ML101620521
| ML101620521 | |
| Person / Time | |
|---|---|
| Issue date: | 06/14/2010 |
| From: | Meador S Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML101620521 (25) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 June 14, 2010 MEMORANDUM TO:
ACRS Members FROM:
Sherry Meador
/RA/
Technical Secretary, ACRS
SUBJECT:
CERTIFICATION OF THE MEETING MINUTES FROM THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 554th FULL COMMITTEE MEETING HELD ON JULY 9-11, 2008 IN ROCKVILLE, MARYLAND The minutes of the subject meeting were certified on September 11, 2008 as the official record of the proceedings of that meeting. A copy of the certified minutes is attached.
Attachment:
As stated
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 September 11, 2008 MEMORANDUM TO:
Sherry Meador, Technical Secretary Advisory Committee on Reactor Safeguards FROM:
Cayetano Santos, Chief
/RA/
Reactor Safety Branch Advisory Committee on Reactor Safeguards
SUBJECT:
MINUTES OF THE 554th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS),
July 9-11, 2008 I certify that based on my review of the minutes from the 554th ACRS Full Committee meeting, and to the best of my knowledge and belief, I have observed no substantive errors or omissions in the record of this proceeding subject to the comments noted below.
OFFICE ACRS ACRS:RSB NAME SMeador CSantos/sam DATE 09/11/08 09/11/08 OFFICIAL RECORD COPY
CERTIFIED Date Issued: 09/03/2008 Date Certified: 09/11/2008 TABLE OF CONTENTS MINUTES OF THE 554th ACRS MEETING July 9-11, 2008 I.
Opening Remarks by the ACRS Chairman (Open)
II.
Stretch Power Uprate Application for Millstone Power Station, Unit 3 (Open)
III.
Selected Chapters of the Safety Evaluation Report (SER) Associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application (Open)
IV.
Safeguards and Security Matters (Open)
V.
Status of NRC Activities Associated with Seismic Design Issues at Nuclear Power Plants (Open)
VI.
Containment Overpressure Credit (Open)
V.
Executive Session (Open)
A. Reconciliation of ACRS Comments and Recommendations B. Report on the Meeting of the Planning and Procedures Subcommittee Held on July 8, 2008 C. Future Meeting Agenda APPENDICES I.
Federal Register Notice II.
Meeting Agenda III.
Attendees IV.
Future Agenda and Subcommittee Activities V.
List of Documents Provided to the Committee
During its 554th meeting, July 9-11, 2008, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports, letters, and memoranda REPORTS Reports to Dale E. Klein, Chairman, NRC, from William J. Shack, Chairman, ACRS:
Security and Aircraft Impact Rulemaking for Nuclear Power Plants, dated July 18, 2008 Stretch Power Uprate Application for the Millstone Power Station, Unit 3, dated July 23, 2008 LETTERS Letters to R. W. Borchardt, Executive Director for Operations, NRC, from William J. Shack, Chairman, ACRS:
Interim Letter 4: Chapter 3 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Certification of the ESBWR Design, dated July 21, 2008 MEMORANDA Memoranda to R. W. Borchardt, Executive Director for Operations, NRC, from Frank P.
Gillespie, Executive Director, ACRS:
Draft Regulatory Guides 1149 and 1189, dated July 15, 2008
MINUTES OF THE 554th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS July 9-11, 2008 ROCKVILLE, MARYLAND The 554th meeting of the Advisory Committee on Reactor Safeguards (ACRS) was held in Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on July 9-11, 2008.
Notice of this meeting was published in the Federal Register on June 20, 2008 (72 FR 35172-35173) (Appendix I). The purpose of this meeting was to discuss and take appropriate action on the items listed in the meeting schedule and outline (Appendix II). The meeting was open to public attendance.
A transcript of selected portions of the meeting is available in the NRC's Public Document Room at One White Flint North, Room 1F-19, 11555 Rockville Pike, Rockville, Maryland. Copies of the transcript are available for purchase from Neal R. Gross and Co., Inc., 1323 Rhode Island Avenue, NW, Washington, DC 20005. Transcripts are also available at no cost to download from, or review on, the Internet at http://www.nrc.gov/ACRS/ACNW.
ATTENDEES ACRS Members: Dr. William J. Shack (Chairman), Dr. Mario V. Bonaca (Vice-Chairman),
Dr. Said Abdel-Khalik (Member-at-Large), Dr. George E. Apostolakis, Dr. Sam Armijo, Dr.
Sanjoy Banerjee, Dr. Dennis Bley, Mr. Charles Brown, Dr. Michael Corradini, Mr. Otto L.
Maynard, Dr. Dana A. Powers, Mr. Harold Ray, Dr. Michael Ryan, Mr. John Sieber, and Mr.
John Stetkar. For a list of other attendees, see Appendix III.
I.
Chairman's Report (Open)
[Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.]
Dr. William J. Shack, Committee Chairman, convened the meeting at 8:30 a.m. In his opening remarks he announced that the meeting was being conducted in accordance with the provisions of the Federal Advisory Committee Act. He reviewed the agenda items for discussion and noted that no written comments or requests for time to make oral statements from members of the public had been received. Dr. Shack also noted that a transcript of the open portions of the meeting was being kept and speakers were requested to identify themselves and speak with clarity and volume. Dr. Shack welcomed Mr. Harold Ray and Dr. Michael Ryan as new official members and stated that the Committee was now at its statutory strength of 15 members.
