ML20140H271

Summary of 434th ACRS Meeting in Rockville,Md on 960912-13 Re Appropriate Action on Items Listed in Attached Agenda. W/Fr Notice,Meeting Schedule & Outline,List of Attendees, Future Agenda & List of Documents Provide to Committee

ML20140H271
Person / Time
Issue date:	01/28/1997
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-3028, NUDOCS 9705130033
Download: ML20140H271 (33)

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k b .h b b b M VUTES OF THE 434TH ACRS MEETING SEPTEMBER 12-13, 1996 EASit I. Chairman's Report (Open) . . . . . . . . . .... 1 II. Adecuacy of the Codes o Analyze Steam Generator Tube Temoerature Distributions Durino Severe Accidents (Open) . . . . . . .... 1 '

III. Indian Point Unit 3 (Open) . . . . . . . . .... 4 i

• IV. Mgtetino with the Director of the NRC Office of Nuclear Reculatory Research (RES) (Open) .... 6 V. Loss of Feedwater Event at Arkansas Nuclear '

One Unit 1 (Open) . . . . . . . . . . . . . .... 8 J

VI. Executive Session (Open) . . . . . . . . . .... 10 A. Reconciliation of ACRS Comments and Recommendations B. Report on the Meeting of the Planning and Proce- -

dures Subcommittee Held on September 11, 1996 l (Open)

C. Future Meeting Agenda i

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9705130033 970128 DESIGNATED ORIGINAL PDR ACRS N"

3028 Certified By. j

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

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. MINUTES OF THE FOUR HUNDRED THIRTY-FOURTH MEETING OF THE

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• ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SEPTEMBER 12-13, 1996 ROCKVILLE, MARYLAND The 434th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on September 12-13, 1996. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. The meeting was open to public attendance. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.

A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W., Washington, D.C. [ Copies of the transcript are available for purchase from Neal R. Gross and Co., Inc., 1323 Rhode Island Avenue, N.W., Washington, D.C. 20005.]

ATTENDEES ACRS Members: Dr. Thomas S. Kress (Chairman), Dr. Robert L. Seale (Vice-Chairman), Dr. George Apostolakis, Mr. John Barton, Dr. Ivan Catton, Dr. Mario H. Fontana, Dr. Don W. Miller, Dr. Dana A.

Powers, and Dr. William J. Shack. [For a list of other attendees, see Appendix III.]

I. CHAIRMAN'S REPORT (Open)

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

Dr. Thomas S. Kress, Committee Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting. He announced that the NRC now has a full complement of five Commissioners and that the Director of the Office of Nuclear Reactor Regulation, Mr.

William Russell, was retiring.

II. Adecuacy of the Codec to Analyze Steam Generator Tube Temoera-ture Distributions Durina Severe Accidents (Open)

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

Introduction Dr. Mario Fontana, ACRS Severe Accidents Subcommittee Chairman, stated that the key issue under discussion concerned the capability of the NRC SCDAP/RELAPS code to calculate steam generator tube tgmperatures during a specific severe accident event. He noted

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434th 3CRS Mocting 2

• September 12-13, 1996 that evaluating the event, which may result in core damage and containment bypass, is very important.  ;

1 Dr. Ivan Catton, ACRS, stated that the NRC code could be used to evaluate the event and was well scaled to the Westinghouse 1/7-scale test data. Dr. Catton stated that determining how to use the code phenomenological behavior results to develop a risk perspec-tive is the next step.

l NRC Staff Presentation i l

Introduction:

Mr. Wayne Hodges, RES, requested that the ACRS issue a report clarifying the June 28, 1996, ACRS report to Chairman Jackson, which stated that the Imc codes are not capable of assessing the specific severe accident event. Mr. Hodges asserted that the staff would explain why the statement was incorrect. He noted that the largest uncertainties associated with steam generator tube failures may come from other parts of the problem not related to thermal hydraulic calculations. Mr. Charles l Tinkler, RES, explained how the SCDAP/RELAPS code supports the steam generator tube integrity rulemaking.

SCDAP/RELAP5 Code Modeling: Mr. Tinkler explained how the observed phenomena from the Westinghouse 1/7-scale tests were used to develop the SCDAP/RELAPS code. He described the code and the modeling assumptions. The Committee and the staff discussed countercurrent hot-leg flows, steam generator inlet-plenum mixing, and upper reactor vessel plenum temperatures. They discussed the adequacy of scaling the Westinghouse test data, the effects of reduced flow through the steam generator tubes, the method for dealing with uncertainties, the deposition of aerosols in the hot leg, and the split fractions used in the nodilization of the steam generator inlet plenum.

Fission Product Decosition: Mr. Tinkler explained how the VICTORIA code was used to confirm that fission product transport and disposition have a minimal effect on steam generator tube tempera-tures. The Committee and the staff discussed the effects of potential localized aerosol deposition, the consequences of using thermal hydraulic code results as inputs to the VICTORIA code, and the need for a test program to validate the VICTORIA code.

Benchmarkina of the Code: Mr. Tinkler explained how Westinghouse 1/7-scale test data and Surry sensitivity analysis results were used to benchmark the SCDAP/RELAP5 code. He noted that the sensitivity analysis results indicate that individual parameters had only a marginal effect on the surge-line and hot-leg failure times. The Committee and the staff discussed the benchmarking uncertainties associated with the test geometry, countercurrent hot-leg flow, steam generator inlet plenum mixing, and the boundary

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434th ACRS Macting 3 September 12-13, 1996 condition temperatures. They also discussed the uncertainties associated with the lack of evaluations, such as convergence testing of COMMIX code results, benchmarking of the SCDAP/RELAPS code to transient test data, and a test data error analysis.

Preliminary Results: Mr. Tinkler provided the preliminary results of the Surry sensitivity analyses. He stated that the analyses indicate that individual independent variables have a minimal  !

impact on the calculated peak average steam generator tube temperatures. Mr. Tinkler concluded that if pressurizer surge-line and hot-leg failures are ignored and a steam generator secondary atmospheric dump valve fails open, steam generator tube rupture is calculated to occur about 20 minutes after the first predicted pressure boundary failure.

The Committee and the staff discussed the differences between the recirculation ratios calculated by the staff and industry, the assumed hot-leg piping circumferential temperatures, and the time constants for temperature increases of the hot gas, hot-leg piping, and steam generator tubes.

IndeDendent Peer Review: Mr. Tinkler noted that three independent peer reviewers commented that the Westinghouse 1/7-scale test data are good and that the SCDAP/RELAP5 code is adequate for calculating natural circulation under severe accident conditions. He presented the peer reviewers' recommendations and the resultant staff actions, which included improving the modeling approach, establish-ing figures of merit, and conducting additional sensitivity analyses. The Committee and the staff discussed the peer reviewer recommendations and how code sensitivity analysis results can be used to quantify uncertainties.

