)
[ Note: Mr. Paul A. Boehnert was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Kress, Chairman of the Thermal-Hydraulic and Severe Accident Phenomena Subcommittee, introduced this topic to the Committee. He noted that the ACRS reviewed NRC Generic Letter 97-04," Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" during its June 1997 meeting. In its June 17,1997 letter to the Executive Director for Operations (EDO), the Committee took the position that the staff should not allow
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447th ACRS Meeting 3 December 3-6,1997 credit for containment overpressure to assure adequate net positive suction head (NPSH). The EDO's letter of response indicated that the staff intended to grant credit for containment overpressure in limited circumstances. Subsequently, the Committee requested' additional dialogue with the staff on this matte NRC Staff Presentation Mr. John Kudrick, NRR,'noted the following points regarding the status of NPSH-related issues:
. The Committee had previously noted that containment overpressure may not be available when most needed - during events occurring at shutdown or for containment bypass events. The staff does not allow credit for overpressure during events occurring during shutdown. For bypass events, the staff essentially evaluates the effects on containment r" lure based on two end points; i.e., the case where high pressure is avasuiu (beyond design-basis-accident events), and bypass occurs due to a failure of containment integrity, and the minimum containment pressure expected based on a conservative analysis of key parameters (e.g., maximum service water temperature, use of containment sprays, etc.).
. The amount of overpressure credit provided is given for the limiting case
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only. The next most limiting case generally requires only one-half the limiting case amoun . The need for any corrective actions relative to this matter will be evaluated by the staff based on licensee responses to the GL-97-04 informatioit reques In rasponse to questions from Dr. Powers, Mr Kudrick noted that licensees seeking credit for overpressure must evaluate the impact on NPSH of a "what-if" scenario where containment backpressure is suddenly lost. Mr. Kudrick also stated that information obtained from licensees to date on this issue gives an indication that the l
pumps of concern are robust and that plant operators can take actions to mitigate
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the effects of loss of adequate NPSH (e.g., throttle back the pumps).
Conclusion
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447th ACRS Meeting 4 i December 3-6,1997:
.l I NRC Performance Plan
[ Note: Mr. Amarjit Singh was the Designated Federal Ofiicial for this portion of the meeting.]
Introduction
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Dr. Robert L. Seale,' ACRS Chairman, welcomed Mr. Jesse L. Funches, Chief !
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Financial Officer for the NRC, and Mr.-James L. Blaha, Executive Secretary of the NRC Executive Council. He stated that the purpose of this briefing was to hear presentations regarding the NRC's Planning and Performance Management System and the Operating Pla NRC Presentation Mr. Funches stated that the Performance Plan was prepared in accordance with the !
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Govemment Performance and Results Act. He stated that, in implementing the Performance Plan, NRC will: (1) precede budget decisions with strategic, policy and planning decisions; (2) use results from assessments to form planning and budgeting decisior.4; (3) identify the activities that no longer add value to the NRC's goals and mission; and (4) monitor progress toward achieving NRC's goals throughov. ine year. The plan is scheduled to be implemented by Fiscal Year 200 Mr. Blaha stated that the Operating Plan is organized by program and not by offic The Operating Plan includes the significant components of the Performance Plan and corresponds to the budget cycle, which will be updated quarterl Conclusion This briefing was for information only. No Committee action was sequire , ACRS Reoort to Congress on the NRC Safety Research Proaram
[ Note: Dr. Medhat El-Zeftswy was the Designated Federal Official for this portion of the meeting.] ,
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The Committee discussed the context of a draft report to the Congress regarding l the NRC Safety Research Program. The Committee plans to issue its report in final i form in February 1998,
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447th ACRS Meeting 5 December 3-6,1997 Conclusion
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This session was for Committee discussion onl V Prona==d Revisions to 10 CFR 50.59 (Changes. Tenta and Exoeriments)
[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.]
Introduction Dr. Dana Powers introduced the topic to the Committee. He noted that the Committee previously issued reports to the Commission regarding proposed changes to 10 CFR 50.59 and related matters.' He stated that the Committee had recommended the staff work with industry to reconcile appropiiate guidance for implementing the 10 CFR 50.59 process and that the proposed guidance not be i issued for public comment. Dr. Powers stated that the documents were subse-quently issued for public comment and that this review would consider a revised version of the staff's approach to improving 10 CFR 50.5 NRC Staff Presentation Ms. Eileen McKenna, NRR, led the discussion for the NRC staff. Mr. Jack Roe, NRR, also participated. The staff discussed the background that led to the .
proposed improvements to the 10 CFR 50.59 process and associated draft l rulemaking including proposed . clarifications to terminology and guidanc Significant points made during the discussion include:
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. The staff stated that they were not requesting a letter from the Committee at this time. The staff requested to meet with the Committee in February 1990 when a complete rulemaking package would be availabl * In a Staff Requirements Memorandum dated April 25,1997, the Commission requested the staff to develop a plan for rulemaking on 10 CFR 50.59. On
September 10,1997, the staff forwarded its recommendation for changes to 10 CFR 50.59 in SECY-97-205," Integration and Evaluation of Results from Recent Lessons-Learned Reviews," including the proposal for rulemakin The ACRS reviewed these matters in October 199 I
- The staff stated that rulemaking is needed to clarify requirements and resolve problems with the implementation of 10 CFR 50.59. The staff noted f
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447th ACRS Meetin : December 3-6;1997 that the scope and intent of the rule is not being revised. Key areas to be considered in the proposed rule includei
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The staff proposes to clarify the definition of what constitutes a
" change in the facility" as described in the safety analysis report (SAR). The staff also proposes that the requirements include the analyses and supporting information. Similar language would be used to clarify " procedures as described."
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The staff proposes to provide revised definitions of terminology and listing of criteria. The staff proposed attemate language to clarify the requirements for design, construction, and operation and the safety analyses that demonstrate the adequacy of systems, structures, and component The staff proposes attemate language for the term unreviewed safety question (USQ) and proposes to use unreviewed licensing question (ULQ) in lieu of USQ. The staff also proposes to clarify " safety evaluation" and " safety analysis report" with respect to Technical Specifications and ULQ . For USQs, the staff proposes to change 10 CFR 50.59(a)(2) as follows:
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Revise "may be increased" to "is increased,"
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Revise "may be created" to "is created," and l
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Add language to the rule on the " basis of any Technical Specifica-tion."
. Other regulations which have provisions similar to 10 CFR 50.59 need to be revised to reflect the noted changes (e.g., Parts 60,72, and 76). The staff does not have immediate plans to modify these regulation Industrv Presentation Messrs. Tony Pietrangelo and Doug Walters of the Nuclear Energy Institute (NEI)
discussed industry views related to the proposed changes to 10 CFR 50.59. They also discussed industry initiatives in this area. Significant points made during the discussion include:
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447th ACRS Meeting 7-December 3-6,1997
NEl has established a 10 CFR 50.59 Task Force to address industry need ' All power reactor licensees have endorsed NEl 97-07, " Guidelines for 10
CFR 50.59 Safety Evaluations." NEl believes this willimprove consistency oflicensee safety evaluations. NEl representatives stated that the process for conducting 10 CFR 50.59 safety evaluations needs to be stabilized and requested NRC endorsement of NEl 96-0 .
NEl agrees with the staff that 10 CFR 50.59 is a regulatory threshold for decisionmaking. However, the proposed changes do not sufficiently focus on safety or allow for very small increases in risk. NEl finds the proposed changes inconsistent with the PRA Policy Statemen * NEl believes that the staffs focus on changes to the bases of Technical Specifications constitutes a change to the operating license envelop * NEl believes there is some acceptance limit that can be considered for consequence. NEl stated that this may be the limits defined in the Final Safety Analysis Reports or in 10 CFR Part 10 * NEl offered alternate language for the staff to consider in revising the rule for 10 CFR 50.59. The NEl approach focuses on determining whether there is
"more than a negligible increase" in probabilit Dr. Seale expressed the view that the issue regarding USQs is as close to a cultural issue as any could be. He added that to attain consistency in implementing 10 CFR 50.59 will require addressing the issue of allowing for very small increases in ris The staff stated that part of the problem lies in defining a "very small increase." The staff added that the term USQ provides an appearance of risk when most USQs are minor in safety significance. Thus, the staff is proposing to use UL Dr. Seale questioned whether risk analysis, if used as the basis for a change, becomes part of the plant licensing basis. The staff stated that it would. Dr. Powers noted that this would " cast a very wide net" over the number of documents to be maintained. Dr. Seale stated that he was troubled by the " spirit" of complete compliance in the proposed changes and expressed the view that the staff's focus should be on the assurance of safet Dr. Kress questioned the use of the proposed term " possibility" versus " probability" with regard to increases in consequences. The staff reiterated that 10 CFR 50.59 is a regulatory decision threshold based on safety' considerations. Dr. Powers
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447th ACRS Meeting 8 December 3-6,199 stated that the change from " probability" to " possibility" could introduce a new set of problems requiring clarificatio At the conclusion of the meeting, the Committee and staff agreed to have another meeting regarding these matters in February 1998 when the rulemaking package is complet '
Conclusion The Committee issued a report to Chairman Jackson, dated December 12,1997, on this matte . Vi Prooosed Generic Letter on Interim Guidance for Uodatina Final Safety Analvsis Reports
[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Dana Powers introduced the topic to the Committee. Dr. Powers introduced the NRC staff and requested the staff to begin its presentation regarding the proposed Generic Letter, " Interim Guidance for Updating Final Safety Analysis Reports."
NRC Staff Presentation Mr. Thomas Bergman, NRR, led the discussions for the NRC staff. Mr. Jack Roe, NRR, also participated. The staff discussed the background which led to development of the proposed Generic Letter, the associated regulatory require-ments, and related NRC activities. Significant points made during the discussion include:
. Final Safety Analysis Report (FSAR) inaccuracies were identified at the Millstone station and were reported to the Commission as p irt of the Lessons-Learned Report (SECY-97-036). The staffs proposed course of action was presented to the Commission in its integration paper (SECY-97-205). The ACRS was briefed previously on each of these policy paper . The applicable regulatory requirements for the contents of FSARs are l
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contained in 10 CFR 50.34(b). The requirements for FSAR updates are contained in 10 CFR 50.71(e).