II.
Stretch Power Uprate Application for Millstone Power Station
[Note: Mr. David Bessette was the Designated Federal Official for this portion of the meeting.]
The Committee met with representatives of the NRC staff, Dominion Nuclear Connecticut, Inc.,
and members of the public to discuss Dominions license amendment request to increase the power level of Millstone Unit 3 by 7%. Topics of discussion included fuel system and nuclear design as well as containment and design basis accident analyses. Also discussed were proposed modifications to the plant to support the increased power level such as changes to the core design and disabling automatic control rod withdrawal. The plant safety analyses have been performed in many cases, with more modern methods than when the plant was initially licensed. These analyses show substantial margins to licensing limits for containment design pressure, peak cladding temperature, and departure from nucleate boiling. Mr. Gunderson of the Citizens Against Millstone described a concern that the containment design pressure could be exceeded. The Committee issued a report to the NRC Chairman on this matter dated July 23, 2008, recommending that the application for power uprate at Millstone Unit 3 be approved.
III.
Selected Chapters of the Safety Evaluation Report (SER) Associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application
[Note: Mr. Harold Vandermolen was the Designated Federal Office for this portion of the meeting.]
The Committee met with representatives of the NRC staff and General Electric-Hitachi Nuclear Energy to discuss Chapter 3, Design of Structures, Components, Equipment, and Systems, of the NRC Staffs SER with Open Items related to the ESBWR Design Certification Application.
The discussion focused on classification of Structures, Systems, and Components (SSCs) and the seismic analysis. The SSCs are classified as Safety Class 1, 2, 3, or N depending on whether the SSC is needed to preserve the integrity of the reactor coolant pressure boundary, to shut down the reactor and maintain it in a safe shutdown condition, or to prevent or mitigate potential offsite exposures. Thus, the reactor coolant pressure boundary components and supports are classified as Safety Class 1 whereas nonsafety-related SSCs are classified as Class N. Safety Classes 1 through 3 are very closely related to Quality Groups A through C.
The quality groups are defined in terms of their pressure retaining functions. Pressure retaining components of the reactor coolant pressure boundary are Quality Group A. Finally, there is a seismic classification; all safety related SSCs are placed in Seismic Category I, which means they must remain functional in the event of a design basis earthquake. Nonsafety-related SSCs may be placed in Seismic Category II, which means that they need not remain functional, but must not fail in such a way as to interfere with safety-related SSCs. The remaining nonsafety-related SSCs may be assigned to Seismic Category NS, which means that they must conform to the International Building Code but have no further seismic design requirements. Regarding the seismic design, the Combined Seismic Design Response Spectra (CSDRS) are based on Regulatory Guide 1.60 spectra with the addition of the North Anna site-specific spectra at high frequencies, i.e., the CSDRS is the envelope of the generic and North Anna spectra.
North Anna is representative of most severe rock sites in the eastern US, and thus the CSDRS envelopes most candidate sites with considerable conservatism. The fluids in the reactor building pools are modeled as a mass-spring (sloshing) component and an impulsive (rigid) component. However, for conservatism, the entire water mass of each pool is considered as an impulsive mass in the seismic stick model for predicting overall building response. The sloshing component generally responds at very low frequencies (below 0.5 Hz), where no structural modes of vibration exist. The seismic loads used in the stress analysis of pool structures include both the global loads calculated from the seismic response analysis and local hydrodynamic pressure loading on the pool boundaries.
The Committee issued a letter to the EDO on this matter, dated July 21, 2008, stating that the evolving nature of the ESBWR design makes it difficult to perform an effective review, and that additional information is needed to demonstrate that dynamic forces from seismic events are treated properly in the analyses of heat exchangers immersed in elevated water pools.
IV.
Safeguards and Security Matters
[Note: Ms. Maitri Banerjee was the Designated Federal Official for this portion of the meeting.]
The Committee met with representatives of the NRC staff and a member of the pubic to discuss the draft final rules on security and aircraft impact assessment. Consistent with the Commission direction in the October 31, 2003, Staff Requirements Memorandum, the Committee did not review the elements of the security rule that dealt with physical security. The ACRS review was limited to three parts of the rule: (i) 10 CFR 50.54(hh), Mitigative Strategies and Response Procedures for Potential or Actual Aircraft Attack; (ii) 10 CFR 73.54 Protection of Digital Computer and Communication Systems and Networks; and (iii) 10 CFR 73.58, Safety/Security Interface Requirements for Nuclear Power Reactors. The Committee also reviewed the draft final rule, Consideration of Aircraft Impacts for New Nuclear Power Reactor Designs. The staff discussed the essential elements of each rule, how comments from the public were addressed, and the status of the associated regulatory guidance. Mr. James Riccio of Greenpeace stated that the aircraft impact rule, in his opinion, lacks substantive acceptance criteria, and the requirements that the containment remains intact may not be sufficient.
The Committee issued a report to the NRC Chairman on this matter, dated July 18, 2008, recommending that the draft final rules be approved. The committee agreed with the staff that it is appropriate to treat aircraft attacks as beyond-design-basis events.
V.
Status of NRC Staff Activities Associated with Seismic Design Issues at Nuclear Power Plants
[Note: Mr. Mike Lee was the Designated Federal Official for this portion of the meeting.]