Conclusion:

Mr. Hodges reiterated that the NRC codes were appropriately modeled and that the staff was conducting additional analyses in response to discussions with the ACRS. Mr. Tinkler noted that the staff continues to look at multiple sensitivity studies, ranges of the data, and 95/5% confidence limits. He concluded that the largest influence on the code results was whether or not the secondary side is depressurized.

ACRS Discussion Dr. Novak Zuber, ACRS Consultant, stated that the countercurrent hot-leg flows and inlet-plenum mixing ratios were important parameters that were not calculated by the SCDAP/RELAP5 code nor compared to transient test data. Based on the presented informa-tion, Dr. Zuber stated that he was not convinced that the code was tuned to properly scaled test data, especially for the hot-leg flows. He suggested that the staff develop a road map for

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September 12-13, 1996 1

determining code uncertainties. Dr. Catton presented an approach !

for developing a response surface for a similar scenario.

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1 Dr. Powers suggested that the staff review the safety significance l of a spontaneous steam generator tube rupture based on the expected I deposition of aerosols and particles inside primary and secondary components. Mr. Charles Ader stated that the staff had no plans to reevaluate the spontaneous tube rupture since the consequences of the event were below the safety goals.

Conclu412D The Committee planned to complete a report on this issue during the October 9-12, 1996 ACRS meeting.

III. Indian Point Unit 3 (Open)

[ Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.) l 1

1 Mr. John Barton, Chairman of the Plant Operations Subcommittee, introduced the topic to the Committee. He stated that the ACRS l

normally hears from licensees whose plants have been shut down for 1 more than a year. He noted that the licensee, the New York Power Authority (NYPA), voluntarily shut down Indian Point Unit 3 (IP-3) in February 1993, completed an extensive improvement program and restarted the unit in June 1995, and then had an extended shutdown from September 1995 through April 1996. He also noted that IP-3 l remains on the NRC "Watchlist" of problem plants as a Category 2 l facility (allowed to operate, but weakness warrants increased NRC attention).

Mr. Barton stated that this was an informational briefing regarding l the resolution of issues that led to the initial shutdown of IP-3 and the status of resolution of new issues which emerged after the restart of the plant.

NYPA Presentation Mr. William J. Cahill, the Chief Nuclear Officer for NYPA, intro-duced representatives of the NYPA/IP-3 staff and led the discus-sions for the licensee. Mr. Harry Salmon, Jr., Vice President-Nuclear Operations, provided an overview of the NYPA/IP-3 organiza-tion, a chronology of the events and performance at the site, a summary of the issues related to IP-3 being on the NRC Watchlist, and a review of the corrective action programs, self-assessments and improvements. Mr. Marc Pearson, IP-3 Operations Manager, reviewed the key problem areas following restart and the improve-ments made to strengthen the operations organization. Mr. Robert

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3 434th ACRS Meeting 5 September 12-13, 1996 T

J. Barrett, IP-3 Plant Manager, reviewed the Systematic Assessment '

j of Licensee Performance history, including the specific issues j within each functional area. He summarized five principal i

improvement areas: accountability, materiel condition,. teamwork, conservative operations, and communications. The licensee highlighted the following significant points in their presentation:

l e There was an initial period of licensee denial with regard to  !

declining performance, i i

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. e Past improvement programs were too broad and labor intensive

! (i.e., trending and tracking) to effectively manage improve- '{'

ment. l l

e The plant operations organization was not always fully in charge of plant activities. At times, the maintenance j organization set the priorities and schedule.

e Some performance problems resulted from the plant's " custom-ized" Technical Specifications. The licensee stated that they plan to convert to the improved Standard Technical Specifica-l tions.

4 j e Risk significant activities are now reviewed twice daily by j the Plant Leadership Team.  :

i The key to success is ownership and accountability.

The Committee questioned the effectiveness of past licensee l' improvement programs. Dr. Powers asked if the difference from the earlier improvement programs was a more thorough root cause analysis. The licensee stated that too much emphasis had been 1 placed on trending data and not enough on setting high standards, j holding people accountable, and taking steps to improve weak j management skills. Dr. Apostolakis questioned the licensee's meaning of weak management skills. The licensee stated that there

was a need to improve the competence of staff personnel and

teamwork.

Mr. Barton questioned how the licensee reinforces procedural compliance and what they are doing differently now. The licensee l replied that significant actions have been taken to improve the quality of procedures and to reinforce the importance of properly implementing them. The licensee stated that NYPA had not been effectively using the plant safety review committee and that 4 organizational communications had been generally poor. The licensee also stated that personnel are expected to initiate corrective actions (i.e. , appropriate changes) when problems arise during procedural use. Mr. Barton asked how the licensee assesses i

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4 i the effectiveness of correctiv'e actions. The licensee stated that 1

[ best measure or proof of effectiveness was the absence of similar

events or recurrence.

The Committee discussed the licensee's programs for work control

! and engineering. Mr. Barton asked how the licensee managed their maintenance and engineering backlogs. He asked specific questions-i regarding the data base, prioritization, and estimates of work-off-

rates. The licensee described their programs and methods ' of l controlling work but emphasized the importance of having superior 4

people who make the right decisions. Dr. Seale questioned who in i the licensee's organization had ownership of the plant design 1 bases. The licensee stated that engineering owned the design bases but acknowledged that there had been significant problems in this

- area especially in communication with the plant operations i' organization.

i At the conclusion of the meeting, Mr. Barton asked the licensee

! what' failed (i.e., licensee, industry support organizations, NRC, i

1 etc.). The licensee stated that it was a slow deterioration that went unnoticed for a period of time. The skills, quality of work, and attitudes of people lacked teamwork and openness in communica- 1 tion.

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

IV. Meetina with the Director of the NRC Office of Nuclear Reculatorv Research (RES) (Open)

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

Dr. Thomas Kress, ACRS Chairman, welcomed Dr. David Morrison,  ;

Director of the Office of Nuclear Regulatory Research (RES). Dr.

Kress noted that this briefing was part of the periodic briefings with the NRC Office Directors to discuss items of current interest.

Dr. Morrison briefly discussed the challenges facing RES, such as I budget reduction and maintaining adequate expertise to support the NRC regulatory development. He indicated that the current emphasis is on increased international collaboration.

In response to the Staff Requirements Memorandum (SRM) in which the Commission requested' "that the NSRRC [ Nuclear Safety Research ,

Review Committee] coordinate its activities with those of the ACRS l in areas of joint' interest to ensure that the activities are j

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'4'34th ACRS Meeting 7 September 12-13, 1996 supportive and complementary and not duplicative," Dr. Morrison and Dr. Boulette (NSRRC Chairman) suggested a cooperative effort as follows:

e ACRS and NSRRC Subcommittees hold one joint meeting per year, e ACRS Subcommittee Chairman participate in the discussions of the NSRRC full Committee, e NSRRC Chairman attend one full ACRS Committee meeting per year and highlight NSRRC activities, e ACRS Chairman participate in one NSRRC meeting per year to highlight regulatory issues, and a NSRRC Chairman and Subcommittee Chairmen be responsible for identifying ACRS regulatory concerns / issues for the full NSRRC Committee based upon their review of ACRS letters and partici-pation in joint meetings.