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447th ACRS Meeting 9 December 3-6,1997 )
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. The proposed Generic Letter is intended to assure that FSARs contain the latest material developed and the analyses required, submitted, or performed at the request of the Commission. It would clarify the description of the facility, present its design basis, and provide limits on operation and the associated safety analysi . The staff proposes to only apply this Generic Letter through the enforcement discretion period for licensee updates to FSARs (SECY-96-154). After the staff receives public comrnent on the proposed Generic Letter, the staff plans
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l to develop a Commission paper to address the need for long-term guidanc The staff suggested that the revised document may be in the form of a Regulatory Guid . The staff has reviewed industry guidance proposed by NEl and has no major objections to that guidance. However, the NRC is not yet prepared to endorse this guidance via a Regulatory Guide. However, the staff may consider such an endorsement after the public comment period. The staff has adopted a recommendation from earlier public comments suggesting that licensees be allowed to remove risk insignificant information from FSAR Industrv Presentation Messrs. Tony Pietrangelo and Russell Bell of NEl discussed industry views related to the proposed Generic Letter. They also discussed industry initiatives in this are Significant points made during the discussion include:
. NEl has established an FSAR Task Force to address the need for licensees to update FSAR . FSARs are bounding analyses, not compliance analyses. NEl stated that the .
proposed Generic Letter could divert licensee resources from more risk- l significant activities. NEl recommended that the staff issue a draft Regula- l tory Guide for comment rather than the proposed Generic Lette !
Dr. Powers questioned what types of material would be maintained in FSARs and what could be deleted. The staff stated that the Generic Letter would request incorporation of information related to the Maintenance Rule, analyses in support of proposed changes, new issues such as 10 CFR 50.54(f) letters, and generic cc:nmunications such as NRC Bulletins and Generic Letters. It would allow for the l removal of information such as the initial startup test and analysis progra _ _ _ _ _ _ _ _ _ - _ -
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447th ACRS Meeting 10 December 34,1997 i
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l Industry representatives stated that this information would be relocated into reference documents rather than being delete Dr. Powers questoned the number and significance of the discrepancies related to FSARs. The staff stated that more than 300 discrepancies were identified during pilot inspections and at Millstone. However, they noted that only about 15 had safety significance. The staff stated that the more safety significant issues of the 15 identified were related to licensees not having updated the plant design bases l in the FSA At the conclusion of the meeting, Dr. Powers expressed support for the cooperative effort between the staff and NEl regarding these matter Conclusion The Committee decided to review this matter following reconciliation of public comments. The ACRS Executive Director issued a memorandum to the Executive Director for Operations, dated December 10,1997, on this matte '
Vil Meetina with Commissioner Dicus
[ Note: Dr. Medhat El-Zeftawy was the Designated Federal Official for this portiori of the meeting.)
Dr. Seale, ACRS Chairman, welcomed NRC Commissioner Greta J. Dieus and stated that the Committee was pleased to have the opportunity to hear the Commissioner share her views on items of current and mutual interes The Commissioner offered her views on the following issues:
.- The NRC Research Program activities
. Use of probabilistic risk assessment in the regulatory decisionmaking process
. Health effects of low levels of ionizing radiation
. Senior Management Meeting process
. The 10 CFR 50.59 process
. Proposed Shutdown Rule
. Plant License Renewal
- Timeliness and utility of ACRS advice u
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447th ACRS Meeting 11 December 3-6,1997 Conclusion This session was for information only. However, the Commissioner er:couraged the Committee to follow up on the following:
. Committee views on the health effects of low levels of ionizing radiation and the Linear No-Threshold (LNT) model. The Commissioner believes that the NRC needs to consider all the available data on this issue and revisit the LNT mode . Committee views on the NRC research programs and whether the agency's 1 budget reductions are prematurely terminating important research activities l
. The Committee needs to think in terms of being a regulator. In providing advice to the Commission, the Committee should consider the impact on the regulato I Prooosed Revision 1 to NUREG-1022. " Event Reoortina Guidelines.10 CFR 50.72 and 50.73
[ Note: Mr. Noel F. Dudley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Seale, Acting Chairman of the Plant Operations Subcommittee, introduced the session by explaining the development of Revision 1 to NUREG-1022, " Event Reporting Guidelines,10 CFR 50.72 and 50.73,"which began in 1991. He noted that Revision 1 consolidates NRC reporting guidance, which presently exists in I several documents dating from 1983, into a single reference documen NRC Staff Presentation Mr. Dennis Allison, Office for Analysis and Evaluation of Operational Data (AEOD),
explained the background of Revision 1, the staff resolution of public comments, and the key differences between NUREG-1022 and Revision 1. He presented the changes made to the NUREG-1022 guidance for event reporting. Mr. Allison stated that the staff plans to publish Revision 1 in final form and initiate rulemaking to resolve issues associated with the present rules and to better align reporting requirements with current NRC risk-informed need l
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' December 3-6,1997 The ACRS members and the staff discussed specific changes to reporting guidelines in NUREG-1022, the voluntary reporting guidalines added to Revision 1, and the necessity for proceeding with rulemaking. Mr. Allison_ explained that rulemaking would be necessary to eliminate the requirements for some reports, which the staff has determined to be excessiv NEl Presentation Mr. James Davis, NEl, commented that even though the guidance for making voluntary reports in Revision 1 would not bs enforceable, the industry viewed the L guidance as prescribing additional requirements. He stated that examples used in Revision i for reporting unanalyzed conditions were essentially rulemaking, since the conditions, in some examples, were not presently required to be reporte Conclusion The Committee issued a letter to the Executive Director for Operations, dated December 10,1997, an this matte Proposed Final SRP Chanter 19 (General Guidance) and Reaulatorv Guide DG-
)- 1061- for Risk-Informed. Performance-Based Reaulation. including Use of Uncertainty Versus Point Values in the PRA-Related Decisionmaking Process
[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. George Apostolakis, Chairman of the Subcommittee on Reliability and Probabilistic Risk Assessment (RPRA), introduced the topic to the Committee. He introduced cognizant NRC representatives and requested they begin their presentation on the proposed final Regulatory Guide 1.174 (formerly DG-1061) and Standard Review Plan (SRP) Chapter 19 (General Guidance) for risk informed,
' performance-based regulation. Dr. Apostolakis also noted that the C:ommittee expects to prepare a report to the Commission in response to the Stafl' Require -
monts M3morandum dated May 27,1997, regarding the use of uncertainty versus point values in the PRA-related decisionmaking proces '
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447th ACRS Meeting 13 December 3-6,1997 NRC Staff Presentation Messrs. Thomas King, Office of Nuclear Regulatory Research (RES), and Gary Holahan, NRR, led the discussion for the NRC staff. Messrs. Mark Cunningham, RES, and. Gareth Parry, NRR, provided supporting discussion. The staff reviewed the proposed changes to Regulatory Guide 1.174 and SRP Chapter 19 resulting from discussions with the RPRA Subcommittee on November 12-13,1997. The staff reviewed the principles of risk-informed regulation, staff expectations for licensee submittals for changes to the current licensing basis (CLB), and accep-tance guidelines for evaluating licensee submittals. The staff also discussed its approach for handling treatment of uncertainty, combined change requests, and issues related to PRA quality. Significant points made during the discussion include:
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The staff requested a report from the Committee regarding the acceptability of Regulatory Guide 1.174 and SRP Chapter 19. The staff requested that this report also address its approach for treatment of uncertainty and PRA qualit .
Policy issues include: acceptance guidelines for very small increases in risk, treatment of uncertainties, acceptance guidelines for shutdown operations, and temporary change .
Major changes in Regulatory Guide 1.174 and SRP Chapter 19 include: 4
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Modification of the principles in accordance with Subcommittee's suggestions on November 12-13,199 Clarification of the definition of CLB to provide for the use of the 10 CFR 54 CLB definition for license renewal, so that there is no implied .
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increase in the types of changes requiring NRC approva Footnotes added to the " figures" for core damage frequency (CDF)
and large, early release frequency (LERF) to indicate that the boundaries are approximation ]
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The staff provided additional guidance to clarify the figures. In particular, a brief narrative was added to clarify that the region for j
" increased management attention" means increased NRC manage- l ment attention with respect to the decisionmaking proces 'l
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447th ACRS Meeting 14 December 3-6,1997
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The staff added additional documents to the reference and bibliogra-phy sections per the request of the Subcommittee on November 12-13,199 . NRC expectations include:
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Assurance that the principles for defense-in-depth and safety margins are me Where risk increases are proposed, the staff expects licensees to describe the benefits and to demonstrate that these benefits clearly outweigh the proposed risk increase The staff expects licensees to use CDF and LERF as the bases for acceptance guidelines. Use of the Commission's Safety Goal quantitative health objectives (QHOs) is acceptable; however, in practice, using this approach would require special attention to the methods and assumptions in the analysis as well as evaluation of the treatment of uncertaintie The analyses should reflect the actual design, construction, and operational practices of the facility. The scope and quality of PRA required should be commensurate with the subject application being requeste Performance monitoring, feedback, and corrective action should ensure that no adverse safety degradation occurs related to the j treatment of uncertaintie j
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Licensee documentation should identify the key assumptions in the PRA that impact the application and commitments made to support the applicatio . Bundling of combined change requests (CCRs) should be for related changes (e.g., single system or activity, same function, or type of change, etc.).
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Use of mean values for companson with guideline ,
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447th ACRS Meeting 15 December _3-6,1997
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Identification of sources of uncertainty: parameter, modeling, and completeness. Sensitivity calculations can be made for parameter and modeling uncertainties. Quantitative and qualitative analysis should be used on completeness uncertaintie For very small changes, the focus should be on the sensitivity of ACDF and ALER Dr. Shack expressed the view that Principle 4 should focus on " proposed changes" rather than on " proposed increases" in CDF. The staff agreed to change the language per Dr. Shack's suggestio Dr. Apostolakis suggested that additional analysis (e.g., Level 3 PRA) is needed if the QHOs are to be the basis for a licensee request. The staff reiterated that the analysis must be appropriate for the requested actio The Committee and staff discussed the possible use of shading in the figures for CDF and LERF to indicate increasing / decreasing risk. Drs. Apostolakis and Kress expressed the view that the use of shading helps to communicate the relative risk within each region. The staff agreed to consider this reques At the conclusion of the meeting, Dr. Apostolakis informed the staff that the Committee plans to prepare reports to the Commission regarding these matter Conclusion The Committee issued a report to Chairman Jackson, dated December 11,1997, on the proposed final Regulatory Guide 1.174 and SRP Chapter 19. The Committee also issued a report to Chairman Jackson, dated December 16,1997, on the use of uncertainties versus point values in the PRA-related decisionmaking proces X Ooeratina Events at Oconee Nuclear Power Plant Units 1 and 2
[ Note: Mr. Noel F. Dudley was the Designated Federal Official for this portion of the' meeting.]-
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447th ACRS Meeting 16 December 3-6,1997 Introduction Dr. Don Miller, Acting Chairman of the Plant Operations Subcommittee, introduced the session by noting the number of augmented and special inspections that the staff had performed at the Oconee Nuclear Station in response to recent event He stated that he saw no commonality between the events and encouraged the ACRS members to look for any commonalities during the presentation Emeraency Power System Failures Mr. Paul Fredrickson, -NRC Region ll, described the emergency power system failures that occurred on June 20 and June 23,1997. On June 20, the Keowee hydroelectric Unit 1 failed to start in response to an emergency start signal, which was generated by an operator error at the Lee Steam Supply Station. M ;
Fredrickson stated that the team identified the following problems related to the 1 event:
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. ineffective procedures and operator training at the Lee Station, e incorrect voltage set point modifications made to the Keowee Unit 1 field flash circuit, and
. inadequate electrical breaker preventive maintenance procedure On June 23, safety-related circuit breakers at Keowee Station failed to close due to operator error while resetting the bus lockout. Mr. Fredrickson stated that the team identified the following problems related to the event:
. a faulty timer in the beaker logic circuits, e inadequate timer calibration procedures, and
. inadequate lockout reset procedure The Committee members and the staff discussed the types of timers used on the breakers,-the training program for the Lee Station operators, and the operating sequence for restoring offsite power to the Oconee Statio r .