The Committee met with representatives of the NRC staff to discuss the evaluation of earthquakes and how that information will be used to evaluate the safety of nuclear power reactors. The staffs presentation focused on four topics: (1) NRC Seismic Research Program Plan; (2) Generic Safety Issue-199, Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern U.S. on Existing Nuclear Power Plants; (3) Interim Staff Guidance on Seismic Issues Associated with High Frequency (HF) Ground Motion; and (4) the July 2007 Earthquake at the Kashiwazaki-Kariwa (KK) Nuclear Power Plant Site. The NRC staff issued a Seismic Research Program Plan in January 2008 that identifies approximately 40 research projects in the areas of (1) Earth Science and Natural Hazards Research; (2)
Earthquake Engineering Analysis and Earthquake Resistant Design; (3) Cooperation in Ongoing International Research Activities; and (4) Updates to NRC Regulatory Guides. This plan will be implemented over the next three years.
In a 2004 analysis prepared for the NRC, the U.S. Geological Survey reported that the Peak Ground Acceleration (PGA) reference probability for the 29 Central Eastern United States (CEUS) nuclear power reactor sites had increased. As a result, the probability of exceeding the Safe Shutdown Earthquake at some nuclear power plants east of the Mississippi River is now believed to be higher than previously understood. The NRC staff is reviewing documentation to better understand what seismic margin currently exists for the current fleet of nuclear power plants and will then evaluate the new PGA estimates against those margins. The NRC staff recently learned that for some current and future nuclear power plant sites, the site specific ground motion may exceed the ground motion derived from a Lawrence Livermore National Laboratory-or Electric Power Research Institutes-based Probabilistic Seismic Hazard Analysis.
On July 16, 2007, a magnitude 6.8 earthquake occurred about 9 kilometers offshore of the KK nuclear power plant site. PGAs as high as 0.69g were recorded at the bases of some of the reactor buildings, and PGAs at the tops of some building roofs were reported to be twice as high. In the U.S. the largest PGA assumed in reactor designs is 0.3g. The PGA associated with this earthquake was 2 to 2.5 times greater than the acceptable earthquake design for the KK site. Although SSCs important to safety appeared to have performed well, there were several incidents involving noncritical SSCs at the KK site. Inspections for all seven reactor units were completed and no abnormalities were found that could impact the functional or structural integrity of the reactor units. All seven reactor units at the KK site remain off-line while additional site inspections and assessments take place. This was an information briefing. Future subcommittee meetings will get into more details related to seismic issues.
V.
Containment Overpressure Credit
[Note: Mr. Harold Vandermolen was the Designated Federal Official for this portion of the meeting.]
The Committee met with representatives of the NRC staff and the Tennessee Valley Authority (TVA) to discuss technical issues related to crediting of containment overpressure during design basis accidents and special events in support of the extended power uprate for Browns Ferry Units 1, 2, and 3. Representatives of TVA described how credit for containment overpressure is part of the current licensing basis for Appendix R and Loss-of-Coolant-Accident requirements.
Of the two, the Appendix R is the more limiting. During a postulated fire event in two specific locations, if all of the equipment in these locations is rendered inoperable by the fire, there will not be sufficient net positive suction head for the residual heat removal pumps if the containment overpressure resulting from primary system blowdown is not credited. However, TVA claims that this assumption, when taken together with other licensing basis assumptions, is overly conservative. Moreover, based on discussions with the pump vendor, TVA claimed that there is a high likelihood that the pumps would survive the period of low suction head. Several members expressed an interest in the pump data and how they were obtained, since the pump tests were performed when the pumps were new in the 1970s and the pump rotors were replaced in the 1990s. In addition, the fire hazard analysis is a deterministic analysis; the licensee does not have a fire Probabilistic Risk Assessment. Several Members discussed the lack of any means for quantifying the degree of conservatism claimed by TVA. This was an information briefing. No Committee action was necessary.
VI.
Executive Session
[Note: Mr. Frank Gillespie was the Designated Federal Official for this portion of the meeting.]
A.
Reconciliation of ACRS Comments and Recommendations/EDO Commitments The Committee considered the EDOs response of June 20, 2008, to conclusions and recommendations included in the April 30, 2008, ACRS report on the Draft NUREG-1902, Next generation Nuclear Plant Licensing Strategy Report. The Committee decided that it was satisfied with the EDOs response.
B.
Report of the Planning and Procedures Subcommittee Meeting Review of the Member Assignments and Priorities for ACRS Reports and Letters for the July ACRS Meeting Member assignments and priorities for ACRS reports and letters for the July ACRS meeting were discussed. Reports and letters that would benefit from additional consideration at a future ACRS meeting were also discussed.
Anticipated Workload for ACRS Members The anticipated workload for ACRS members through October 2008 was discussed. The objectives were:
Review the reasons for the scheduling of each activity and the expected work product and to make changes, as appropriate Manage the members= workload for these meetings Plan and schedule items for ACRS discussion of topical and emerging issues Staff Requirements Memorandum Resulting from the ACRS Meeting with the Commission In a Staff Requirements Memorandum (SRM) dated June 26, 2008 which resulted from the ACRS meeting with the Commission on June 5, 2008, the Commission stated the following:
At the next Commission briefing on digital I&C, the staff should report the progress made with respect to identifying and analyzing digital I&C failure modes, and discuss the feasibility of applying failure mode analysis to the quantification of risk associated with digital I&C.