Currently, there is a strategic shift in RES performance to emphasize the following:

e Improve staff capability to perform analytical research previously contracted by establishing uniform standards for proficiency and performance. This requires individual development plans or management-directed training for all staff members. In addition, a seminar program has been initiated to raise awareness of current research and to stimulate innovation.

e Update computing capabilities by providing more powerful work-stations for staff to run analytical codes and to have collaborative computing testbeds. )

1. Integrated international reactor safety research.

The desired goals for research programs in the area of thermal-hydraulics are to maintain a high level of expertise, to maintain experimental f acilities, to conduct experiments for code validation and for better understanding of thermal-hydraulic phenomena, and to develop and maintain in-house capabilities. Containment feedback and kinetic capabilities are required with a thermal-hydraulic code capable of performing accident and transient analysis for operating light water reactors as well as advanced passive reactors. One code is preferable, so all staff members can be knowledgeable users. The CATHARE code will be adopted to check results.

Dr. Morrison outlined some of the new international research initiatives, such as:

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e Nondestructive examination -

develop new examination tech-niques for reactor vessel embrittlement e Probabilistic risk assessment (PRA) - share ra, search results and experiences related to the application of PRA e Steam generator tube integrity - share available data, results and correlation models to improve the assessment of steam generator tube integrity e Thermal-hydraulic code development - improve analysis capabil-ities through consolidation of codes and assessment of new '

code packages e High-burnup fuels - increase cooperative efforts, especially with Japan and France, on behavior of high-burnup fuels in '

reactivity insertion and loss-of-coolant accident conditions.

i Other considerations in setting research priorities are fire methods development, and general regulatory guidance for PRA .

standards. Research also considered the expansion of NUREG-1150 PRAs to include shutdown modes and external events. However, Dr.

Morrison noted that the cost of completion of the NUREG-1150

" matrix" is very high and, based on current information, completing-the " matrix" does not appear to be a cost-effective approach.

Dr. Morrison submitted informational charts that describe the research programs for reactor aging; reactor structural perfor- j mance; PRA; thermal-hydraulics; control, instrumentation, and human l f actors; severe accidents; reactor regulation development; nuclear  !

materials regulation development; radionuclide transport and decommissioning; and information technology, educational grants, and international activities.

I conclusion This briefing was for information only. No Committee action was j required.

V. Loss of Feedwater Event at Arkansas Nuclear One Unit 1 (Open)

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

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. September 12-13, 1996 Introduction Mr. John Barton, Chairman of the Plant Operations Subcommittee, introduced the topic to the Committee. Mr. Barton stated that the purpose of th'.s presentation was to brief the Committee on a loss-of-feedwater event at Arkansas Nuclear One Unit 1 that occurred on May 19, 1996. The primary focus of this briefing was on the Augmented Inspection Team (AIT) findings.

NRR Presentation Mr. Edward Goodwin, Acting Branch Chief, Events Assessment and Generic Communications Branch, NRR, introduced the NRR staff and Mr. Terrence Reis of Region IV. Mr. Reis led the discussions and presented the results of the AIT inspection.

Prior to the initiation of the event, the plant was operating at 100 percent power. On May 19, 1996, a malfunction in the feedwater control circuitry caused a prompt reduction in the speed and corresponding output of main feed pump A, resulting in a reactor trip on high pressure. As designed during the speed reduction, the plant's integrated control system demanded an increase in flow from main feedwater pump A. Feedwater pump A responded to the increased demand by increasing the speed. Six of the eight main steam safety valves on steam header B opened as designed on the reactor trip.

However, one valve failed to close, and the operators, in accor-dance with the procedures, isolated Once-Through Steam Generator (OTSG) B and let it boil dry. This action resulted in the

declaration of an unusual event.

Following the reactor trip, normal feedwater was lost because of further feedwater control deficiencies. Emergency feedwater actuated as designed and provided a decay heat removal path through OTSG A and the condenser. Shortly thereafter, the condenser became unavailable due to an absence of gland sealing steam and decay heat removal proceeded through the atmospheric dump valves.

The AIT found that the most probable cause of the initiating event was the erratic behavior of main feedwater pump A due to a degradation in the 24-volt power supplies to the hydraulic valves that control main feedwater pump speed. The degraded voltage was caused by a short to ground on a digital speed sensor that was common to the power supplies.

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

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. September 12-13, 1996 X. EXECUTIVE SESSION (Open)

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

A. Reconciliation of ACRS Comments and Recommendations

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

The Committee discussed the response from the NRC Executive Director for Operations to ACRS comments and recommendations

, included in recent ACRS reports:

EDO letter dated September 5, 1996, responding to the ACRS report dated August 15, 1996, concerning the Design Changes Proposed by GENE Relating to the Certification of the U.S. Advanced Boiling Water Reactor Design.

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

EDO letter dated September 5, 1996, responding to the ACRS letter dated August 14, 1996, concerning Design Changes Proposed by ASEA Brown Boveri-CE (ABB-CE) Related to the Certification of the System 80+ Design.

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

EDO letter dated September 6, 1996, responding to the

! ACRS letter dated August 15, 1996, concerning Risk-Performance-Based Pegulation and Related Informed, Matters. ,

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

An e-mail response from the NRC staff dated August 26, 1996, responding to ACRS comments and recommendations included in the ACRS report dated June 5, 1996, concern-ing the Implementation of the Regulatory Review Group Recommendations.

The Committee decided that it was satisfied with the staff's response.

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

,434th 3CRS Meeting 11 S,eptemaer 12-13, 1996 The Committee heard a report from Dr. Kress on the Planning and Procedures Subcommittee meeting held on September 11, 1996. The following items were discussed:

1. ETHICS TRAINING The annual ethics training scheduled for the September 1996 ACRS meeting has been postponed to the October 1996 ACRS meeting as requasted by the Office of the General Counsel (OGC). Representatives of OGC and the Division of Contracts intend to discuss the ethics requirements associated with the use of NRC-supplied rental offices and performing contract work by ACRS members. Addition-ally, ACRS members were reminded of potential impact of exceeding the 130-day limit for Special Government Employees (memo from C. Harris to ACRS Members dated August 21, 1996).

RECOMMENDATION The Subcommittee recommended that those members who have questions regarding the use of NRC-supplied rental offices and performing contract work raise them during this session at the October meeting.

2. CONTRACTING BY ACRS MEMBERS The members are aware that they are required to submit financial disclosure forms to OGC annually for review.

These forms go direm2 y to OGC and are not reviewed by the ACRS/ACNW Office.

Based on its review, OGC makes a conflict-of-interest determination, specifying that a member cannot advise the ACRS on matters associated with certain organizations in which the member has a financial interest either through a contract or employment. The usual practice by OGC has been to hold members in conflict with all of the work performed by these organizations and not just the narrow areas in which the member works or has a contract Contract work that a member performs as a salaried employee of an organization such as a university normally only causes a member to be in conflict with the review of the work that was done under that contract and not with all matters directly affecting the company that paid for the work.