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447th ACRS Meeting 17-December 3-6,1997-Unisolable Reactor Coolant Leak Mr. Edward Girard, Region ll, described the event at Oconee Unit 2 caused by an unisolable reactor coolant leak. The leak resulted from a crack in the high pressure injection line to the primary coolant loop nozzle safe-end weld. The crack was caused by high cycle low stress thermal fatigue. Mr. Girard stated that the licensee-identified root cause was an ineffective examination program for high pressure injection lines. The staff has issued an Information Notice regarding the examina-tion program problem The Committee members and the staff discussed the periodicity of licent.ee weld inspections and Region ll audits of augmented inspections. They also discussed the training of the licensee's nondestructive-examination inspectors, confirmation of leakage behind the thermal sleeves, and the licensee actions for dealing with identified temperature stratification in the injection line pipin Damaae to Hioh Pressure Iniection Pumos -
Mr. William Holland, Region 11, described the sequence of events that resulted in damage to two high pressure injectiorj pumps during an Oconee Unit 3 cooldow The damage occurred when the operators failed to identify the loss of water in the letdown storage tank, which was suppling water to the operating pumps. M Holland explained that a leaking fitting in a common reference leg to the tank level indicators resulted in the level indicators failing at mid-scale. He noted that contributors to the event were:
. ineffective management response to regulatory challenges, e inadequate potential hazards analysis,
. inadequate performance monitoring and trending, e inadequate root and common-cause analysis, and
. inadequate management expectations and networkin The Committee, staff, and licensee discussed the following issues:
. reasons why the common-cause mode failure was not identified by the plant-specific Individual Plant Examination,
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447th ACRS Meeti December 3-6,1997
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corrective actions to change operator awareness and sensitivity,'
a conditions that would result in pump damage, and
reasons why opportunities to correct an identified design deficiency were not pursue Conclusion This briefing was for information only. No Committee action was require Xl Canability and Aoolication of the EPRI CHECKWORKS Code (Open)
[ Note: Mr. Paul A. Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr. Kress, Chairman of the Subcommittee on Thermal-Hydraulic Phenomena, noted that the topic for discussion is flow-accelerated corrosion (FAC) and the use of the Electric Power Research Institute (EPRI) CHECWORKS code for prediction of FAC wear rates for nuclear power plant secondary-side components. He noted that questions had been raised regarding the use and application of this code, since piping ruptures had occurred at nuclear power plants where the code had been applied. He said that presentations would be provided by representatives of the NRC staff and EPR NRC Staff Presentation Mr. Krzystof Parczewski, NRR, discussed issues pertaining to the degradation of )
caMon steel components by FAC. Specifically, he noted the characteristics of FAC, the physical variables affecting the rate of FAC, plant systems susceptible to FAC, and a history of FAC-induced failures seen in nuclear power plants. Regarding regulatory efforts to address FAC issues, Mr. Parczewski noted that, since 1982, NRC has issued 12 Information Notices, one NRC Bulletin, one Generic Letter (GL) 1 89-08), two NUREG reports and a SECY Commission Paper pertaining to this matter. In response to Dr. Catton (ACRS Consultant), Mr. Parczewski said that FAC I is considered a safety issue, as documented in GL 89-08. The NRC relies, in part, on use of the Maintenance Rule as a regulatory enforcement vehicle for this issu NRR also noted the EPRI development work pertaining to the "CHEC" series of codes, q
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. . 1 447th ACRS Meeting 19 December 3-6,1997 i
Dr. Apostolakis requested [and later received] material concoming a Workshop on FAC, held in Philadelphia, PA in 199 There was some discussion of the CHECWORKS code, initiated by a question from Dr. Catton concoming the staffs knowledge of the code's contents. In response to a comment from Dr. Apostolakis, Mr. Jack Strosnider, NRR, said that the staffs interest in the use of the CHECWORKS code is to ensure that it is properly applied; NRC is not knowledgeable of the code's contents. Dr. Apostolakis asked if the NRC should have access to the details of the code. Dr. Bindi Chexal, EPRI, noted that every case seen to date where licensees have experienced FAC-induced failures while using CHECWORKS has been found to be the result of a misapplication of the code. This includes the recent pipe failure event at the Ft. Calhoun nuclear power statio EPRI Presentation Dr. Chexal discussed the use of the EPRI CHECWORKS code. Due to time constraints, his presentation was conducted in a question-and-answer format. D Chexal's comments focused on the capabilities of CHECWORKS and its qualifica-tion via use of relevant laboratory test data generated primarily in England and Franc During this discussion, the following points were noted and information requests made:
. Dr. Chexal said that since 1986, all FAC-included component failures could be predicted, a priori, using CHECWORKS. He repeated the above point that all licensee problems seen while using the code can be subscribed to its misapplicatio . Dr. Jeffrey Horowitz (co-author of CHECWORKS) noted that there is no conclusive proof that so-called computational fluid dynamics codes give results that ere superior to CHECWORKS calculational result . Referring to a FAC correlation developed by Dr. W. Kastner, KWU, that showed results that were not consistent with those obtained by CHEC-WORKS, Dr. Chexal said that Dr. Kastner's correlation was too conservative for practical use by a plant vendor. His later work now falls in line with the EPRI approach, because he is correcting his model with use of plant measurement dat _______ _ . . .. . .
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447th ACRS Meeting 20 December 3-6,1997
. Dr. Catton, noting that the modeling of component geometric factors is key to this issue, accepted Dr. Chexal's offer to provide information on the modeling of these factors in CHECWORK . Dr. Apostolakis asked that EPRI send the ACRS a copy of its postmortem analysis of the Ft. Calhoun pipe rupture event, with regard to the use of j CHECWORK Conclusion This briefing was for information only. No Committee action was require Xil EXECUTIVE SESSION (Open)
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[ Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.] Reports, Letters and Memoranda REPORTS
. Prooosed Final Reaulatorv Guide 1.174 and Standard Review Plan Chaoter 19 for Risk-Informed. Performance-Bamad Reanistion (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 11,1997.)
. Prooosed Revisions to 10 CFR 50.59 (Changes. Tests and Exoeri-ments) (Report to Shirley Ann Jackson, Chairman, NRC, from R. Seale, Chairman, ACRS, dated December 12,1997.)
. Credit for Containment Overoressure to Provide Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumos (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated December 12,1997.)
. Treatment of Uncertainties Versus Point Values in the PRA-Related Decisionmaking Process (Report to Shirley Ann Jackson, Chairman,
- NRC, from R. L. Seale, Chairman, ACRS, dated December 16,1997.)
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t-447th ACRS Meeting 21 December 3-6,~ 1997 LETTER
. Pronosed Final Revision 1 to NUREG-1022. " Event- Reoortina Guidelines 10 CFR 50.72 and 50.73 (Letter to L. Joseph Callan,.
Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated December 10,1997)
MEMORANDA
. Prooosed Generic Letter. "Auamented insoection of Pressurized-Water Reactor Class 1 Hioh-Pressure Safety Iniection Pioina" (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 9,1997)
. Draft Reaulatorv Guide DG-1071. " Standard Format and Content for Post-Shutdown Decommianlonina Activities Ranort"(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 9,1997)
. Year 2000 Comouter Issue (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 10,1997)
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Prooosed Generic Letter on Interim Guidance for Uodatina Final Safety Analvsis Reoorts (Memorandum to L. Joseph Callan, Execu-tive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated December 10,1997) Reconciliation of ACRS Comments and Recommendations
[ Note: Mr. Sam Duraiswamy was the Designated Federal Official for this
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portion of the meeting.]