The staff should continue working to address Committee concerns, such as SOARCA, digital I&C, and containment overpressurization, and, as necessary and appropriate, provide timely policy decision papers to the Commission to resolve any disagreements.
Direction to the staff regarding SOARCA will be provided in the SRM for SECY-08-0029, State-of-the-Art Reactor Consequence Analysis Reporting Offsite Health Consequences, which is currently before the Commission for voting.
Status of the Quality Assessment of Selected NRC Research Projects The Committee is in the process of assessing the quality of the following NRC research projects:
FRAPCON/FRAPTRAN Code work at the Pacific Northwest National Laboratory and NUREG-6948, Study of Remote Visual Methods to Detect Cracking in Reactor Components The Panel Chairmen provided a brief report on their preliminary findings.
Visit to the Braidwood Nuclear Plant and Meeting with the Region III Administrator Several members of the Committee plan to visit the Braidwood Nuclear Plant on July 23 and meet with the Regional Administrator on July 24, 2008. An itinerary and logistics for the plant visit and meeting with the Regional Administrator were discussed.
Proposed Regulatory Guides, DG-1149, Qualification of Safety Related Motor Control Centers for Nuclear Power Plants DG-1149 is a new Regulatory Guide, which describes a method for qualification of safety-related motor control centers for nuclear power plants. This Guide endorses, with certain exceptions, IEEE Standard 649-2006, Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations. This Standard provides the basic principles, requirements, and methods for qualifying safety-related motor control centers for applications in both harsh and mild environments in nuclear power plants.
The staff plans to issue DG-1149 for public comment and would like to know whether the Committee wants to review this Guide prior to being issued for public comment.
Proposed Revision 2 to Regulatory Guide 1.126, (DG-1189), An Acceptable Model and Related Statistical Methods for Analysis of Fuel Densification This Guide describes an analytical model and related assumptions and procedures for predicting the effects of fuel densification in LWR plants. To meet these objectives, this Guide describes statistical methods related to product sampling that will ensure that this and other approved analytical models will adequately describe the effects of densification for each initial core and reload fuel quantity produced.
Revision 1 to Regulatory Guide 1.126 was issued in 1978. The proposed revision 2 includes more recent information on in-reactor densification. There are no substantive changes to the existing technical guidance.
The staff plans to issue DG-1189 for public comment and would like to know whether the Committee wants to review this Guide prior to being issued for public comment.
Visit to the US-APWR Simulation Facility During its June 2008 meeting, Mitsubishi Heavy Industries, LTD (MHI) provided an overview of the US-Advanced Pressurized Water Reactor (US - APWR) design. During that meeting, MHI invited interested ACRS members to visit a simulation facility related to US-APWR in Pittsburgh, Pennsylvania.
The meeting was adjourned at 1:00 p.m. on July 11, 2008.
29169 Federal Register / Vol. 73, No. 98 / Tuesday, May 20, 2008 / Notices NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Subcommittee Meeting on Planning and Procedures; Notice of Meeting The ACRS Subcommittee on Planning and Procedures will hold a meeting on June 3, 2008, Room T-2B1, 11545 Rockville Pike, Rockville, Maryland.
The entire meeting will be open to public attendance, with the exception of a portion that may be closed pursuant to 5 U.S.C. 552b (c) (2) and (6) to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of the ACRS, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.
The agenda for the subject meeting shall be as follows:
Tuesday, June 3, 2008, 8 a.m. Until 9 a.m.
The Subcommittee will discuss proposed ACRS activities and related matters. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the full Committee.
Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Officer, Mr. Sam Duraiswamy (telephone: 301-415-7364) between 7:30 a.m. and 4 p.m. (ET) five days prior to the meeting, if possible, so that appropriate arrangements can be made.
Electronic recordings will be permitted only during those portions of the meeting that are open to the public.
Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on September 26, 2007 (72 FR 54695).
Further information regarding this meeting can be obtained by contacting the Designated Federal Officer between 7:30 a.m. and 4 p.m. (ET). Persons planning to attend this meeting are urged to contact the above named individual at least two working days prior to the meeting to be advised of any potential changes in the agenda.
Dated: May 13, 2008.
Cayetano Santos, Chief, Reactor Safety Branch.
[FR Doc. E8-11230 Filed 5-19-08; 8:45 am]
BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Meeting Notice In accordance with the purposes of Sections 29 and 182b. of the Atomic Energy Act (42 U.S.C. 2039, 2232b), the Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on June 4-6, 2008, 11545 Rockville Pike, Rockville, Maryland. The date of this meeting was previously published in the Federal Register on Monday, October 22, 2007 (72 FR 59574).
Wednesday, June 4, 2008, Conference Room T-2B3, Two White Flint North, Rockville, Maryland 8:30 a.m.-8:35 a.m.: Opening Remarks by the ACRS Chairman (Open)
The ACRS Chairman will make opening remarks regarding the conduct of the meeting.
8:35 a.m.-10 a.m.: ARTIST Test Program (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the findings from the ARTIST Tests on aerosol retention in the secondary side of a steam generator, and related matters.
10:15 a.m.-11:45 a.m.: Risk Assessment Standardization Project (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the Risk Assessment Standardization Project (RASP) and related matters.
1:45 p.m.-3:45 p.m.: Overview of the U.S. Evolutionary Power Reactor (EPR) Design (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff and AREVA Nuclear Power Inc.,
regarding design features of the EPR and related matters.