The ACRS staff engineers rely not only on the OGC determination but also on updated information provided by

434th ACRS Meeting 12 September 12-13, 1996 1

l the members to determine the conflict-of-interest status for each Subcommittee and full Committee meeting.

Consequently, it is very important for the members to keep the ACRS Office apprised of new contract work which involves mattero being or expected to be discussed by the .

ACRS.

1 EEf'OMMENDATION The Subcommittee recommended that Members keep the ACRS i office apprised of their - tract work. '

3. MEMBERS' ATTENDANCE AT NRC-SPONSORED MEETINGS Currently, the members are not required to fill out the "ACRS Special Travel Endorsement Form" to get the full Committee approval to attend NRC-sponsored meetings. It is recommended that those who plan to attend NRC-spon-sored meetings: l e Fill out the ACRS Special Travel Endorsement Form to keep the Committee informed of the t.opics to be discussed at the meeting and to help the ACRS Office allocate necessary funding. Also, it makes it easier to establish that members were in offi-cial travel status and therefore covered for Work-man's Compensation or Accident benefits.

e Prepare a summary report of the meeting for distri-bution to the other members and ACRS staff, espe-cially for those meetings that involve discussion of matters of interest to the ACRS.

e Ensure that the meeting participants understand that the views, if any, expressed by the member are his own and not those of the ACRS.

RECOMMENDATION The Subcommittee recommended that Committee Members routinely fill out the Special Travel Endorsement Forms and prepare summary reports of meetings where applicable.

The forms will be made available to the Members.

4. INTERNATIONAL

• The German RSK Committee sent 3 fax to suggest that the proposed September meeting with ACRS be post-poned until either November 8-12 or December 12-13.

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,434,th ACRS Meeting 13 September 12-13, 1996 e The Canadian Advisory Committee on Nuclear Safety

' sent a message by e-mail concerning the agenda for  !

the October 9, 1996 meeting with ACRS. This mes-  !

sage included a suggested final agenda and specifi-cally requested that . the meetinc focus more on discussions than on presentations.

RECOMMENDATION '

The Subcommittee recommended that the Committee suggest either November 6 or December 4 as proposed dates for the  ;

meeting with the German RSK.

l The Subcommittee recommended that the attached agenda remain the final agenda for the meeting with the Canadian l Advisory Committee on Nuclear Safety, as it does not J

differ substantially from the agenda approved last month  !

by the committee.

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! 5. ACRS REPORTS I

i The ACRS has recently written two reports (one on fire 4

protection and - the other on severe accident research) which have caused a significant amount of controversy at 's the EDO and Commission level. In one case, the useful- i i ness of work in the area of fire protection performed by

an - ACRS consultant's company was-endorsed without the associated report being reviewed by or made available to j

the Committee. In the second case, a comment was made that the NRC thermal-hydraulic and aerosol codes are not capable of predicting. steam ger. orator tube failure during  !

i severe accidents. This comment was made without prior

discussion with the RES staff. Consequently, the staff  ;

e was not able to provide information to the Committee 1

! regarding the capability of the NRC codes.

The fire protection report was eventually provided to the NRC staff by the consultant's employer and returned by the staff with a determination that it was not useful for the staff's purposes. The Committee's statements on the capability of NRC codes will be reconsidered at the  !

September ACRS meeting in light of additional information to be provided by the NRC staff. Dr. Catton provided a report including an analysis of the issues to be dis-cussed at the September meeting.

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1. RECOMMENDATION i

The Subcommittee recommended that the Committee address 3

this issue during a review of its letter-writing process j at the October retreat.

6) RETREAT i The ACRS retreat is scheduled to be held at the Royal

Sonesta Hotel, 5 Cambridge Parkway, Cambridge, Massachu-setts,~on October-17-18, 1996. Reservations have been made-for the nights of October 16 and 17 at the above l

. hotel. .Dr. Seale is preparing the agenda for this '

!. retreat.

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7) COORDINATION WITH THE NSRRC i

ACRS management has been working to improve communicc-jl tions between the ACRS and the NSRRC (included in Amrt handouts). The Commission ~ has since issued an SRM  ;

requesting that the NSRRC coordinate its activities with i

those of the ACRS. Coordination between ACRS and NSRRC would be an appropriate subject for discussion with Dr.

Morrison at the September meeting.

RECOMMENDATION The Subcommittee recommended that the Committee discuss -

this subject with Dr. Morrison at the-September meeting.

8) MEMBER ISSUES There were no Members' issues and no travel requests.

D. Future Meetino Aaenda l

Appendix IV summarizes the proposed items endorsed by the  ;

Committee for the 435th ACRS Meeting, October 9-12, 1996. i The 434th ACRS meeting was adjourned at 3:20 p.m. on Friday, September 13, 1996.

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iAPPEND X .:. M j . n M 81rRI N ( St. No 18E / Wednesday, August 728.T __

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!4 The filing of requests for hearings and pr-ading a petitioner shall file a the above date. Where petitions are filed petitions for issve to intessess ts s' supplement to the petition to intervene during the last to days of the notice discussed below. Ah - - which must include a list of the period. Itla wested that the petitioner By September 27 mntentions which are sought to be promptly so ha the en==i== ion by may Ble a request for a litigated in the matter. Each contention a toll-free telephone call to Western

respect to issuanca of to ' must consist of a specific statement of Union at 1-(a00) 248-510e (in Missouri the subject facility o and the issue oflaw or fact to be raised or 1-(800) 342-6700). De Western Union any person whose int be controverted. In addition, the petitioner operstar should be given Detagram affected by this proceeding and who shall provide a brief explanation of the Identification Number N1023 and the wishes to participate as a pasty in the bases of the contentian and a concise following message addmesed to William proceeding must file a wntten request statament of the alleged Escis or expert H. Bateman, Director, Propet Directorate for a hearing and a petition to intervene. opinion which support the contention IV-2

petitioner's name and telephone Requests for a hearing and a petition for and on which the petitioner intends to number, date petition was mailed, pfant

! leave to intervene shallbe filed in rely in proving the contention at the name, and publication date and page

accordance with theenmmission's* hearing. ne petitioner must also number of this Federal Register notice.