The Committee discussed the response from the NRC Executive Director for Operations to ACRS comments and recommendations included in recent ACRS reports:
.. The Committee discussed the response from the NRC Executive Director for Operations dated November 26,1997, responding to
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447th ACRS Meeting 22 December 3-6,1997 L ACRS comments and recommendations included in the ACRS report dated October 8.1997, conceming the Human Performance and Reliability implementation Pla The Committee decided that it was satisfied with the EDO's respons * The Committee discussed the response from the NRC Executive Director for Operations dated Novernber 12,1997, responding to
- ACRS comments and recommendations included in the ACRS report dated October 9,1997, conceming proposed changes to 10 CFR 50.59 and proposed Revision 1 to Generic Letter 91-1 The Committee plans to continue its discussion with the staff during future ACRS meetings. A briefing is planned for the February 1998 ACRS meetin . The Committee discussed the response from the NRC Executive Director for Operations dated November 10,1997, responding to ACRS comments and recommendations included in the ACRS report dated October 10,1997, concerning the staff response to ACRS comments on the Differing Professional Opinion pertaining to steam generator tube integrit The Committee decided that it was satisfied with the EDO's respons 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 December 3,1997. The following items were discussed: FEDERAL REPORTS ELIMINATION ACT The Federal Reports Elimination Act of 1997 was a bill introduced as S.1364 on November 4,1997. Although Senate action is anticipated before adjournment, it is unlikely the House will act on similar legislation. This bill would eliminate the requirement for the ACRS Report to Congress. The ACRS had originally asked that the Report to Congress be included in the list of Federal Reports to be Elimi-nated, but had subsequently requested that the ACRS Report Dol be l
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447th ACRS Meeting 23 December 3-6,1997 j eliminated. To ensure that this Report to Congress is not eliminated, a memorandum will be sent to the Office of the General Counsel (OGC) stating that ACRS does not want the Report to be dropped and giving an explanation for this change in positio RECOMNIENDATION The Subcommittee recommended that a letter to the Commission be drafted for Dr. Seale's signature, requesting withdrawal of the earlier ACRS request for elimination of the requirement for a Report to Congress on the NRC Research Progra . PREPARATION OF MFFTING MINUTES j The procedures for the preparation of Subcommittee Meeting Minutes '
have been revised to reduce the burden on the ACRS Engineers. The new procedures continue to meet the requirements of the Federal ;
Advisory Committee Act and 10 CFR 7.13. The minutes will contain 1 sufficient detai! to allow a person absent from the meeting to readily understand the important issues discussed, the views of those -
participating in the meeting, and the important issues and concerns raised by Committee Members and consultant I RECOMMENDATION The Subcommittee recommended that Members review the new guidanes on preparing Subcommittee Meeting Minutes and provide any comments to the Executive Director as soon as possibl I CONFLICT-OF-INTEREST The ACRS Executive Director issued additional guidance to the staff on November 20, 1997, on handling of conflict-of-interest (COI)
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reviews for ACRS/ACNW Members. This was in response to a re-quest from the staff for additionalinformation on COI, ac a result of an )
earlier meeting with representatives of OGC on this subject. Two i d
Senior Staff Engineers have forwarded memoranda on COI issues to the ACRS/ACNW Executive Director that emphasize the need for ACRS Members to work through the ACRS staff on any matters related to or having a potential impact on Committee activitie Meetings with NRC staff or others not related to ACRS current or i
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447th ACRS Meeting ' 24 December 3-6,1997
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future activities should be scheduled so as not to interfere with or have an impact on Committee meetings. ACRS Members should also avoid being on peer review panels on subjects related to ACRS current or future activities. Any questions related to these matters should be directed to ine ACRS Chairman or ACRS Executive Directo RECOMMENDATION The Subcommittee recommended that Members be aware of the appearance of conflict of interest when they serve on peer review panels on subjects related to current or future ACRS activitie Generally, Members should attend such pancis only as ACRS Members, not as invited experts for the NRC staff, and they should not give direction to the staff on issues that will later be reviewed by the ACRS. Members who serve on such panels, because of contractual requirements or other circumstances, are advised to announce this fact at the beginning of the ACRS review, indicate the exact parameters of their involvement in the material being presented to the ACRS for review, and recuse themselves from the revie Members are also reminded to go through the ACRS staff when arranging meetings with NRC staff or others on any matters related to or having an impact on ACRS activitie . NEW MEMBERS The Commission has selected Dr. Graham Wallis as a new member for the ACRS, subject to the usual government paperwor "
Last month, the ACRS and ACRS Member Screening Panel inter-viewed a candidate in the plant operations field, and the response to these interviews was very positive. The ACRS staff has recently prepared a Federal Register Notice and Press Release for Commis-sion approval to solicit new candidates in the area of Plant Operations and/or Probabilistic Risk Assessment. These advertisements should 9 pear within the next month, and some new candidates should be
- chosen early in 1998. In the meantime, previous applications and recommendations are being reviewed to determine if there are individuals who should be reconsidered or have been overlooked.
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447th ACRS Meetin '
December 3-6,1997 INTERNATIONAL MEETINGS The ACRS has wntten to the Japanese requesting that the Quadripar-tite Meeting be held in September 1998, rather than April 199 There has been no response. If the meeting is confirmed for September 1998, an inquiry will be made about the possibility of meeting with the U.K. Advisory Committee on the Safety of Nuclear Installations in May.or June 1998. To accommodate this foreign travel in the budget, no more than 6 or 7 ACRS members should attend the Quadripartite Meeting, and no more than half the Members should attend the meeting in Englan . ACRS RETREAT A revised agenda has been prepared for the ACRS Retreat, to be held on January 30-31,1998. Revisions have been made based on Members' comments. This agenda will be finalized during the December 3-6,1997 meetin RECOMMENDATION The Subcommittee recommended that Members review the draft agenda and provide any comments or changes to the Executive Director before the end of the December meetin . ELECTION OF OFFICERS Election of Officers was held during the December 1997 meetin Those Members who indicated in writing that they did not wish to be e;ected as an Officer are: Dr. Shack, Dr. Fontana, Dr. Uhtig, and M Barto Elected officials were Dr, Robert Seale, Chairman; Dr. Dana Powers, Vice Chairman; and Dr. Thomas Kress, Member-at-Larg . FINANCIAL DISCLOSURE REPORTS Members should have received a recently updated Financial Disclo-sure Report from OGC. Members should review and report any errors or other problems (e.g., omissions, wrong titles, etc.) to the Chief, Operations Support Branch, or to the Executive Director, ACRS.
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447th ACRS Meeting 26 December 3-6,1997 RECOMMENDATION The Subcommittee recommended that each Member review the OGC letters and report any errors to the Chief, Operations Support Branch, or to the Executive Director, ACR . HUMAN PERFORMANCE AND HUMAN RFI IABILITY IMPLEMEN-TATION PLAN A senior staff engineer provided a summary of a meeting between D Apostolakis and members of the NRC staff to discuss development of the Human Performance and Human Reliability implementation Plan, in the absence of a transcript.or notice of a meeting on this subject, this summary was provided to Members for their informatio Future Meeting Agenda Appendix IV summarizes the proposed items endorsed by the Committee for the 448th ACRS Meeting, February 5-7,199 The 447th ACRS meeting was adjourned at 2:00 p.m. on Saturday, December 6,1997.
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Federal Register / Vol 62, Ms. 224 / 'I6ehy, NMh- 1
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er =ad-adal metmo,includies Advisory Committee on Reactor . Hereday. December 4,1997 -
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Remarke Maia=1 tion: Saancial desa,such as Safeguards willhold a meeting on soaAX-e35 AX: )-
' December M 1997,in Conference '
. by the ACRS Chairman (
N 5'"c ,# M,,,,, ,b D . D wigggh . Room T-2ns, ,,,,,,,sius Roewm. Pa.,
,,,,,,,,t.ede, no ACRS Cha, man wm
- Rochme, Maryland,b dam of thisf opening manarks agardingconduct fi.s'c ss2b(c).(4) and D) of the - was pmviously ublishedin . . of the meeting. ' i /
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l na the Samhine Ac . the F Register on unday,s 3:35 AX-20:25 AX: Proposed /
Deted: November 17,see January 23, see7 (61FR asse). .T Revisions to 20 CFR 50.59, Changes, V ->
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Wedmeeder. December a, see7
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Remarks and hold - .
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(FR Dec. e7-30515 Filed 11-se.4P; e:45 am)- 2 2 P K -2:15 F X :
sums osos sans soar . A by the ACRS Chairman )- Stations g,,, ,g - tatives of -
Proposed 1 -
N ACRS Chairman will -
b NRC staf '"'
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NATIONALSCIENCE FOUNDAMOlt
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Core - hear ra==,eaHans by and hold In accordance with the Federal 2:25 FX-2:28 PX: * tatives of ,
Cooling System StminerR discuadons with ~ ,
Advisory Committee Act (Pub.L. 92- .
the-463, as anwnded), the National Science (Open)-b Committee will hear tim NRC staE Foundation announces the following . presentationsbyandhold . . c ,ge g,tur onInterim
- discussions witn apresentatives of dance for Updating Final Safety meeting .
the NRC staE regarding the stas's . 7 Name and Comsdass Code- @ Safety Evaluation on the. . 2mA, 3 ,g, g,p5desting PK-2m rX: with ,
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Emphasis Panelin Human Rosemos
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BWROwnere Group tility r - c,,,,,,=8=='oner Dicus ( bb Development (ettee .
' Resolution Guidance for emergency Comanttee willamet th NRC
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Dote and TIow: December ts-12.seerr core cooling system suction strainer ramminaloner Dieus to discuss ~
eso aJa. to 5:00 p.e Ploce: Nations! Science Fe== dada = 4201 blockage,and related matter Items of mutualinterest. 'adad8a*
Wilaos hi ._,-t Rosen 390. Arlington, VA 2:25 FX-3:25 PX: Assurance of NRC Safety Research Program.Usis
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of PRAin the tory 22:3 Sufffeient Net Poeftive Suction , Elevation Decistoamaking l
Dr. A.jenes Hick *
NeodforEme'3e8CYC 8'8Cooll88 - of com damage to a I fact and Confalament Hoot Removal Program Director.Hunan Renowne n=d==antal Safety , and -
i Pumps (OpenbThe Committee
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Development Diviolon. Room ets. National willhear presentations by and hold Health E5 sets of Low Invels ofs. i l Science Fonad.etan. 4201 Wileos E_.-d. . discussions with re resentatives of . Ionising Fadiada Arlington, VA 22230 Telephone: (703) aos- g the ACRS g:og pg.3m PX: Proposed Final the NRC staE mg 163 * Revision 2 to NUREG-2022,Ehrat purpose of Adesting:To provide edelas e4 concerns associated with the .
secommodations coneeming poposale proposed final Generic Intter on Reporting"Guidelinee,20 CFR 50.72 r-suba ned N Aaane euppe Assurance of Suf5cient Not Positive and50.73 (Open)-TheComsdttee
, ,g * Suction Head for Emergency Cos' willhear presentations by and hold Ain.n,== for Minority Participation discussions wi resentatives of. ,
Cooling and Contala=aae Heat -
.. proposals es pen of me enlaction process der . Pumps... the NRC staf proposed Remo
\ oward Baal revision to NUREG-1022.
c Reason for Oceing:The proposals being . 3:30 PK-4:30 FX:NRCPerformance Plan (Open)-b Committee will - 3:15 PX-7:00 PK: Preparation of ~
mviewed include information of e .
ACRS Reposts (Open)-The
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preprietary or confidential nature,includine hear presentations by rud hold s eachnical information; Anantial data, such as . discussions with the Odef rammittee will continueits
discussion of proposed ACRS ..
' I* "" Finana:ial OSicer and a
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,', , g* dg,Pg d with b representative of the OtBee of th reports on matters considened '
tions during this nosoting bmpoests.These
.s.c asab(c) (4) and (s) ofmuereiro the Government exemp%Executive s Dimetor fo nnaam "
in the sunsw= 4 .
mgarding tlw NRC's Friday,rh 3, tegy Plan. . - .
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D 4:30 PX-6:30 PX: ACRS Report t :30 AK-6:35 AX: Opening Remoths y, Qeted gg,, ,^ 17*1seF .L -
by the ACRS Chairman (Open)~
' Congress on the NRCSofet Coemdues Managesent of#eer. .. i Research Progrom (Open)-b a . The ACRS Chairman will make /
(FR Doc. 97-3051s Filed 11-st-er; a:45 aml opening remarks regarding conduct Committee will hold discussions ,
'of the meetin 'F ausse coes ress.ee.as
. with the NRC staf, as naadad
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mgarding the NRC Safety Raeearch ' s:35 AX-20m AX: Prop (osed Final StandardReviewPlan SAP)
, Program.The Committee will also -
discuss a proposed ACRS report to , Chopter 29 and Regulatory Gulds NUCLEAR REOULATORY * .