4 p.m.-5 p.m.: Status of the Development of Rules and Regulatory Guidance in the areas of Safeguards and Security (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the status of activities associated with the development of rules and regulatory guidance in the safeguards and security areas.
5 p.m.-5:30 p.m.: Status of the Quality Assessment of Selected Research Projects (Open)The Committee will hold discussions with the Chairmen of the ACRS Panels regarding the status of the quality assessment of the research projects on: FRAPCON/FRAPTRAN Code work at the Pacific Northwest National Laboratory; and NUREG-6943, Study of Remote Visual Methods to Detect Cracking in Reactor Components.
5:45 p.m.-7 p.m.: Preparation of ACRS Report (Open)The Committee will prepare and discuss the proposed ACRS report on the ARTIST Test Program.
Thursday, June 5, 2008, Conference Room T-2B3, Two White Flint North, Rockville, Maryland 8:30 a.m.-8:35 a.m.: Opening Remarks by the ACRS Chairman (Open)
The ACRS Chairman will make opening remarks regarding the conduct of the meeting.
8:35 a.m.-9:30 a.m.: Future ACRS Activities/Report of the Planning and Procedures Subcommittee (Open)The Committee will discuss the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future ACRS meetings. It will hear a report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, including anticipated workload and member assignments.
9:30 a.m.-9:45 a.m.: Reconciliation of ACRS Comments and Recommendations (Open)The Committee will discuss the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports and letters.
10 a.m.-11:15 a.m.: Preparation for Meeting with the Commission (Open)The Committee will hold discussions in preparation for their meeting with the Commission on the following topics: Safety Research Program Report, Digital I&C Matters, State-of-the-Art Reactor Consequence Analysis Program, ESBWR Design Certification, and Extended Power Uprates and related Technical Issues.
1:30 p.m.-3:30 p.m.: Meeting with the Commission (Open)The Committee will meet with the Commission to discuss topics noted above.
3:45 p.m.-6 p.m.: Preparation of ACRS Report (Open)The Committee will continue its discussion of a proposed ACRS report on the ARTIST Test Program.
VerDate Aug<31>2005 18:23 May 19, 2008 Jkt 214001 PO 00000 Frm 00063 Fmt 4703 Sfmt 4703 E:\\FR\\FM\\20MYN1.SGM 20MYN1 jlentini on PROD1PC65 with NOTICES
29170 Federal Register / Vol. 73, No. 98 / Tuesday, May 20, 2008 / Notices Friday June 6, 2008, Conference Room T-2B3, Two White Flint North, Rockville, Maryland 8:30 a.m.-8:35 a.m.: Opening Remarks by the ACRS Chairman (Open)
The ACRS Chairman will make opening remarks regarding the conduct of the meeting.
8:35 a.m.-10:30 a.m.: Overview of the US-Advanced Pressurized Water Reactor (US-APWR) Design (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff and Mitsubishi Heavy Industries, Ltd., regarding design features of the US-APWR and related matters.
10:45 a.m.-11:45 a.m.: Status of NRC Staff Activities Associated with the Resolution of Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the status of NRC staff activities associated with the resolution of GSI-191.
1:15 p.m.-1:30 p.m.: Miscellaneous (Open)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 permit.
Procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on September 26, 2007 (72 FR 54695). In accordance with those procedures, oral or written views may be presented by members of the public, including representatives of the nuclear industry.
Electronic recordings will be permitted only during the open portions of the meeting. Persons desiring to make oral statements should notify the Cognizant ACRS staff named below five days before the meeting, if possible, so that appropriate arrangements can be made to allow necessary time during the meeting for such statements. Use of still, motion picture, and television cameras during the meeting may be limited to selected portions of the meeting as determined by the Chairman.
Information regarding the time to be set aside for this purpose may be obtained by contacting the Cognizant ACRS staff prior to the meeting. In view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with the Cognizant ACRS staff if such rescheduling would result in major inconvenience.
Further information regarding topics to be discussed, whether the meeting has been canceled or rescheduled, as well as the Chairmans ruling on requests for the opportunity to present oral statements and the time allotted therefor can be obtained by contacting Mr. Girija S. Shukla, Cognizant ACRS staff (301-415-6855), between 7:30 a.m.
and 4 p.m., (ET). ACRS meeting agenda, meeting transcripts, and letter reports are available through the NRC Public Document Room at pdr@nrc.gov, or by calling the PDR at 1-800-397-4209, or from the Publicly Available Records System (PARS) component of NRCs document system (ADAMS) which is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/
adams.html or http://www.nrc.gov/
reading-rm/doc-collections/ACRS/.
Video teleconferencing service is available for observing open sessions of ACRS meetings. Those wishing to use this service for observing ACRS meetings should contact Mr. Theron Brown, ACRS Audio Visual Technician (301-415-8066), between 7:30 a.m. and 3:45 p.m., (ET), at least 10 days before the meeting to ensure the availability of this service. Individuals or organizations requesting this service will be responsible for telephone line charges and for providing the equipment and facilities that they use to establish the video teleconferencing link. The availability of video teleconferencing services is not guaranteed.
Dated: May 14, 2008.
Andrew L. Bates, Advisory Committee Management Officer.
[FR Doc. E8-11232 Filed 5-19-08; 8:45 am]
BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Sunshine Act Notice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission.
DATES: Weeks of May 19, 26, June 2, 9, 16, 23, 2008.