" Rules of Practice for Domestic provide referona to those specific A copy of thepetition should also be Licensing Proceedings" in t o CFR Part sources and documents of which the sent to the Offim of the General i 2. Interested persons should consult a petitioner is aware and on which the Counsel, U.S. Nuclear Regulatory

current copy of to CFR 2.714 which if petitioner intende to rely to establish Commia= ion, Weahington, DC 20555-available at the Commission's Public those facts or expert opinion. Petitioner 0001, and to M. H. Phillips Jr., Esq.,

l Winston & Strewn,1400 L Street NW.,

4 Docuroent Room. the Gelman Building, must provide sufficient information to

! 2120 L Street, NW., Washington, DC, show that a genuine dispute exists with WaaMngton. DC 20005-3512, attorney I

and at the local public document room the applicant on a materialissue of law for the licensee i located at the Richland Public Library. or act. Contentions shall be limited to Nontimely filings of petitions for 955 Northgate Street Richland, matters within the scope of the leave to intervene, amended petitions,

! Washington 99352. If a request for a amendment under consideration. The supplemental tions and/or uests

! hearing or petition for leave to intervene contention must be one which,if for hearing w ot be entert

is filed by the above date, the proven, would entitle the petitioner to absent a determination by the Commission or an Atomic Safety and j relief. A petitioner who fails to flIe such Commission, the presiding oMeer @

Licensing Board, designated by the a cupplement which satisfies these presiding Atomic Safety and Licensing Commission or by the Chairman of the tsquirements with respect to at least one Board that the petition and/or request Atomic Safety and Licensing Board contention will not be pennitted to shoulo be grantedbased upon a Panel, will rule on the request and/or participate as a party. balagc,ing of the factors specified in to petition; and the Secretary or the Those permitted to intervene become CFR 2.714(a)(1) (IHv) and 2.714tdl.

designated Atomic Safety and Licensing parties to the proceeding, subject to any For further details with respect to this Board will issue a notice of hearing or limitations in the order granting leave to intervene, and have the opportunity to action, see the ap cation for an appropriate order. amendment August 9,1996, As required by 10 CFR 2.714. a participate fully in the conduct of the which is available for public inspection petition for leave to intervene shall set hearing, including the opportunity to at the r%-* s Public Document forth with particularity the interest of present evidence and cross-eramine Room, the Gelman Building,2120 L the petitioner in the proceeding. and witnesses. Street, NW., WMP DC, and at the be affected by the if a hearing is requested, the how that interest mading. The petition local public document room located at results of the procee Commission will make a final the Richland Public Library,955 lain the reasons determination on the issue of no should specifically 71d be permitted significant hazards consideration. he Northgate Street. Richland, Washington why intervention sho 99352.

with particular reference to the final determination will serve to decide following factors:(1) the nature'of the when the hearing is held. Dated at Rockvtlla, Maryland, this 23rd day petitioner's right under the Act to be if the final determination is that the of Agust 1996.

made party to the proceeding:(2) the amendment request involves no . For the Nuclear Regulatory enmmission.

nature and extent of the petitioner's significant hazards consideration, the 'Dmothy G. Cetparu.

property, financial, or other interest in Commission may issue the amendment 3,njor prop,cf Monoger, Proisd Gn ctomte the proceeding; and (3) the poestble and make it immediately effective, N-2, Dvwon ofReactor Projects-M/N.

effect of any order mesy be. notwithstanding the request for a Office ofNuclear Asoctor Regulacon.

entered in the p on the bearing Any hearing held would take (FR Dcc. 96-21938 Flied 6-27-96: 8.45 ami petitioner's interest. should place after issuance of the amendment. a. i a coa, resw also identify the s ' alof the tf the final determination is that the subject matter of as to amendment request involves a which petitioner wis ed to intervens. signiEcant hazards consideration, an Advloory Committee on Reactor Any person who has filed a petition for hearing held would take place before Safeguards; Meeting Not6ce leave to intervene or who has been the issuance of any amendment.

admitted as a party may amend the A request for a haanng or a petition in accordance with the purposes,of petition without requesting leave of the for leave to intervene must be filed with Sections 29 and 182b. of the Atomic the Secretary of the Commission, U.S. Energy Act (42 U.S.C. 2039,2232b). the Board up to 15 days prior to the first preheanng conference scheduled in the Nuclear Regulatory Commission, Advisory r%nmittee on Reactor proceeding, but such an amended Washington, DC 20555-o001, Attention: Safeguards will hold a meeting on Docketing and Services Branch, or may September 12-13,1996, in Conference petition must satisfy the specificity be delivered to the Commission's Public Room T-2B3,11545 Rockville Pike.,

requirements descnbed above, Rockville, Maryland. The date of this Not later than 15 days prior to the first Document Room, the Celman Buildin9.

prehearing conference scheduled in the 2120 L Street NW., Washington, DC, eq meeting was previously published in

~

'(> 9P

,. e a -

' ~

44352 Federal Ragleter'/ Vol. Sti No.16e / Wedneed2y, August 28.-1996 / Notices J

he Federal Register an unnamy, Representatives of the NRC staff will members of the Committee,its dovember 27,1995 (60 PR 5a303). participate. consultants, and staff. Persons desiring nuroday, $speember 12,1988 3:00 FX-5:00 PX: Preparation of to make oral statements should notify ACRS Reports (Open)--he r ==tttee Mr. Sam Duraiswamy, Chief. Nuclear a 30 AX-4:45 AX:Opendag will discuse posed ACRS reports on Reactore Branch, at least Sve days Remarks by the ACRS Chairman matters dered during this meeting. before the meeting, if possible, so that (Open)-.no ACRS Chairman will make 5:25 FX-7:00 FX: Strategic appropriate arrangements can be made opening remarks regarding conduct of PJanning (Open)-b Committee will to allow the n-ry time during the the meeting and an====t brie 0y continue its discussion ofitems that are meeting for euch statements. Use of still, items of current interest. of signiacant im to NRC, motion picture, and television cameras During eseelon, the Committee will including rebase of thera==ittee during this meeting may be limited to discuss priorities for y,- ^

• of activities for FY 97, selected perdons of the meeting as ACRS reports. determined by the Oneirman s:45 AX-20:45 AX: A PrWeI' 13' toes of information negereleg b time to be set tJ e Codes as Analyse Steam _ :L .; - #:30 AX-a:35 AX:Openini eside lor this porpose may be obtained Tube Temperatum Distributions During Jteenerks by the ACRS Chairman by aansar+ tag the Qief of the Nucioar Seven Accidents IOpen)-b (Open)-N ACRS Chairman will make Reactore Brand to the muting. In Cosamittee will hear r ^' = by opening maarks mgarding conduct of view of the the ty that the schedule and hold discussions with for ACRS mes ings may be adjusted by representatives of the NRC staff #:35 .-20:30 AX: Meeting with Geanc the Oneirinan as -ry to facilitate regarding the adequacy of the NRC theNRCOffice of b moduct of b mwnng, penons codes to anal steam generator tube NucJear.ja __ _ y Jtesserch (RKS) planning to attend abould check with temperature butions during severe. (Open)-N Caninittee will hear a the Odef of the Nuclear Ranctors Branch acddent canditions. Presentation and hold discussions with Mr. Dad Marison, RES Disector, if such reacheduling would moult in Representatives of the industry will on items Mmutualintemet including:

,,ga, g,,,,,,,g,,,,,

' participate, as appropriate.

e Overview Mthe NRC mesarch la encordance with Subsection 10(d) 22:00 AX-22:25 AX:flaconcibation Pub.1 92-463,I have determined that it cfACRS Comments and Recommendations (Open)-b P'*E'*"  %, is necoseary to close portions of this meeting noted above to discuss matters r==ittee will diam = responess frosn Acuddm. e NRCNrmalHydraulicCode that relate solely to the internal b NRC Emscutive Director for Personnel rules and practiose of this Operations (EDO) to axnments and e Imerandonalcooperadve monarch d program. Advisory Committee per 5 U.S.C.