DG-2062 for Risi. Informed, COMMISSION
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. Congress on the NRC Safet '
Performance.Bosed Regulation,
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Research Programa. ~ .
Advloory Committee on Remotor . gg,, ,f '- Includin$uesin the PRA.RefotedUm of Un
,g pg,7g pg. p,,p),,,Tbe W *9"*"I*I*****9 N**** *
ACRS Reports (Open -
Committee will discuss proposed .
Point Va Decisionmaking Process (Open)-
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in accordance with tim purposes of . b Committee will hear I ACRS reports on matters considered *
Sections 29 and 182b. of'the Atomic , during this meetin .
presentations by and hol Energy Act (42 U.S.C. 2039. 2232b), the
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62079
, famions with resentatives cf Sub-mW (Open/ Closed)-The
.the NRC etaff pro In accordanceLwith Subsecti:n to(d)
. Anal SRP Chapter 29, Tommittee will hear a mport of the P.L.92-463,I have determined that it is tory ~ Planning and Procedures Guide DG-1061, and use of necessary to close portions of this uncertainty versus point es in Subcommittee on matters related to ' meeting noted above to diar = matters the conduct of ACRS business, 8 hat relate solely to the internal the PRA-related decialaa~ 1a:
proces qualifications of candidata nominated for a personnel rules and practices of this 20:25 AX-222 Noon: '
intment to the Advisory Committee per 5 U. Events at Oconee Nu Power ACRS, agenda e lannin meeting, and 552b(c)(2) and to discuss information Plant Units 2 ands (Open)--b onal d the release of which would constitute a
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Committee wiD hear presentations personnel matters relating to the clearly unwarrented invasion of by and hold discussions with - ACR ' personal rivacy.per 5 U.S.C 552b(c)(6).
representatives of the NRC staff INote: A Portion of this session mos be
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F information regarding topics a
pgarding the results of the '
dosed to dlacuss organizational and to be stia-d, whether the meeting j investigation performed by an nibel matters that relate solel has been canceled or rescheduled, the temal personnel rules and nrar*y to the in== of this
.Aupnented Inspection Team (AIT) Advisory Committee, and informmHna the r%.taaaa's ruling on requests for the of sneJune 20 and 23 event at op ortunity to present oral statements
, Oconee Unit 1 involving isuure of selease anwarranted of which isvosson wouldprivac of personal constitute an thea clearly)
time allotted therefor, can be ,
emergency electrical power suppl obtained by contacting Mr. Sam ~
, and of the April 22,1997 eve,nt at ,pg Ag.,gpg gjpg ggpg Durgiswam , Chief NuclearReactors Oconee Unit 2 that involved - ,wy.Pieparadon ofACRS Branch (tel hone 301/415-7364),
inoperability of the high pressure r its (Ope)--h Commiuse between 7:30 A.M. and 4:15 PM ES ,
1 continue its' discussion of ACRSmeetin agenda, meeting ,,
A S. buttyand ProPmd ACRS reports on matters CTIQaj j
am Scotton o Checkworks considered during meeting ,,
e (Open)-f Thethe Committee will on the internet at http://www.nre. gov /
d:00FX-4:30FXrMisceDanwus-hear presentations by and hold
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(Open)--h Committee will : ACRSACN '
discussions with resentatives of . discuss matters related to the The ACRS m dates for Calendar the NRC staff and Power conduct ofI'nmmittee activities and Year 1998 are provi ed below:
Rmmh Institute (EPRI) matters and speciSc issues that ,
the ce ability and op lication of e ACRS were not completed during Meeting EPRI ockworks Previous mee ,as time and No- 1998 ACRS Meehn9 Dete 3:25 PX-3.45 FXrFuture ACRS c availability of rmation permi Acuvmes ( }--The Caninee g4 wiD discuss recommendations Procedures for the coziduct of and 448 Feb. M .199 , cf the Planning and Procedures . partici tion in ACRS meetings were 449 Mar. 2-4,199 Subcommittee regarding items hublis ed in the Federal Regieter on 460 Mar. M.199 Posed for consideretion by the ptember 4,1997 (82 FR 46782). In (Se% Research Progrern)
Caninae during futm ' accordance with the procedurw, oral 461 Apr 2-4,199 :45N( 60PXrReconed/odon or written views may be presented by . $
members of of the public,inclu 464 ,
$ 9d My s-10,199 ACRS Comments ""a -
reprwentatives of the nuclearin ,
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Recanendadons (OpenWe electronic recordings will be perm! 465 Au9 4 o Meetn9 . .,
Sept. 2-4,199 Canluee wiD discusa responses only during the open portions of the - 468 Oct.1-3.1998. .
from the NRC Executive Director for meeting, and qumtions may be asked . 457 N w 5-7,199 Opentions (EDO) to comments and only members of the Committee,its 468 Dec. M m recommendations included in * "' dshNP du!&g recent ACRS reports, including the make o tements a d notify U*tedmmmber 14. m EDO response to the October 10 Mr. Sam Duralswamy, Chief. Nuclear ^*d"'I 8'ase, 1997 ACRS report related to the Reactors Branch, at least five days Advisory mauninae Manosement of) fee differing professional opinion before the meeting,if possible, so that (FR Doc. 97-30526 Filed 11-19-47; 8:45 ami to eteam generetor tube app priate arrangements can be made esAsse coot rsese e to w the necessary time during the '
d:00PY-4755PX:
oye,,,p,f gyypp, Election ofACRS meeting for such statements. Use of still,
}_ g ' motion Icture, and television cameras Committee wul elect th Chairman during meeting my be limited to NUCLEAR REGULATORY selected portions of e meetin COMMi&SION
- and Vice Chairman for the ACRS'
- and Member-at- for the * determined by the Chairman. g as PlanMng and ENYlRONMENTAL PROTECTION Information regarding the time to be set AGENCY 4:25 7 5f.: o'n o c sta gth ChiefoYth u Joint NRC/ EPA Ouldence on Testing ACRS Reports (Open Reactors Branch rior to the meetin . In Requirements for Mixed Radioactive Commitke will continueits view of the possi ility that the och ule and Hazardous Waste discussion of proposed ACRS for ACRS meetings may be adjusted by re ris on matters considered the Chairman as necessary to facilitate AGENCIE8:EnvironmentalProtection d g this meetin the conduct of the mee g Agency and Nuclear Regulatory .
isons
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- Commissio S; turd:y, Der ==I=er 8,2 997 h efofthe uc earReac rs
, 8:30 AM-9:00 AX R P1 arming and ofthe uros .
if such racheduling would result in ch $ c n e Ies Req mets
. majorinconvenienc for Mixed Wast .
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$ : ADVISORY COMMITTEE ON REACTOR SAFE 2UARDS 1 WASHINGTON, D. C 20505
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\***e* Revised: December 1, 1997 SCREDULE AND OUTLINE FOR DISCUSSION 447th ACRS MEETING Danamhar 3-5. 1997 I WEDMEED1Y. DEcaumER 3. 1997, enMTEREMcE ROOM 2B3. TWO WHITE FLINT MORTE. ROCEVILLE. MARYL1MD D7 '
1) 1:00 - 1: 2 Openina mamarks by the Acns chairman (Open)
1.1) Opening Statement (RLS/JTL)
1.2) Items of current interest (RLS/JTL/NFD)
1.3) Priorities for preparation of ACRS reports (RLS/JTL)
03 I:57 2). 1:25 - anos Emergency core cooling system strainer Blockage (Open) (REU/AS)
2.1) Remarks by the Acting Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding the staff Safety Evaluation Report on the BWR Owners Group Utility Resolution Guidance l for Emergency Core Cooling System Suction Strainer Blockage, and related matter Representatives of the nuclear industry will provide their views, as appropriate, t 57 2: <t3 3) 2nes - 3m15 P.M. Assurance of sufficient Net Positive Suction Head for Emergency Core coolina and containment Heat Removal Pumpm (Open)
(TSK/PAB)
3.1) Remarks by the Subcommittee T Chairma ( Transersh ol f>c t-Eens 09 the irwe.t,'n {
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3.2) Briofing by cnd diecuacions with '
representatives of the NRC staff ,
regarding the ACRS concerns associated with the proposed
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final Generic Letter on Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pump Representatives of the nuclear industry will provide their views, as appropriat : 43 %
3445 - 3:30 *** BREAK ***
4) 3:30 - 4: he NRC Performance Plan (Open) (RLS/AS)
4.1) Remarks by the ACRS Chairman 4.2) Briefing by and discussions with the Chief Financial Officer and representative of the Office of the Executive Director for Operations regarding the NRC Performance Pla , g, \ ggg(
5) 4:30 - 5:20 ACRS Renort to Congress on the NRC 6: CC' 40 Safety Research Procram (Open) (DAP/MME)
5.1) Remarks by the Subcommittee Chairma .2) Discussions with representatives of the NRC staff, as needed, regarding the NRC Safety Research Progra YO 6 .' / O 6) 5:M - 9740 Preparation of ACRS Renorts (Open)
Discussion of proposed ACRS reports on:
6.1) Annual ACRS Report to Congress on the NRC Safety Research Progra l (DAP/MME)
6.2) Emergency Core Cooling System Strainer Blockage. (REU/AS)
6.3) Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and ;
Containment Heat Removal Pump l
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(TSK/PAB)
THURBDAY, DECEMBER d, 1997. CONFERENCE ROOM 2B3. TWO WHITE FLIMT MORTH, ROCKVILLE, MARYLAND 7) 8:30 - 8:35 openina Remarks by the ACRS Chairman (Open) (RLS/JTL)
<
8) 8:35 - 10:35 Proposed Revisions to 10 CFR 50.5 '
Chanaes. Tests. and Experiments (Open)
(DAP/MTM)
8.1) Remarks by the Acting
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. . Subcommitt03 Chairmn .2) Bricfing by end diccuccions with j representatives of the NRC staff l regarding proposed revisions to
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10 CFR 50.59 and related matter Representatives of the nuclear industry )
will provide their views, as appropriat :33 - 10:20 *** BREAK ***
10:[d-11:30 '
9) Proposed Generic Letter on Interim Guidance for Updatina Final Safety Analysis Reports (Open) (DAP/MTM)
9.1) Remarks by the Acting Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding the proposed Generic Letter on Interim Guidance for Updating Final Safety Analysis Report Representatives of the nuclear industry will provide their views, as appropriat :30 - 1:00 *** LUNCH ***