PLACE: Commissioners Conference Room, 11555 Rockville Pike, Rockville, Maryland.
STATUS: Public and Closed.
Week of May 19, 2008 There are no meetings scheduled for the Week of May 19, 2008.
Week of May 26, 2008Tentative Tuesday, May 27, 2008 1:30 p.m.NRC All Hands Meeting (Public Meeting), Marriott Bethesda North Hotel, 5701 Marinelli Road, Rockville, MD 20852.
Wednesday, May 28, 2008 9:30 a.m.Briefing on Equal Employment Opportunity (EEO) and Workforce Planning (Public Meeting)
(Contact: Kristin Davis, 301-492-2266).
This meeting will be webcast live at the Web addresshttp://www.nrc.gov.
Week of June 2, 2008Tentative Wednesday, June 4, 2008 9 a.m.Briefing on Results of the Agency Action Review Meeting (AARM) (Public Meeting) (Contact:
Shaun Anderson, 301-415-2039).
This meeting will be webcast live at the Web addresshttp://www.nrc.gov.
Thursday, June 5, 2008 1:30 p.m.Meeting with Advisory Committee on Reactor Safeguards (ACRS) (Public Meeting) (Contact:
Tanny Santos, 301-415-7270).
This meeting will be webcast live at the Web addresshttp://www.nrc.gov.
Week of June 9, 2008Tentative There are no meetings scheduled for the Week of June 9, 2008.
Week of June 16, 2008Tentative There are no meetings scheduled for the Week of June 16, 2008.
Week of June 23, 2008Tentative Friday, June 27, 2008 9:30 a.m.Periodic Briefing on New Reactor Issues (Public Meeting)
(Contact: Donna Williams, 301-415-1322).
This meeting will be webcast live at the Web addresshttp://www.nrc.gov.
- The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)301-415-1292.
Contact person for more information:
Michelle Schroll, 301-415-1662.
Additional Information The start time for the Briefing on Results of the Agency Action Review Meeting (AARM) (Public Meeting) on Wednesday, June 4, 2008, has been changed from 9:30 a.m. to 9 a.m.
The NRC Commission Meeting Schedule can be found on the Internet VerDate Aug<31>2005 18:23 May 19, 2008 Jkt 214001 PO 00000 Frm 00064 Fmt 4703 Sfmt 4703 E:\\FR\\FM\\20MYN1.SGM 20MYN1 jlentini on PROD1PC65 with NOTICES
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 Appendix II REVISED June 25, 2008 AGENDA 554th ACRS MEETING JULY 9-11, 2008 WEDNESDAY JULY 9, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND
- 1) 8:30 - 8:35 A.M.
Opening Remarks by the ACRS Chairman (Open) (WJS/CS/SD) 1.1)
Opening statement 1.2)
Items of current interest
- 2) 8:35 - 10:30 A.M.
Stretch Power Uprate Application for Millstone Power Station, 10:40 Unit 3 (Open/Closed) (JDS/DEB) 2.1)
Remarks by the Subcommittee Chairman 2.2)
Briefing by and discussions with representatives of the NRC staff, Dominion Nuclear Connecticut, Inc. and its contractor Westinghouse Electric Company LLC regarding the proposed 7% stretch power uprate for Millstone Power Station, Unit 3.
Members of the public may provide their views, as appropriate.
[NOTE: A portion of this session may be closed to protect information that is proprietary to Dominion Nuclear Connecticut and its contractor pursuant to 5 U.S.C. 552b (c) (4).]
10:30 - 10:45 A.M.
- BREAK ***
10:40 - 10:50
- 3) 10:45 - 2:15 P.M.
Selected Chapters of the Safety Evaluation Report (SER) 10:50 - 2:30 Associated with the Economic Simplified Boiling Water Reactor 12:15 - 1:15 P.M.
(ESBWR) Design Certification Application (Open/Closed) 12:00 - 1:20 (MLC/HJV)
- LUNCH ***
3.1)
Remarks by the Subcommittee Chairman 3.2)
Briefing by and discussions with representatives of the NRC staff and General Electric - Hitachi Nuclear Energy (GEH) regarding selected chapters of the NRC staffs SER With Open Items associated with the ESBWR design certification application.
Members of the public may provide their views, as appropriate.
[NOTE: A portion of this session may be closed to protect information that is proprietary to GEH and its contractors pursuant to 5 U.S.C. 552b (c) (4).]
2:15 - 2:30 P.M.
- BREAK ***
2:30 - 2:40
- 4) 2:30 - 6:00 P.M.
Safeguards and Security Matters (Open/Closed) (MVB/MB)
(Room T-8E8) 4.1)
Remarks by the Subcommittee Chairman 4.2)
Briefing by and discussions with representatives of the 4:30 - 4:45 P.M.
NRC staff regarding the draft final/proposed rules and 5:00 - 5:15 associated regulatory guidance in the area of safeguards
- BREAK***
and security.
[NOTE: A portion of this session will be closed to protect information classified as National Security Information as well as Safeguards Information pursuant to 5 U.S.C. 552b (c)
(1) and (3).]
6:00 - 6:15 P.M.
- BREAK ***
- 5) 6:15 - 7:30 P.M.
Preparation of ACRS Reports (Open/Closed)
Discussion of proposed ACRS reports on:
5.1)
Stretch Power Uprate Application for Millstone Power Station, Unit 3 (Open) (JDS/DEB) 5.2)
Selected Chapters of the SER Associated with the ESBWR Design Certification Application (Open) (MLC/HJV) 5.3)
Safeguards and Security Matters (Closed) (MVB/MB)
THURSDAY JULY 10, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND
- 6) 8:30 - 8:35 A.M.