r===andations included in recent . RES plans and priorities for 552b(c)(2), and to discuss matters the ACRS reports. N EDO responsee are ding informbdon Wry for b release of which would constitute a expected to be provided in writing to lopment of risk-informed and clearly unwarranted invasion of the ACRS prior to the meeting j,,, ;,,, -- - Sri regulations by Personal privacy per 5 U.S.C. 552b(c)(6). ,

!!:25 AK-22:45 AX:Jtepart of the ^^^ expanding the empe of NUREG-1150 Purther information regarding topics and Procedume Su- .___ - work to include 1svol 3 PRA for to be discussed, whether the mm (Open/ e

)--The n==ettee will shutdown modes of opersdon, Bro, and has been cancelled or roscheduled, e hear a ioport of the Planning and other external events; rationale for these Chairinan's ruhng on requets fw the Procedures Sh=lttee on menare plans and priorities; ongoing and Opportunity to present oral statements rolsted to the conduct of ACRS planned research to do such PRAs for and the time allotted therefor can be business, and organisational and other modes of operation. ahemia=d by -"'+iam Mr. Sasn personnel matters relating to ACRS. Dumiswamy, Chief. Nelaar Reactors A portion of this session may be 20:45 AK-12.co NOON:less of PaedweserEvent of Arkannes NucJeor Branch (telephone 301/415-7364).

, closed to discuss organindonal and One Unit 2 (Open)-m em==ittee will between 7:30 A.M. and 4:15 PK EDT.

personnel matters that relate solely to hear presentedcas by and hold AQtS meeting notions, meeting the internal parecenel rules and discuselons with topresentatives of the transcripts, and letter se are now practions of this Advisory Comunittee, available on FedWorld m the "NRC NRC staff regarding the Radings and and mettere the release of whid would conclusions of the Augmenten MAIN MENU.*' Direct Dial Access constitute a clearly unwarranted taapartian Team, widch i .d i b number to FedWorld is (800) 303-4672:

invasion of pomonal privacy. .

May 19,1996 loss of feedwater event at the local direts dial nusnber is 703-321-22:45 AX-22:25 PX:Phrdasy ACRS Arkansas Nuclear One Unit 1, 3339-Activities (Open)--b em-meen , will _% og the is, .** will Dated: August 12.1996.

discuss r=ca==endations of the participano, as appropriate Planning and Procedures 4=hna==lttee Jehec.morts 2:25 PK-3.00 P.K:Paparation of Acting Advisory casuntrame Management regarding items proposed for ACRS Reports (Open)-N Committee consideration by the full r==8ttee offleer will discuss pmposed ACRS reports on (FR Doc,96-2t939 Filed 8-27-06; a:45 mm) during future meetings. mattere ma id-ed d this meeting 2:15 PM-2:45 PK: Indian Potat Unit Procedures for the uct of and "'*****"*'*

3 (Open)-m r===lttee will hear participation in ACRS meetings were presentations by and hold discussions published in the Federal Register on with representatives of the ladian Point September 27,1995 (60 FR 49925). In Addeory Ceaunfase on Reactor Unit 3 licensee (New York Power accordance with these procadures, oral 9@eementse Moseng on Authority) regarding the resolutian of or written statements may be presented M Maserig g ,,,,g y % .Notee lesues that led to the shutdown of by mesobers of the public, electronic Indian Point Unit 3, and the status of recordings will be permitted only he ACRS Suhm==ittee on Dermal resolution of new issume since b restart during the open portions of the meeting, Hydraulic Phenomena will hold a of the plant in June 1995. and questions may be asked only by meeting on September 16-19,1996,

APPENDIX II

. e s

/p ueg'o, UNITED STATES

'8 't., NUCLEAR REGULATORY COMMISSION y, ,I ADVISORY COMMITTEE oN REACTOR SAFEGUARDS WASHINGTON, D. C. 20656

• ,,,s*

August 22, 1996 SCIEDULE AND OUTLINE FOR DISCUSSION 434th ACRS MEETING 1 SEPTEMBER 12-13, 1996 l TEU N AY. SEPT m ER 12. 1996. CONFu m CE 10C38 2B3. TWO WEITE FLINT NORTE.

ROCEVILLE. MARYLAND

)

^

1) 8:30 -

8:45 A.M. Ooenina Ramarks by the ACRS Chairman (Open) 1.1) Opening Statement (TSK/SD) 1.2) Items of Current Interest l (TSK/JTL/SD) i

. 1.3) Priorities for Preparation of ACRS j Reports (TSK/SD) l 12:.29 '

2) 8:45 -

1CT45 A.M. Adecuacy of the Codes to Analyze Steam Gen- l erator Tube Temoerature Distributions Durina l Severe Accidents (Open) (MHF/NFD) l 2.1) Remarks by the Subcommittee Chairman 2.2) Briefing by and discussions with representatives of the NRC staff regarding the adequacy of the NRC l

codes to analyze steam generator tube i temperature distributions during l severe-accident conditions. 1 Representatives of the industry will )

participate, as apprcpriate.

10.*45*

N 10: Nv - 14740A.M. BREAK

( See m n page)

3) 14-e40 - 11 45 AxM. Reconciliation of ACRS Comments and 4 3:95 g;yo pg Recommendations (Open) (TSK, et al./SD, dt al.)

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

4) lic&5 -

M Add. ReDort of the Plannina and Procedures 4:or 9; ,$g p, g Subcommittee (Open/ Closed) (TSK/JTL)

Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, and organizational and personnel matters relating to the ACRS.

7R A ustfi SCb Po E do 's or die HEEbA/$

l l

f u .. Q j

2 l

' [ Note: A portion of this session may  !

, be closed to discuss organizational and k personnel matters that relate solely to 1

the internal personnel rules and practices '

of this Advisory Committee, and matters the

- release of which would constitute a clearly l unwarranted invasion of personal privacy.] ,

5) 11:F45 - 12n5 P.M. Future ACRS Activitigg (Open) (TSK/SD) 3:50 - 14 : oy F. h. Discussion of the reconenendations of the .

Planning and Procedures Subconunittee regarding items proposed for consideration by the full Conunittee during future meetings.

12: N- 1:1[ P.M LUNCH n ]

6) 1: N b:45 P.M. indian Point Unit 3 (Open) .(JJB/MIM) 1 6.1) Remarks by the Subcommittee Chairman 6.2) Briefing by and discussions with '

representatives of the Indian Point  !

Unit 3 licensee (New York Power Authority) regarding the resolution of issues that led to the shutdown of Indian Point Unit 3, and the status of resolution of new issues since the restart of the plant in June 1995.

, , Representatives of the NRC staff will participate.