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i 10) 1:00 - 2 : DE Meetina with commissioner Dieus (Open)
(RLS/MME)
10.1) Remarks by the ACRS Chairma .2) Discussion with Commissioner Dicus on items of mutual interest, including:
- NRC Safety Research Program
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- Uno of PRA in th9 R gulatory Decicionm king Proc 2co 4
- Elevation of core damage frequency to a Fundamental Safety Goal
- Health Effects of Low Levels jjy, , g . yo ( H. 6.< ca g of Ionizing Radiation 11) 2:$O - 3:hh Proposed Revision i to NUREG-102 " Event ReDortina Guidelines. 10 CFR 50.72 and 50.73" (Open) (RLS/NFD)
11.1) Remarks by the Acting Subcommittee Chairman 11.2) Briefing by and discussions with representatives of the NRC staff regarding proposed final revision to NUREG-102 Representatives of the nuclear industry will provide their views, as appropriat vo \
3: 00 - 3:M ,
- BREAK ***
12) 3:36 - 7:00 Preparation of ACRS Reports (Open)
Discussion of proposed ACRS Reports on:
12.1) Annual ACRS Report to Congress on the NRC Safety Research Progra (DAP/MME)
12.2) Emergency Core Cooling System i
Strainer Blockage. (REU/AS)
12.3) Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pump (TSK/PAB)
12.4) Proposed Revisions to 10 CFR 50.59 and Proposed Generic Letter on Interim Guidance for Updating Final Safety Analysis Report (DAP/MTM)
12.5) Proposed Final SRP Chapter 19 and Regulatory Guide DG-106 (GA/MTM)
12.6) Use of Uncertainty Versus Point Values in the PRA-Related Decisionmaking Process. (GA/MTM)
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12.7) Proponcd Ravicion 1 to NUREG-1022, Event Reporting Guidelines, 10 CFR 50.72 and 50.73. (RLS/NFD)
i FRIDAY, DECEMBER 5, 1997. CONFERENCE ROOM 2B3, TWO WHITE FLINT MORTH, ROCKVILLE, MARYLAND 13) 8:30 - 8:35 Ooenina Remarks by the ACRE Chairman (Open) (RLS/JTL)
14) 8:35-10:hd Proposed Final SRP Chapter 19 and Regulatory Guide DG-1061 for Risk-Informed. Performance-Based Regulation, including Use of Uncertainty Versus Point Values in the PRI-Related Decisionmakina Process (Open) (GA/MTM)
14.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding proposed final SRP Chapter 19, Regulatory Guide DG-1061, and use of uncertainty versus point values in the PRA-related decisionmaking proces Representatives of the nuclear industry
, will provide their views, as appropriat US \
10: 2 - 10:24 *** BREAK ***
15) 10: -
12: Operatina Events at Oconee Nuclear Power Plant Units 1 and 2 (Open) (DWM/NFD)
15.1) Remarks by the Acting Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding the results of the investigation performed by an Augmented Inspection Team (AIT)
of the June 20 and 23 event at g Oconee Unit 1 involving failure 1 of emergency electrical power I
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t cupply, and of th3 April 22, 1997 cvant at OconO3 Unit 2 that-
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involved inoperability of the
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high pressure injection pum I 12:00 - 1:0 e**LUNCE***
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16) 1:00 - 3:00 Canability and Annlication of the EPRI CHECKWORKS Code (Open/Gaesed) (TSK/PAB)
16.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff and Electric Power Research Institute (EPRI) regarding the capability and application of the EPRI CHECKWORKS Cod (NOTE: A o ortiohx (r this' session may be el ed to d scuss E Q proprietary nformatA'on associated with the CHECKWORK Code.] N 3 -
3: *** BREAK ***
VF 4:15-17) 3: 2 - WEM5 Future ACRS Activities (Open) (RLS/JTL)
Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee i
during future meeting .'35 yo 18) Se65 - 4:09 Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et al./
JTL, et al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS report ) 4:hb- A P.M. Election of ACRS Officers For CY 1998 (Open) (JTL)
The committee will elect Chairman and Vice Chairman for the ACRS and Member-at-Large for the Planning and Procedures Subcommitte V: 5b - 9,'59 20) 4:15 - 7:00 Prenaration of ACRS Reports (Open)
SV 3 Discussion of proposed ACRS Reports on:
20.1) Annual ACRS Report to Congress on
, the NRC Safety Research Progra (DAP/MME)
20.2) Emergency Core Cooling System Strainer Blockage. (REU/AS)
20.3) Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pump .
' - (TSK/PAB)
20.4) Propocad R$ visions to 10 CFR 50.59 and Proposed Generic Letter on Interim Guidance for Updating ( Final Safety Analysis Report (DAP/MTM)
20.5) Proposed Final SRP Chapter 19 and Regulatory Guide DG-106 (GA/MTM)
20.6) Use of Uncertainty Versus Point Values in the PRA-Related Decisionmaking Process. (GA/MTM)
20.7) Proposed Revision 1 to NUREG-1022, Event Reporting Guidelines, 10 CFR 50.72 and 50.73. (RLS/NFD)
20.8) Capability and Application of CHECKWORKS Code.(TSK/PAB)
BATURDAY. DECEMBER 6. 1997. CONFERENCE ROON 2B3. TWO WNITE FLINT MORTH, ROCKVILLE. MARYLAND 21) 8: -
9: Report of the Plannina and Procedures Subcommittee (Open/ Closed) (RLS/JTL)
Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, qualifications of candidates nominated for appointment to the ACRS, agenda for the planning meeting, and organizational I
and personnel matters relating to the j ACR !
(Note: A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory Committee, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.]
22) 9:00 - (5550 Newn Preparation of ACRS Renorts (Open)
Continue discussion of proposed ACRS reports identified under Item 2 :00 - 1:00 ***LUNCE*** i 23) 1:00 - 4:00 Prenaration of ACRS RNoorts (Open)
(3:00-3:15 BREAK) Continue discussion of proposed ACRS reports identified under Item 2 \
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s 24) 4:00 - 4:30 Miscellaneous (open) (RLS/JTL) '
The Committee will discuss matters related to the co'nduct of Committee activitie's and matters and specific issues that were not completed during previous meetings, as time and i' .
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. . avcilability of information psrmi NOTE: * Presentation time should not exceed 50 percent of the
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APPENDIX lil: MEETING ATTENDEES 447TH ACRS MEETING DECEMBER 3-6,1997 NRC STAFF - December 3,1997 i A. H. Hsia, OCM/NJD J. Mitchell, OEDO C. Berlinger, NRR K. Kavanaugh, NRR M. Lynch, NRR J. Kudrick, NRR R. Lobel, NRR R. Caruso, NRR R. Elliott, NRR S. Bailey, NRR E. McKenna, NRR M. Malloy, NRR T. Bergman, NRR J. Roe, NRR S. Magruder, NRR A. Serkiz, RES M. Marshall, RES ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC H. Williams, BWROG-TVA B. Houston, Sequoia Consulting M. Mjaatvedt, PP&L C J. Peterson, Duke Engineering A. Singh, EPRI D. Smith, Entergy G. Zigla, ITS Cor J. Butler, NEl D. Raleigh, SERCH R. Ingram, Entergy M. Neal, NUSIS K. Unnerstall, Morgan, Lew & Backius P. Robinson, Winston & Strawn
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Appendix 111 2 447th ACRS Meeting l
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APPENDIXlil: MEETING ATTENDEES 447TH ACRS MEETING DECEMBER 3-6,1997 NRC Staff- December 4,1997 J. Mitchell, OEDO J. Perath, NRR J. Roe, NRR C. Craig, NRR R. Benedict, NRR B. Gramm, NRR J. Birmingham, NRR J. Kramer, RES N. Siu, RES
< A. Ramey-Smith, RES D. Allison, AEOD C. Rossi, AEOD M. Harper, AEOD R. Tripathi, AEOD ATTENDEES FROM OT_HER AGENCIES AND GENERAL PUBLIC T. Pietrangelo, NEl H. Fontecilla, VAP D. Walters, NEl N. Chapman, SERCH, Bechtel J. Weil M. Neal, NUSIS J. Davis, NEl J. Fulford, NUS c
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Appendix lil 3 447th ACRS Meeting l NRC Staff- December 5,1997 l P. Castleman, OCM/NJD J. Mitchell, OEDO M. Cheok, NRR G. Parry, NRR M. Malloy, NRR W. Rubin, NRR l. Jung, NRR J. Fleeu, NRR G. Bagchi, NRR D. LaBarge, NRR B. Dennig, NRR E. Benner, NRR S. Richards, NRR J. Lazevnick, NRR F. Ashe, NRR F. Burrows, NRR D. Nguyen, NRR J. Calvo, NRR S. Long, NRR B. Elliot, NRR M. McNell, NRR C. Petrone, NRR K. Parczewski, NRR J. D. Wilcox, NRR E. Sullivan, NRR R. Hermann, NRR M. Hartzman, NRR N. Siu, RES B. Hardin, RES A. Ramey-Smith, RES W. Holland, Ril P. Fredrickson, Ril E. Girard, Rll C. Rossi, AEOD ATTENDEEL .JROM OTHER AGENCIES AND GENERAL PUBLIC S. Floyd, NEl J. Fulford, LIS A. Wyche, SERCH/ Bechtel B. Peele, Duke Energy J. Burchfield, Duke B. Chexil, EPRI J. Horowitz, EPRI (
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APPENDIX IV: FUTURE AGENDA-The Committee agreed to consider the following during the 448th ACRS Meeting. February 5-7, 1997:
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- p aseoy'o ,, UNITED STATES
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'l n NUCLEAR REGULATORY COMMISSION
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o l ADVISORY COMMITTEE ON REACTCR SAFE!UA7.DS WASWNGTON, D. C. 20565 4.... REVISED: January 27, 1998 SCHEDULE AND OUTLINE FOR DISCUSSION 448th ACRS MEETING FEBRUARY 5-7, 1998 THUREDAY. FEBRUARY 5, 1998. CONFERENCE ROOM 2B3. TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND 1) 8:30 - 8:35 Openina Remarks by the ACRS Chairman
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(Open)
1.1) Opening Statement (RLS/JTL)
1.2) Items of current interest (RLS/JTL)
1.3) Priorities for preparation of ACRS reports (RLS/JTL)
2) 8:35 - 10:00 Status of Develonino a Revised Fire Protection Rule (Open) (DAP/AS)
2.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff,
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Nuclear Energy Institute (NEI),
National Fire Protection Association (NFPA), and the Union of Concerned Scientists (UCS)
regarding staff actions related to the development of a revised Fire Protection Rul :00 - 10:15 *** BREAK ***
3) 10:15 - 12:00 Noon AP600 Test and Analyses Procram and Standard Safety Analysis ReDort (Open/ Closed) (JJB/TSK/NFD/PAB)
3.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff and Westinghouse regarding the Test and Analysis Program and Standard Safety Analysis Report Chapters 1, 4, 5, 7, 8, 11, 13, 17 and 18 associated with the AP600 design.
