ML101660712

Meeting Minutes of the 555th ACRS Meeting, September 4-6, 2010

ML101660712
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Issue date:	06/15/2010
From:	Meador S Advisory Committee on Reactor Safeguards
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UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 June 15, 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 555th FULL COMMITTEE MEETING HELD ON SEPTEMBER 4-6, 2008 IN ROCKVILLE, MARYLAND The minutes of the subject meeting were certified on June 19, 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 June 19, 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 552nd MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS),

May 8-10, 2008 I certify that based on my review of the minutes from the 552nd 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 06/ 19 /08 06/ 19 /08 OFFICIAL RECORD COPY

CERTIFIED Date Issued: June 11, 2008 Date Certified: June 19, 2008 TABLE OF CONTENTS MINUTES OF THE 555th ACRS MEETING September 4-6, 2008 I.

Opening Remarks by the ACRS Chairman II.

(Open)

License Renewal Application and Final SER for the Wolf Creek Generating Station, Unit 1 III.

(Open)

Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of (Open)

Safety-Related Cables and Field Splices for Nuclear Power Plants IV.

TRACE Computer Code Peer Review V.

(Open)

Anticipated Advanced Reactor Research Needs VI.

(Open)

Quality Assessment of Selected Research Projects VII.

(Open)

Subcommittee Reports VIII.

(Open)

Executive Session A. Reconciliation of ACRS Comments and Recommendations (Open)

B. Report on the Meeting of the Planning and Procedures Subcommittee Held on September 3, 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 555th meeting, September 4-6, 2008, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memoranda:

REPORTS Reports to Dale E. Klein, Chairman, NRC, from William J. Shack, Chairman, ACRS:

Development of the TRACE Thermal-Hydraulic System Analysis Code, dated September 24, 2008 Report on the Safety Aspects of the License Renewal Application for the Wolf Creek Generating Station, Unit 1, dated September 17, 2008 MEMORANDA Memoranda to R. W. Borchardt, Executive Director for Operations, NRC, from Edwin M.

Hackett, Executive Director, ACRS:

Draft Final Revision to Regulatory Guides 10.7, 10.8, and 10.9, dated September 9, 2008 Draft Regulatory Guides DG-1205, DG-1187, DG-1197, DG-1196, DG-3031, DG-0020, DG-5026, DG-1141, DG-3035, DG-5027, and DG-1203, dated September 9, 2008 Proposed Interim Staff Guidance (ISG) DC/COL-ISG-06, dated September 9, 2008 Withdrawal of Regulatory Guide (RG) 8.1, Radiation Symbol, dated September 9, 2008

MINUTES OF THE 555th MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS September 4-6, 2008 ROCKVILLE, MARYLAND The 555th meeting of the Advisory Committee on Reactor Safeguards (ACRS) was held in Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on September 4-6, 2008. Notice of this meeting was published in the Federal Register on August 22, 2008 (72 FR 49713-49714) (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 announced that Mr. Charles Brown, Jr. is an official member of the committee with an expertise in digital instrumentation and control.

II.

License Renewal Application and Final SER for the Wolf Creek Generating Station, Unit 1

[Note: Peter Wen was the Designated Federal Official for this portion of the meeting.]

The Committee met with representatives of the Wolf Creek Nuclear Operating Corporation (WCNOC) (the applicant) and the NRC staff to discuss the license renewal application (LRA) for the Wolf Creek Generating Station (WCGS) and the associated NRC staffs final Safety Evaluation Report (SER). The operating license for WCGS expires on March 11, 2025. The applicant has requested approval for continued operation for a period of 20 years beyond the current license expiration date. The applicant discussed the resolution of the five open items, of which, two items were related to scoping boundary of station blackout (SBO) recovery paths and the remaining three were related to metal fatigue. For closure of the SBO recovery paths related open items, the applicant submitted an amendment to the LRA by including: (a) a breaker at transmission system voltage on both the East and West switchyard bus and (b) an underground medium voltage switchyard cable. The staff reviewed this amendment and found it to be acceptable. For the metal fatigue issues, the applicant has committed to update the fatigue monitoring program baseline fatigue analyses as follows: (a) for the surge line hot leg nozzle, the applicant will account for the additional insurge and outsurge cycles accumulated in the early years of plant operation, during which thermal cycle counts were not collected in a systematic and rigorous manner, and (b) for the charging nozzles, the applicant will account for differential contribution of fatigue for each category of charging event. Based on the commitments made by the applicant, the staff concludes that the applicant has provided an acceptable basis for managing aging effect of environmentally assisted metal fatigue of surge line hot leg nozzle and charging nozzles in accordance with 10 CFR 54.21(c)(1)(iii).