3:3i 4r N 2:45 -

3:90 P.M. BREAK j 4 38 i:30

7) 3M -

5 00 P.M. #renaration of ACRS Reoort (Open) '

Discussion of proposed ACRS report on:

7.1)' Adequacy of NRC Codes to Analyze Steam Generator Tube Temperature Distributions During Severe Accidents (MHF/NFD) 5.00 5.15 l'.M. OREAK I

l

. . G ,

l 3  !

8)

" -' " ^^ " " ^ " - - - ' - " ' -

- (Open) (TS

Discussiop 4f items of si icant

. import 3nde to NRC, in ing rebaselining of th6 Committee ivities for FY 97.

i i

FRIDAY, SEPTEMBER 13, 1996, CONFERENCE ROON 2B3, TWO MEITE FLINT NORTE, ROCKVILLE, NARYLAND

9) 8:30 - 8:35 A.M. Onenina Remarks by the ACRS Chairman (Open)

(TSK/SD) j J

10) 8:35-10:3hA.M. Meetina with the Director of the NRC Office of Nuclear Reculatorv Research (RES) (Open)

(TSK/MME) 10.1) Remarks by the ACRS Chairman 10.2) Briefing by and discussions with Mr.

David Morrison, RES Director, on items of mutual interest including:

e Overview of the NRC research

- program and budget e Research priorities e NRC Thermal Hydraulic Code Activities

• International cooperative research program o RES plans and priorities for providing information necessary for the development of risk-informed and performance-based regulations by expanding the scope of NUREG-1150 work to include Level 3 PRA for shutdown modes of operation, fire, and other external events; rationale for these plans and priorities; ongoing and/or proposed research to do such PRAs for other modes of operation T

U 55 10:30 - 10:45 A.M. BREAK

'l .

t .

4 11)'10:haf-12:hhNOON Loss of Feedwater Event.at Arkanmas Nuclear One Unit 1 (Open) (JJB/AS) 11.1) Remarks by the Subcommittee Chairman 11.2) Briefing by and discussions with representatives of the NRC staff regarding the findings and conclusions of the Augmented Inspection Team which investigated the May 19, 1996 loss of feedwater event at Arkansas Nuclear One Unit 1.

Representatives of the licensee will ,

participate, as appropriate.

If ,

12:0@ - 1:15 P.M. LUNCH 20

12) 1:15 - 3:@0 P.M. Precaration of ACRS Reoort (Open)

Discussion of proposed ACRS report on:

13.1) Adequacy of NRC Codes to Analyze Steam Generator Tube Temperature Distributions During Severe Accidents (MHF/NFD)

EQTE:

• Presentation time should not exceed 50 percent of the total time allocated for a specific item. The remaining 50 percent of the time is, reserved for discussion.

• Number of copies of the presentation materials to be provided

to the ACRS - 35.

s l

l l

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

2.

- e'-'A .

. APPENDIX III: MEETING ATTENDEES i 434TH ACRS MEETING SEPTEMBER 12, 1996 NRC STAFF l i Charles Ader RES R. Barrett AEOD Yi'Chen RES i David T. Dize NRR Joe Donoghue NRR

Bill Gleaves RES

, W. Hodges RES-l .R. Jones NRR Tom King. RES Alan Levin NRR D. Morrison RES Bob Pacca' NRR Tim Reed NRR John N.. Ridgely RES.

Alan Rubin RES Jason Schaperow RES I

i 1

l

. o* s *

' Appendix III 2 434th ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC l t

434TH ACRS MEETING i SEPTET!BER 12, 1996 ,

Darrell Knudson INEL Theresa Sutter Bechtel E. Boulette Boston Edison (NSRRC)

Jim Meyer Scientech Steve Katradis NUS Corp.

William A. Cross STS Clive Caallaway NEI John Kelly NYPA George Groilanski NYPA  :

Robert Barrett NYPA  ;

Marc Pearson NYPA  :

Muzaffer Karasulu NYPA I Robert Deasy NYPA l W. J. Cahill NYPA l William A. Zosiger Harry Salmon NYPA Louie Allenbach Arthur Anderson Drew Valentine Arthur Anderson Ron Lamig Penn State i

I l

I l

I l

4

.,e. 3' a .

Appelldix III 3 i~ 434th ACRS Meeting

l I

l 434TH ACRS MEETING SEPTEMBER 13, 1996 l l

1 l

l NRC STAFE i

I. Ahmed NRR W. Beckner- NRR R. Benedict NRR F. Coffman RES R. Eckenrode NRR F. Eltawila RES E. Goodwin NRR G. Hammer NRR 4

T. Heavey OC W. Hodges RES R. Jones NRR Joel Kramer RES Tom King RES Alan Levin NRR  !

Chu-yu Liang NRR l S. Long NRR.

R. Meyer RES D. Morrison RES t J. Murphy RES Dan O'Neal NRR  ;

Bob Pacca NRR .

J. Rajan NRR Tim Reed NRR ,

Terry Reis RIV

]

John N.Ridgely RES 1 Alan Rubin RES i L. Shea .

RES I Jason Schaperow RES R. Wessman NRR ,

l

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

. e< . >.1

. 1 Appehdix III 4 434th ACRS Meeting i

. ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC i

434TH ACRS MEETING  ;

SEPTEMBER 13, 1996 Lynn Connor Self '

John N. Miller Entergy Operations Marc Smith Entergy Operations '

E. T. Boulette NSRRC j Steve Katradis NUS Corp. ,

i i

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t

- - , . . , n+, , - , , , - . . , ,

. e< . .

J

, APPENDIX IV: FUTURE AGENDA

-The Committee agreed to consider the following during the 435th

ACRS Meeting, October 9-12, 1996

WEDNESDAY, OCTOBER 9, 1996, CONFERENCE ROOM 2B3, TWO WHITE FLIMI NORTH, ROCKVILLE, MARYLAND t 1

1). 8:30 -

8:35 A.M. Openina Remarks by the ACRS Chairman (Open) 4 1.1) Opening Statement (Kress/Larkins/

{ Duraiswamy)

2) 8:35 -

9:00 A.M. Introduetion (Open) (Kr-  ;

ess/Pearson/Larkins)  !

2.1) Introduction of ACRS Members l

) 2.2) Introduction of the Members of the Canadian Advisory Committee on

Nuclear Safety (ACNS)

I 2.3) Discussion of ACRS and ACNS missions, regulatory environments, )

process / )

products, interactions, and l independence i

, 3) 9:00 - 11:30 A.M. Risk-Informed. Performance-Based Recula-tion (Open) (Apostolakis/ Powers / Rogers /

(10:00-10:15 A.M. BREAK) Markley) j 3.1) Prescriptive vs Performance-based

regulation 3.2)

PRA Methods and Completeness l 3.3) De fense - in- Dept h 4

11:30 - 1 00 P.M. LUNCH

4) 1:00 - 2:15 P.M. Plant Acina (Open) (Shack /Biron/Dudley) 4.1) Discussion of issues associated with plant aging e

5) 2:15 - 3:00 P.M. Ooerator Trainina/ Simulator Use (Open)

(Seale/Natalizio/Boehnert) 5.1) Discussion of training of nuclear power plant operators, and use of simulators for training operators and other plant personnel 3:00 - 3:15 P.M. BREAK

I

,.',s .