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, Portions of this session may be closed to discuss Westinghouse Proprietary Information related to the test and analysis progra :00 - 1:00 *** LUNCH ***
4) 1:00 - 2:00 P.M. Meetino with chairman Jackson (Open) (RLS/MME)
4.1) Remarks by the ACRS Chairma .2) Discussion with Chairman Jackson on items of mutual interest, including:
- NRC Research Progra *
Use of PRA in the Regulatory Decisionmaking Process (CDF as a Safety Goal, Policy Issues, etc.).
- Risk-Informed, Performance-Based Regulatio * Proposed Revisions to 10 CFR 50.5 * Nr.C Strategic and Performance Plannin *
Shutdown and Low-Power Rulemaking and Maintenance Rul '
Timeliness and Utility of ACRS Advice (Comments on ACRS/ACNW Survey).
5) 2:00 - 3:00 P.M. Westinohouse Spent Fuel Rack Criticality Analysis Methodolocy (Open) (TSK/NFD)
5.1) Remarks by the ACRS Chairma i 5.2) Briefing by and discussions with representatives of the NRC staff and Westinghouse regarding
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Westinghouse's spent fuel rack criticality analysis methodolog :00 - 3:15 P.M. *** BREAK ***
6) 3:15 - 5:15 P.M. Proposed Imorovements to the Senior Management Meeting Process (Open)
(JJB/MTM)
6.1) Remarks by the Subcommittee Chairma , .
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6.2) Briefing by and discucsions with representatives of the NRC staff and the Nuclear Energy Institute regarding proposed improvements to the Senior Management Meeting proces Representatives of the nuclear industry will provide their views, as appropriat ) 5:15 - 7:00 Precaration cf ACRS Recorts (Open)
Discussion of proposed ACRS reports on:
7.1) Annual ACRS Report to Congress on the NRC Safety Research Progra (DAP/MME)
7.2) Interim Report on AP600 Design Certification Revie (JJB/TSK/NFD/PAB)
7.3) Senior Management Meeting proces (JJB/MTM)
7.4) Status of Developing a Revised Fire Protection Rul (DAP/AS)
FRIDAY. FEBRUARY 6, 1998. CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE. MARYLAND l
8) 8:30 - 8:35 Openino Remarks by the ACRS Chairman (Open) (RLS/JTL)
8.1) Opening Statement (RLS/JTL)
9) 8:35 - 9:30 Proposed Revision to 10 CFR 50.5 " Chances. Tests and Ereeriments" (Open) (JJB/MTM)
9.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding the proposed revision I to 10 CFR 50.5 ,
10) 9:30 - 10:15 SECY-97-231. Performance-Based Inspection Guidance (Open) (GA/MTM)
10.1) Remarks by the Subcommittee Chairma I i
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10.2) Briefing by end diccussions with
., rcpraccntativas of the NRC staff regarding SECY-97-231, and related matter :15 - 10:30 *** BREAK ***
11) 10:30 - 11:30 Human Performance and Reliability Implementation Plan (Open) (GA/NFD)
11.1) Remarka by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding the Human Performance and Reliability Implementation Plan and related activitie ) 11:30 - 12:00 Noon Future ACRS Activities (Open) (RLS/JTL)
Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for considera-tion by the full Committee during future meeting :00 -
1:00 *** LUNCH ***
13) 1:00 - 3:00 P.M. Draft NUREG-1555. "SRP For Environmental Reviews For Nuclear Power Plants" (Open)
(MHF/DAP/MME)
13.1) Remarks by the Subcommittee Chairma .2) Briefing by and discussions with representatives of the NRC staff regarding draft NUREG-1555 with emphasis on severe accident management design alternative Representatives of the nuclear industry will provide their views, as appropriat :00 - 3:15 P.M. *** BREAK ***
14) 3:15 - 7:00 P.M. Prenaration of ACRS Renorts (Open)
Discussion of proposed ACRS Reports on:
14.1) Annual ACRS Report to Congress on the NRC Safety Research Progra (DAP/MME)
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Certification Revie (JJB/TSK/NFD/PAB)
14.3) Senior Management Meeting Proces (JJB/MTM)
14.4's Status of Developing a Revised Fire Protection Rul (DAP/AS)
14.5) Proposed Revision to 10 CFR 50.59. (JJB/MTM)
14.6) Human Performance and Reliability Implementation Pla (GA/NFD)
14.7) Draft NUREG-1555, "SRP for Environmental Reviews for Nuclear Power Plants."
(MHF/DAP/MME)
14.8) SECY-97-231, Performance Based Inspection Guidanc (GA/MTM)
SATURDAY, FEBRUARY 7, 1998, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH. ROCKVILLE. MARYLAND 15) 8:30 - 9:00 Recort of the Plannine 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 ACR [ Note: A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory Committee, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.]
16) 9:00 - 9:15 Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et al./
JTL, et al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included .
in recent ACRS report l
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, 17) 9:15 - 12:00 Nool: Prenaration of ACRS Reoorts (Open)
Continue discussion of proposed ACRS reports identified under Item 1 :00 - 1:00 *** LUNCH ***
18) 1:00 - 4:00 Prenaration of ACRS Renorts (Open)
(3 : 00-3 :15 BREAK) Continue discussion of proposed ACRS reports identified under Item 1 ) 4:00 - 4:30 Miscellaneous (Open) (RLS/JTL)
The Committee will discuss 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 permi NOTE: o Presentation time should not exceed 50 percent of the total time allocated for a specific item. The rammining 50 percent of the time is reserved for discussion, e Number of copies of the presentation materials to be provided to the ACRS - 3 r
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APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE
[ Note: ~ Some documents listed below may have been provided or prepared for Committee use only. These documents must be reviewed prior to release to the public.)
MEETING HANDOUTS AGENDA DOCUMENTS ITEM N Onenino Remarks by the ACRS Chairman Items of interest, dated December 3-6,1997 -
2 Emeroency Core Canlina Svstem Strainer B!M rmaa i Presentation to the ACRS on the Status of NRC Bulletin 96-03 and the Staff Review of the BWROG's Utility Resolution Guidance Document, dated December 3,1997, presented by Robert Elliott, NRR [Viewgraphs)
3 Assurance of Sufficient Net Positive Sudian Hand for Emeroency Core Coolina and Containment Heat Removal Pumos Presentation to the ACRS on the Status of NPSH lasues, dated December 3,1997, presented by Jack Kudrick, NRR [Viewgraphs)
4' NRC Performance Plan NRC's Planning and Performance Management System, undated, presented by Jesse L. Funches, Chief Financial Officer [Viewgraphs) NRC Planning Framework, undated, presented by James L. Blaha, Office of the Executive Director for Operations [Viewgraphs) Memorandum from James L. Blaha: Analytical Support Team Report - State Programs, dated November 13,1997 [ Handout) U.S. NRC Strategic Plan: Fiscal Year 1997-Fiscal Year 2002, dated September 1997 [ Handout)
8 Prana =ad Revialans to 10 CFR 50.59 (Chanoes. Tests and Exneriments) Proposed Rulemaking on 10 CFR 50.59, dated December 4,1997, presented by ,
Eileen McKenna, NRR [Viewgraphs)
9- Proon=ad Generic Letter on interim Guidance for U_adatino Final Safety Analysis
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l Prposed Generic Letter: Updated Final Safety Analyses Reports, dated December 4,1997, presented by Tom Bergman (Viewgraphs)
1 [ Draft) Relationship of Design Information, Design Bases, Current Licensing Based
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and Commitments, undated [Viewgraph)
11 Prooosed Revision 1 to NUREG-1022. " Event Reoortina Guidelines.10 CFR 50.72 and 50.73 1 NUREG-1022, Revision 1: Event reporting Guidelines,10 CFR 50.72 and 50.73, dated December 4,1997, presented by Dennis Allison, AEOD [Viewgraphs)
14 Prooosed Final SRP Chaoter 19 (General Guidance) and Reaulatorv Guide DG-1061 for Risk-Informed. Performance-Based Reaulation. includina Use of Uncertainty Versus Point Values in the PRA-Related Decisionmakino Process 1 Final Draft Regulatory Guide and Standard Review Plan on Risk-Informed Decision Making for Plant Specific Changes to a Plant's Licensing Basis, dated December 5,1997, presented by Thomas L. King and Mark Cunningham, RES, and Gary Holahan and Gareth Parry, NRR [Viewgraphs) j 15 Ooeratina Events at Oconee Nuclear Power PlanLUnits 1 and 2 1 ACRS Presentation: Oconee, Unit 1: Failure of Emergency Power Electrical Equipment (June 20 and 23,1997),: AIT - Report 50-269,270,287/97-11, dated December 5,1997, presented by Paul Fredrickson, Region ll [Viewgraphs)
16 Caoability and Acolication of the EPRI CHECKWORKS Code (Open/ Closed)
1 Evaluation of Degradation of Carbon Steel Components by Flow Accelerated Corrosion, dated December 1997, prcsonted by K.I. Prczewski, NRR [Viewgraphs)
1 Fow-Accelerated Corrosion (FAC) - History & Currrent Status, dated December 5,1997, presented by Bindi Chexal and Jeff Horowitz, EPRI 17 Future ACRS Activities 1 Future ACRS Activities -448th ACRS Meeting, February 5-7,1998 [ Handout #17-1)
18 Reconciliation of ACRS Comments and Recommendations 1 Reconciliation of ACRS Comments and Recommendations (Handout #18-1)
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Appendix V 3 447th ACRS Meeting -
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21 Recork of the Plannino and Procedures Subcommittee 1 Final Draft Minutes of Planning and Procedures Subcommittee Meeting - December 3,1997 [ Handout #21-1)
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Appendix V 4 447th ACRS Meeting .