The staff described its review and inspection of the applicants scoping, screening, and aging management programs; the program implementation at WCGS; and resolution of the open items. The staff concluded that the requirement of 10 CFR 54.29(a) has been met. The Committee issued a report to the NRC Chairman on this matter, dated September 17, 2008.

The Committee concluded that the programs established by the applicant to manage age-related degradation provide reasonable assurance that the WCGS can be operated in accordance with the current licensing basis for the period of extended operation without undue risk to the health and safety of the public. The Committee recommended that the WCNOC application for renewal of the operating license for WCGS should be approved.

III.

Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants

[Note: Mrs. Christina Antonescu was the Designated Federal Official for this portion of the meeting.]

The Committee met with representatives of the NRC staff to discuss Revision 1 of Draft Final Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants. The staff noted that the final Regulatory Guide will be issued as a new regulatory guide bearing the number 1.211.

This Guide endorses IEEE Standard 383-2003, Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations, with some minor clarifications and/or exceptions. This Guide describes a method that the NRC staff considers acceptable for complying with the Commissions regulations for the qualification of safety-related cables and field splices for nuclear power plants. Some Committee members suggested that clarifications be added in the Guide regarding the definition of risk-significant safety-related equipment (e.g.

cable). Also, it should be made clear: that (a) the scope of the Guide is limited to the safety-related cables; (b) the cables under Appendix R Fire Protection Program for Nuclear Power Facilities are not within the scope of this Guide; and (c) that there is a need for testing specialty cables with connectors. In addition, some members noted that the last Regulatory Position in this Guide does not offer any specific condition monitoring techniques to assess physical and operating conditions of the cable. It only mentions that some condition monitoring should be incorporated. The requirement for condition monitoring is being imposed without any condition monitoring techniques being endorsed by RG 1.131, Rev. 1. This introduction of cable monitoring establishes a requirement for testing with no defined test methodology or acceptance criteria. Also, the members expressed concern about the lack of adequate time to review the changes made to this Guide the day before the ACRS meeting.

A representative from the industry focus group on equipment qualification also made oral remarks at the meeting. The nuclear industry generally supports the proposed draft final Regulatory Guide except it opposes the requirements for condition monitoring of safety-related power, control, instrumentation, and control cables.

The Committee recommended that a revised copy of this Guide, concurred in by other Offices, be provided to the Committee for its review in a future ACRS meeting.

IV.

TRACE Computer Code Peer Review

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

The Committee met with representatives of the NRC staff to discuss the development of the TRACE thermal-hydraulic system analysis code and the outcome of the recently completed peer review. The peer reviewers identified no major deficiencies that preclude the use of TRACE for confirmatory analyses of postulated loss-of-coolant accidents (LOCAs) in current light water reactors (LWRs). Several improvements have been recommended by the peer reviewers and the staff has proposed a plan to address them. The Committee agreed with the recommended improvements and endorsed the staffs plan.

The staff noted that TRACE is now being used for performing small-break and large-break LOCA confirmatory analyses for the Browns Ferry Nuclear Plant extended power uprate (EPU).

Plant decks are also being prepared to assist EPU reviews of other BWR designs, as well as Westinghouse, Combustion Engineering, and Babcock & Wilcox PWRs. Analyses of anticipated operational occurrences (AOOs) and chimney instabilities for the Economic Simplified Boiling Water Reactor (ESBWR), and assessments of applicability of TRACE to other new reactor designs are in progress.

The Committee issued a report to the NRC Chairman on this matter, dated September 24, 2008. The Committee concluded that significant progress has been made toward the incorporation of TRACE into the regulatory process. The Committee recommended that further peer review be conducted to evaluate the applicability of TRACE to new LWR designs, as well as for analysis of coupled reactor physics-thermal hydraulics issues related to EPUs and expanded operating domains. The Committee also recommended that the capability to evaluate uncertainties in the TRACE code predictions be incorporated into TRACE. The Committee noted that the continued development of TRACE is necessary to keep pace with the evolving industry capabilities.