Opening Remarks by the ACRS Chairman (Open) (WJS/CS/SD)
- 7) 8:35 - 10:30 A.M.
Status of NRC Staff Activities Associated with Seismic Design 11:25 Issues at Nuclear Power Plants (Open) (DAP/MPL) 7.1)
Remarks by the Subcommittee Chairman 7.2)
Briefing by and discussions with representatives of the NRC staff regarding the 2008 seismic research program plan, the interim staff guidance on high frequency ground motion, the July 2007 Japan earthquake, and the status of resolution of Generic Safety Issue-199 (GSI-199).
Representatives of the nuclear industry and members of the public may provide their views, as appropriate.
10:30 - 10:45 A.M.
- BREAK ***
10:40 - 10:50
- 8) 10:45 - 12:30 P.M.
Containment Overpressure Credit (Open/Closed) (MVB/ZA) 11:30 8.1)
Remarks by the Subcommittee Chairman 8.2)
Briefing by and discussions with representatives of the NRC staff and Tennessee Valley Authority (TVA) regarding technical issues related to crediting of containment overpressure during design basis accidents and special events in support of the extended power uprate for Browns Ferry Units 1, 2, and 3.
Members of the public may provide their views, as appropriate.
[NOTE: A portion of this session may be closed to protect information that is proprietary to TVA and/or its contractors pursuant to 5 U.S.C. 552b (c) (4).]
12:30 - 1:30 P.M.
- LUNCH ***
1:15 - 2:15
- 9) 1:30 - 2:15 P.M.
Future ACRS Activities/Report of the Planning and Procedures 2:15 - 3:00 Subcommittee (Open) (WJS/FPG) 9.1)
Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future ACRS meetings.
9.2)
Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, including anticipated workload and member assignments.
- 10) 2:15 - 2:30 P.M.
Reconciliation of ACRS Comments and Recommendations (Open) (WJS/CS/AFD)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports and letters 2:30 - 2:45 P.M.
- BREAK ***
- 11) 2:45 - 7:30 P.M.
Preparation of ACRS Reports (Open/Closed)
Continued discussion of proposed ACRS reports listed under Item 5.
FRIDAY JULY 11, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND
- 12) 8:30 - 1:00 P.M.
Preparation of ACRS Reports (Open/Closed)
Continued discussion of proposed ACRS reports listed under Item 5. There may be a 15 minute break at some point during this activity.
- 13) 1:00 - 1:30 P.M.
Miscellaneous (Open) (WJS/FPG)
Discussion of matters related to the conduct of Committee activities and specific issues that were not completed during previous meetings, as time and availability of information permit.
NOTES:
During the days of the meeting, phone number 301-415-7360 should be used in order to access anyone in the ACRS Office.
Presentation time should not exceed 50 percent of the total time allocated for a given item. The remaining 50 percent of the time is reserved for discussion.
Thirty five (35) hard copies and one (1) electronic copy of the presentation materials should be provided to the ACRS in advance of the briefing.
SIGN-IN SHEETS 554TH ACRS FULL COMMITTEE MEETING July 9, 2008 NAME NRC ORGANIZATION 1
J. Lamb NRR 2
J. Miller NRR 3
S. Ray NRR 4
G. Cranston NRR 5
B. Parks NRR 6
S. Miranda NRR 7
G. Georgiev NRR 8
A. Cubbage NRO 9
M. Caruso NRO 10 P. Shemanski NRO 11 A. Pal NRO 12 D. Jeng NRO 13 R. McNally NRO 14 M. Shams NRO 15 M. Abid NRO 16 J. Huang NRO 17 P. Y Chen NRO 18 T. Spicher NRO 19 M. Chakravorty NRO 20 S. Chakrabarti NRO 21 M. Jardaneh NRO 22 P. Sekerak NRO 23 D. Shum NRO 24 R. Hernandez NRO 25 T. Scarbrough NRO 26 C. Ng NRO 27 A. Hsia NRO 28 C. Patel NRO
SIGN-IN SHEETS 554TH ACRS FULL COMMITTEE MEETING JULY 9, 2010 29 J. Fair NRR 30 B. Thomas NRO 31 P. Patel NRO 32 T. Reed NRR 33 D. Nelson NRR 34 E. Bowman NRR 35 R. Chazell NRO 36 J. Vaughn NSIR 37 B. Schneider NSIR 38 D. Gordon NSIR 39 J. Zimmerman NRR 40 S. Schneider NRR 41 M. Case NRR 42 P. Holahan NSIR 43 G. Tartell NRO 44 S. Ali RES 45 G. Mizuno OGC 46 P. Madden NRO 47 K. Lois NRR