MEETING NOTEBQOK CONTENTS IAS DOCUMENTS 2 Emeroency Core Cooling System Strainer Blockage
' Table of Contents . Proposed Schedule Status Report Executive Summary of the Draft Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Bulletin 96-03, BWR Owners Group Topical Report NEDO-32686, " Utility Resolution Guidance for ECCS Suction Strainer Blockage" 3 Anurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumos Table of Contents Project Status Report, dated December 3,1997 Letter to L. J. Callan, EDO, from R. Seale, ACRS, Proposed Final Generic Letter,
" Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps", dated June 17,1997 Letter to R. Seale, ACRS, from L. J. Callan, EDO, Proposed Final Generic Letter,
" Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps"., dated August 15,1997 Memorandum to L. J. Callan, EDO, from J. T. Larkins, ACRS, Proposed Final
- Generic Letter, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," dated September 9,1997 1 NRC Generic Letter 97-04: Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps, dated October 7,1997 5- ACRS Reoort to Conaress on the NRC Safety Research Proaram 1 Table of Contents
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1 Status Report 1 . Staff Requirements Memorandum, dated September 9,1997: SECY-97-149
- Nuclear Safety Research Review Committee (NSRRC)
1 Memorandum from L. Joseph Callan, Executive Director for Operations (EDO) to The Commissioners, . dated April 2,1997: . SECY-97-075; Methodology and Criteria for Evaluating Core Research Capabilitie ' 1 ' Memorandum from L. Joseph Callan, EDO, to The Commissioners, dated July 30,1997: . DSI 22 Implementatio . - Staff Requirements Memorandum, dated September 16,1997: SECY-97-I 167 - DSI 22 Implementation (Role of the Office of Research).
17.' Letter from Robert L. Seale, ACRS Chairman, to Albert Gore, Jr., dated February 21,1997, transmitting the 1996 ACRS Report to Congress on the U.S. Nuclear Regulatory Commission's Safety Research Progra . Viewgraphs from Dr. Dana Powers on the Safety Research Progra Proposad Revisions to 10 CFR 50.59 (Chanaes. Tests and Funeriments)
1 Table of Contents -q 2 Proposed Schedule 2 Project Status Report !
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2 Memorandum from Jack W. Roe, NRR, to John T. Larkins, ACRS, dated November 24,1997, dated December 4,1997: Meeting on 10 CFR 50.59 Rulemaking (predecisional, draft information for internal ACRS use only)
2 Proposed Rule,10 CFR Part 50 (Changes, Tests and Experiments), and ,
(Part 60, 72, and 76), dated November 6,1997 (predecisional, draft !
Information for internal ACRS use only)
2 Letter from, L. Joseph Callan, EDO, to R..L. Seale, Chairman, ACRS, dated November 12,1997: Proposed Changes to 10 CFR 5)0.59 and Proposed Rev.1 to Generic Letter 91-1811
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Appendix V- 6 447th ACRS Meeting
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' 2 Report from R.L. Seale, Chairman, ACRS, to Shirley Ann ' Jackson, Chairman, NRC, dated October 9,1997, ; " Proposed Changes to 10 CFR 50.59 and Proposed Revision 1 to Generic Letter 91-1811 2 Report from R. L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated April 8,1997: Proposed Regulator, Guidance Related to implementation of 10 CFR. 50.59 (Changes, Tests and Experiments)
i 2 Memorandum from John C. Hoyle, SECY, to L. Joseph Callan, EDO, dated -
October 2,1997: Staff. Requirements - SECY-97-205, Integration and Evaluation of Results from Recent Lessons-Learned Reviews 2 Memorandum from John C. Hoyle, SECY to L. Joseph Callan, EDO, dated April 25,1997: Staff Requirements - SECY-97-035 - Proposed Regulatory Guidance Related to implementation of 10 CFR 50.59 (Changes, Tests, and Experiments)
9 Pronosad Generic Letter on Interim Guidance for Uodatina Final Safety Analysis Reports 2 Table of Contents 3 Proposed Schedule 31, Project Status Report 3 NRC Generic Letter 99-XX: Interim Guidance Regarding Updating Final Safety Analysis Reporting in Accordance with 10 CFR 50.71(e), dated November 6,1997 (predecisional, draft information for internal ACRS use only)
3 Memorandum from John C. Hoyle, SECY, to L. Joseph Callan, EDO, dated May 20,1997: Staff Requirements - SECY-97-036 - Millstone Lessons Learned Report, Part 2: Policy issues 3 Memorandum from John C. Hoyle, SECY, to James M. Taylor, EDO, dated September 27, 1997: Staff Requirements - SECY-96-154 - Proposed Revision to NRC Enforcement Guidance for Departures from FSAR in
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Violation of 1.0 CFR 50.59 and for Failures to Update FSAR in Violation of
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Appendix V 7
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447th ACRS Meeting '
3 Memorandum from Egan Wang,-NRR, to Thomas Essig, NRR, ' dated
' November 18,1997: Summary of Meeting Held on October 30,1997, with NEl to Discuss issues Related to Updating FSAR 3 Memorandum from Egan Wang, NRR, to Thomas Essig, NRR, dated November 18,1997: Summary of Meeting Held on October 9,1997, with NEl to Discuss lasues Related to Updating FSAR 10 Meeting with Commissioner Dicus 3 Letter from Robert L. Seale, ACRS Chairman, to Albert Gore, Jr., dated February 21,1997, transmitting the 1996 ACRS Report to Congress on the '
U.S. Nuclear Regulatory Commission's Safety Research Progra . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated September 10,1997: Staff Action Plan to improve the Senior Management Meeting Proces . Memorandum from John T. Larkins, Executive Director, ACRS, to the Commissioners, dated September 11,1997: ACRS Letter on the Senior Management Meeting Process, September 11,199 . Letter from Dr. George Apostolakis, ACRS Member, to John T. Larkins, ,
Executive Director, ACRS, dated September 8.1997: ACRS Letter on the Senior Management Meetin . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated September 10, 1997: Proposed Rulemaking for Shutdown and Fuel Storage Pool Operations at Nuclear Power Plant . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated October 9,1997: Proposed Changes to 10 CFR 50.59 and Proposed Revision 1 to Generic Letter 91-1 . Report from Robert 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 Experiments)
4 Memorandum from John T. Larkins, Executive Director, ACRS, to L. Joseph
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Callan, EDO, dated June 19, 1997: Proposed Regulatory Guidance
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Appendix V 8 447th ACRS Meetirig Related to implementation of 10 CFR 50.59 (Changes, Tests, and Experiments)
4 Report from Thomas S. Kress, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated August 15, 1996: Risk-informed, Performance-Based Regulation and Related Matter . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated March 17,1997: Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation 4 Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated July 14, 1997: Proposed Regulatory Guide and Standard Review Plan Sections for Risk-Informed, Performance-Based inservice inspectio . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated September 19,1997: Site-to-Site Variation in Risk-Based Regulatory Acceptance Criteria for Plant-Specific Application of Safety Goal . Report from Robert L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC, dated April 11,1997: Risk-Based Regulatory Acceptar,ce Criteria for Plant-Specific Application of Safety Goal . Memorandum from Commissioner Nils J. Diaz to Dr. B. John Garrick, Chairman, ACNW, dated October 16, 1997: Health Effects of Low-Level lonizing Radiatio . Report from Paul W. Pomeroy, Chairman, ACNW, to Shirley Ann Jackson, Chairman, NRC, dated July 10, 1996: Health Effects of Low Levels of lonizing Radiatio . Letter from L. Joseph Callan, EDO, to Paul W. Pomeroy, Chairman, ACNW, dated August 9,1996: Health Effects of Low Levels of lonizing Radiatio . Letter from William M. Beckner, Executive Director, National Council on Radiation Protection and Measurements, to U.S. NRC, dated September 5, 1997: Ref: Grant No. NRC 04 95 08 __ _ _ _ _ _ - _ _____-_ -
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Appendix V- _
447th ACRS Meeting 5 NRC Background Paper, undated: Biological Effects of Radiatio . Inside NRC article, undated: Approach to Cleaning Up Nuclear Sites .
Questioned at Seville Meetin Prooosed Revision 1 to NUREG-1022. " Event Reoortina Guidelines.10 CFR 50.72 and 50.73 5 Table of Contents 5 Proposed Agenda 5 Status Report 5 Memorandum from Raymond F. Fraley, Executive Director, ACRS, to James M. Taylor, Executive Director for Operations, NRC, dated December 20, 1991: Proposed Rulemaking to Modify Operating Power Reactor Event Reporting Requirements -10 CFR Past 50.72 and Part 50.73 6 Memorandum from Charles E. Rossi, AEOD, to John T. Larkins, Executive Director ACRS, dated November 7,1997: Forwarding NUREG-1022, Revision 1, Event Reporting Guidelines,10 CFR 50.72 and 50.73 6 Draft Summary of Resolution of Comments on the Second Draft of Revision 1 to NUREG-1022, undated 14 Prooosed Final SRP Chanter 19 (General Guidance) and Reaulatorv Guide DG-
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i 1061 for Risk-Informed. Performance-Based Reaulation. includino Use of Uncertainty Versus Point Values in the PRA-Related Decisionmakina Process 1 6 Table of Contents 6 Proposed Schedule 6 Project Status Report 6 Memorandum from M. Wayne Hodges, RES, and Gary M. Holahan, NRR, to John T. Larkins, Executive Director ACRS, dated November 24,1997:
General Regulatory Guide (DG-1061) and Standard review Plan (SRP-Chapter 19) for Risk-Informed Regulatory Decision Making for Plant Specific CLB Changes [Predecisional, not to be released without prior approval]
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6 Draft Commission Paper from Joseph Callan, EDO, to the Commissioners, dated November 7,1997: Final Regulatory Guidance on -
Risk-Informed Regulation: Policy issues (Predecisional, not to be released '
without prior approval].
6 Staff Requirements Memorandum, dated May 27,1997: Meeting with the ACRS on May 2,199 . Email note from ACRS Member Dana Powers to Reliability and PRA Subcommittee: Comments on DG-1061 and Risk increase Ooerating Events at Oconee Nuclear Power Plant Units 1 and 2 6 Table of Contents 7 Proposed Agenda 7 Status Report 7 Executive Summary of NRC Inspection Report 50-269/97-11,50-270/97-11, 50-287/97-11: Augmented Inspection Team Review of Failure of Safety Related Electrical Equipmen . Executive Summary of NRC inspection Report 50-269/97-07,50-270/97-07, 50-287/97-07: Special Inspection Team Review of Unisolable Reactor Coolant Lea . Executive Surnmary of NRC Inspection Report 50-269/97-06,50-270/97-06, 50-287/97-06: Augmented Inspection Team Review of Degradation of High Pressure Injectio . Executive Summary of NRC Inspection Report 50-269/97-08,50-270/97-08, 50-287/97-08: Special Inspection Tesm Review of Degradation of High Pressure injection Syste Caoability and Anotication of the EPRI CHECKWORKS Code (Open/ Closed)
7 Paper: Chexal-Horewitz Model for Flow Accelerated Corrosion in CHECWORKS B. Chexal/J. Horowitz, Presented at 20th WRSM, Bethesda, Maryland, October 23,1992 L . . .. ... . . . _ . . .
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Appendix V 11 447th ACRS Meeting j
7 Viewgraphs: Evaluation of Degradation of Carbon Steel Components by Flow Accelerated Corrosion", K. Parczewski, NRR, Presentation to ACRS, December 1997 .
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