)

' Appe'ndix IV

. 2 418th ACRS Meeting i

6) 3:15-- 4:15 P.M. Dicital Instrumentation and Control S v s t e m s ( O p e n )

(Miller /Pearson/Markley/Singh) 6.1) Discussion of proposed Standard Review Plan Sections, Branch Technical Positions, and Regul-atory Guides associated with the digital instrumentation and control systems 6.2) Discussion of the issues identified by the National Academy of Sciences / National Research Council (NAS/NRC) in the Phase 1 study, status of the Phase 2 study, and ACNS views on the use of digital instrumentation and control systems.

7) 4:15 - 5:00 P.M. Miscellaneous Matters (Open)

(Kress/Pearson/

Robertson/El-Zeftawy) 7.1) Discussion of miscellaneous issues, including ALARA, cost-benefit considerations, safety culture, etc.

THURSDAY, OCTOBER 10, 1996, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

8) 8:30 - 8:45 A.M. Oneninc Remarks by the ACRS Chairman (Open) l 8.1) Opening Statement (TSK/SD) 8.2) Items of current interest (TSK/JTL/SD) 8.3) Priorities for preparation of ACRS reports (TSK/SD)

9) 8:45 - 10:15 A.M. Status of NRC Stratecic Assessment and Rebaselinina Effort (Open) (TSK/MME) 9.1) Remarks by the ACRS Chairman 9.2) Briefing by and discussions with the Deputy Executive Director for Nuclear Reactor Regulation, Regional Operations and Research, regarding the status of the NRC

.- o' +4 .

. ' Appe$1 dix IV 3 418th ACRS Meeting strategic assessment and rebaselining effort.

10:15 - 10:30 A.M. BREAK

10) 10:30 - 12:00 Noon Dicital Instrumentation and Control Systems (Open) (DWM/MTM) 10.1) Remarks by the Subcommittee

- Chairman 10.2) Briefing by and discussions with representatives of the NRC staff regarding the proposed Standard Review Plan Sections and Branch Technical Positions associated with the digital instrumentation and control systems.

Representatives of the nuclear industry will participate, as appropriate.

12:00 -

1:00 P.M. LUNCH

11) 1:00 - 2:30 P.M. Control Room Back-Panel Fire at Palo Verde Unit 2 (Open) (JJB/AS) 11.1) Remarks by the Subcommittee Chairman 11.2) Briefing by and discussions with representatives of the NRC staff regarding the findings and recommendations resulting from the investigation of the April 4,1996 event that involved two related fires in a back panel of the main control room of Palo Verde Nuclear Power Plant, Unit 2.

Representatives of the licensee will participate, as appropriate.

12) 2:30 - 3:00 P.M. Reoort of the Plannina and Procedures 3 I

Subcommittee (open/ Closed) (TSK/JTL)

Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, and organi-zational and personnel matters relating

i

. e* 's s .

l l ,

!Appehdix IV 4 418th ACRS Meeting to the ACRS.

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

. > a ,0L , +

c 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 NO.

1 Openina Remarks by the ACRS Chairman

1. Items of Interest, ACRS, 434th Meeting, September 12-13, 1996.

2 Adecuacy of the Codes to Analyze Steam Generator Tube Temoerature Distributions Durina Severe Accidents

2. Analysis of Steam Generator Tube Conditions During Severe Accidents, presented by Charles G. Tinkler, RES, dated September 12, 1996 [Viewgraphs]

3. Adequacy of Codes to Analyze Steam Generator Tube Temperature Distributions During Severe Accident, submitted by Noel Dudley, ACRS, [ Handout #2.1]

1 l

3. Reconciliation of ACRS Comments and Recommendations 1

4. Reconciliation of ACRS Comments and Recommendations

[ Handout #3.1]

4. Report of the Plannina and Procedures Subcommittee

5. Final Draft Minutes of Planning and Procedures Subcommittee Meeting - September 11, 1996 [ Handout #4.1]

1

5. Future ACRS Activities  !

6. Future ACRS Activities - 435th ACRS Meeting, October 10-12, 1996 [ Handout #5.1]

6. Indian Point Unit 3

7. New York Power Authority, Indian Point 3 Nuclear Plant, presented by William J. Cahill, Jr., Harry Salmon, Jr.,

Robert J. Barrett, and Marc Pearson, New York Power Authority, dated September 12, 1996 [Viewgraphs]

1 l.

Al /d- .

'/ Appehdix V 2 418th ACRS Meeting 4

i

7. Meetina Reculatory Research-(RES) with " the Director of the NRC Office of Nuclear 3

1, 8. ACRS Briefing: NRC's Research Program, dated September f! .13, 1996, presented by. David L. Morrison, Director, Office of Nuclear Regulatory Research [Viewgraphs)

_8. Loss of Feedwater Event at Arkansas Nuclear One Unit 1 1

9. ACRS Presentation, Arkansas Nuclear One, Unit 1: Reactor j- Trip with Steam Generator _ Dryout, May 19, 1996, presented i i by Terrence Reis, Region IV on September 13, 1996 )

[Viewgraphs) l 2

s.

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. i I-s 4

(

e f,

4 a= i 9

2 l

i I

i a

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

I

. 4)L r% ,

, VAppe'ndix V 3 418th ACRS Meeting MEETING NOTEBOOK CONTENTS IAR DOCUMENTS

2. Adecuacy of the Codes to Analyze Steam Generator Tube Temperature Distributions Durina Severe Accidents

1. Table of Contents

2. Agenda

3. Status Report, dated September 12, 1996

3. Report f rom T. S . Kress, Chairman, ACRS, to Shirley A.

Jackson, Chairman, NRC, dated June 28, 1996: Severe Accident Research

4. Letter from James M. Taylor, Executive Director for Operations, NRC, to T.S. Kress, Chairman, ACRS, dated July 26, 1996: Severe Accident Research

5. Article from Inside NRC, August 19, 1996: NRC Rechecking l Code Used to Justify Operation with Cracked SG Tubes.

6. Indian Point Unit 3

8. Table of Contents

9. Proposed Schedule

10. Status Report

11. Letter from Thomas T. Martin, Regional Administrator, NRC Region 1, to Mr. William J. Cahill, Jr., dated June 19, 1995: Restart of the Indian Point 3 Nuclear Power Plant (Modification of CAL-1-93-009) and two attachments.

10. Meetina with the Director of the NRC Office of Nuclear Reculatory Research (RES)

12. Table of Contents

13. Tentative Agenda, dated September 13, 1996

14. Status Report

15. Memorandum from John T. Larkins, Executive Dircetor, ACRS, to David L. Morrison, Director, Office of Nuclear Regulatory Research: ACRS Meeting with the Director of the NRC Office of Nuclear Regulatory Research, September 13, 1996, Rockville, Maryland

11. Loss of Feedwater Event at Arkansas Nuclear One Unit 1

16. Table of Contents

17. Proposed Schedule

18. Status Report, dated September 13, 1996