SIGN-IN SHEETS 554TH ACRS FULL COMMITTEE MEETING July 10, 2008 NAME NRC ORGANIZATION 1
G. Bjorkman NMSS 2
M. Stutzke RES 3
M. Chakravorty NRO 4
P. Shemanski NRO 5
A. Murphy RES 6
J. Thompson NRO 7
P. Y. Chen NRO 8
J. Kauffman RES 9
R. Karas NRO 10 C. Munson NRO 11 J. Perez RES 12 M. Shams NRO 13 M. Shah NMSS 14 A. Campbell NMSS 15 H. Graves RES 16 Y. Orechwa NRR 17 L. Killiam RES 18 E. Miller NRO 19 F. Vega NRO 20 V. Graizer NRO 21 E. Brown NRR 22 D. Frumkin NRR 23 J. cusing NRR 24 T. Orf NRR 25 T. Collins NRR 26 K. Martin NRR 27 T. McGinty NRR 28 T. Boyce NRR
July 9, 2008 NAME OUTSIDE ORGANIZATION 1
D. Dominicis Westinghouse 2
T. Williams Westinghouse 3
J. Killimaher Westinghouse 4
B. Gillard Dominion 5
B. Papken Dominion 6
B. Kellerman Westinghouse 7
G. Wang Westinghouse 8
W. Barton Dominion 9
A. Price Dominion 10 J. Craffey Dominion 11 D. Fink Westinghouse 12 R. Patel Dominion 13 A. Gundersen Fairewinds 14 D. Kovack Westinghouse 15 J. Deaver General Electric -Hitachi (GEH) 16 D. Hamon GEH 17 P. Campbell GEH 18 C. Rajendra GEH 19 A. Liu GEH 20 R. Kingston GEH 21 J. Alan Beard GEH 22 A. Pfister WEC 23 P. Hastings Duke Energy 24 J. Weil McGraw Hill 25 J. Weil GEH 26 J. Keys NEI 27 J. Guery Dominion 28 M. Elmeghrihr Dominion 29 M. OConnor Dominion
NAME ORGANIZATION 30 P. Russell Dominion 31 M. Kim Dominion 32 R. Thomas Dominion 33 G. Gardner Dominion 34 A. Gharakhanian Dominion 35 K. Connor Dominion 36 H. Beeman Dominion 37 D. Graves Shaw 38 R. Bain Shaw 39 S. Ferguson Shaw 40 L. Salyards Dominion 41 R. MacManus Dominion 42 H. Onoratd FP&L 43 S. Blodgett Dominion 44 D. Hei Dominion 45 S. Andre Westinghouse 46 N. Florentine Westinghouse 47 B. Eakin Dominion 48 K. Descandes Dominion 49 R. burnham Dominion 50 J. Hantz Westinghouse 51 A. Elms Dominion 52 D. Huegel Westinghouse 53 S. Antoine Westinghouse 54 J. Riccio Greenpeace
July 10, 2008 NAME OUTSIDE ORGANIZATION 1
L. Reiter Consultant 2
R. Barrett AdSTM Contractor 3
W. He AdSTM Contractor 4
M. Rasmussen TVA 5
L. Stafford TVA 6
P. Heck TVA 7
M. Purcell TVA 8
J. Wolcott TVA 9
B. Wetzel TVA 10 C. Carey TVA 11 R. Kalantari EPM 12 B. Morris TVA 13 J. Emens TVA 14 R. Marks TVA 15 A. Heymer NEI 16 G. Li GEH 17 T. Abney GEH 18 J. Stamatakis CNWRA 19 B. MacKissock NMC/Monticello
SIGN-IN SHEETS 554TH ACRS FULL COMMITTEE MEETING June 6, 2008 NAME OUTSIDE ORGANIZATION 1
M. Kanzda MNES 2
M. Onozuica MNES 3
M. Hoshi MHI 4
H. Arikawa MHI 5
H. Teshima MHI 6
M. Takashima MHI 7
H. Hamamoto MHI 8
M. Kikuta MHI 9
Y. Ogata MHI 10 M. Ishida MNES 11 S. Watanabe MNES 12 D. Wood MHI 13 K. Kawai MNES 14 S. Kaawanago MNES 15 T. Hafesa Worley Parsons 16 S. Unkewicg Alion 17 T. Shiraishi MHI 18 K. Yamauchi MHI 19 D. Fischer NUMARK Associates 20 M. Lucas Luminant 21 K. Paulson MNES 22 D. Lange MNES 23 J. Butler NEI
Appendix IV LIST OF DOCUMENTS FROM THE 554th ACRS MEETING JULY 9-11, 2008 Agenda Item 2:
Stretch Power Uprate Application for Millstone Power Station, Unit 3
- 1.
Proposed Schedule
- 2.
Status Reports
- 3.
References Agenda Item 3:
Selected Chapters of the Safety Evaluation Report (SER) Associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application
- 4.
Proposed Schedule
- 5.
Status Report
- 6.
Attachments Agenda Item 4:
Safeguards and Security Matters
- 7.
Table of Contents
- 8.
Proposed Meeting Agenda
- 9.
Status Report Agenda Item 7:
Status of NRC Staff Activities Associated with Seismic Design Issues at Nuclear Power Plants
- 10.
Proposed Schedule
- 11.
Status Report
- 12.
Attachments Agenda Item 8:
Containment Overpressure Credit
- 13.
Agenda
- 14.
Status Report
- 15.
Draft Staff COP Safety Evaluation Input
- 16.
Draft TVA July 10th COP Slides
- 17.
June 12, 2008 TVA Submittal addressing ACRS COP Concerns
- 18.
November 15, 2007 TVA Response to Round 13 RAI on COP Regarding Risk Evaluation
- 19.
February 8, 2008 Staff ACRS Briefing Slides on Background of Containment Overpressure Credit
- 20.
Selected ACRS Commission Slides on Containment Overpressure Credit