V.

Anticipated Advanced Reactor Research Needs

[Note: Maitri Banerjee was the Designated Federal Official for this portion of the meeting.]

The Committee members discussed anticipated research needs in the area of advanced reactors and identified items to be discussed during the January 2009 Future Plant Designs Subcommittee and the February 2009 full Committee meetings. The Future Plant Designs Subcommittee Chair presented a chronology of recent developments in the area of advanced reactors and an outline of what should be addressed at these two meetings. The following subjects received considerable discussion: use of PRA to establish the licensing basis events; radiological consequence and source term research; and safety system performance and qualification. Some specific issues, unique to HTGR, will also be discussed at the above meetings. Following Commission guidance, HTGR is the current focus of the NRC advanced reactor research plan. The Committee plans to review the NRC advanced reactor research plan during its February 2009, meeting.

VI.

Quality Assessment of Selected Research Projects

[Note: Dr. Hossein Nourbakhsh was the Designated Federal Official for this portion of the meeting.]

The Committee discussed the status of the quality assessment of the research projects on:

"Assessment of Predictive Bias and the Influence of Manufacturing, Model, and Power Uncertainties in NRC Fuel Performance Code Predictions," and NUREG/CR - 6943, A Study of Remote Visual Methods to Detect Cracking in Reactor Components. The Committee discussed the results of panel review and the numerical rating scores for these projects.

The Committee plans to complete its report on the quality assessment of the research projects noted above during its October 2-4, 2008, meeting.

VII.

Subcommittee Reports Materials, Metallurgy, and Reactor Fuels Subcommittee Report The Subcommittee on Materials, Metallurgy, and Reactor Fuels met with the NRC staff and representatives from AREVA, Global Nuclear Fuel, Westinghouse, and the Electric Power Research Institute on September 3, 2008, to discuss current fuel designs, new fuel designs, new cladding materials, lead test assembly program post-irradiation examinations, extended burnup experience, recent fuel performance experience, upcoming design and analytical methods.

The Committee recommended that the Subcommittee undertake more detailed reviews of the major topics and issues discussed during the Subcommittee meeting, including:

New Zirconium base alloys for fuel cladding, guide tube, spacer and channel application New UO2 formulations containing solid solution or grain boundary additives Selected topical reports containing significant changes in analytical methods ESBWR Subcommittee Report The ESBWR Subcommittee met with the NRC staff and representatives of General Electric Hitachi Nuclear Energy to discuss the PRA supporting the Safety Evaluation Report with Open Items associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application. The Subcommittee also continued a review of Section 19.2, on severe accident mitigation.

Chapter 19 of the ESBWR Design Control Document is not a complete description of the PRA.

Instead, Chapter 19 presents the results of the PRA. A full description of the PRA was submitted in the form of a topical report, NEDO-33201. Although the Office of New Reactors (NRO) staff has reviewed this document, the review has been done in the context of the overall review of the ESBWR Design Control Document. There is no separate staff-generated safety evaluation for NEDO-33201. Consequently, the Subcommittee opted to interactively discuss four selected accident sequences with the applicants staff and the NRO staff, with the objective of exploring the quality and completeness of the PRA. The Committee plans to discuss Chapters 19 and 22 and issue an interim letter during its meeting on October 2-4, 2008.

VIII.

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 EDO's response of July 8, 2008, to comments and recommendations included in the May 19, 2008, ACRS report concerning the draft NUREG/CR-6962, Approaches for Using Traditional Probabilistic Risk Assessment Methods for Digital Systems. The Committee decided that it was satisfied with the EDO's response.

The Committee considered the August 21, 2008, EDO response to the June 3, 2008, ACRS report on Susquehanna extended power uprate application. The EDO response states that the recommended void fraction uncertainty analyses are being performed.

The Committee lauds the staffs effort to quantify the impact of void fraction uncertainties on the safety analyses. For any future inquiries or concerns on the Susquehanna EPU application, the EDO proposes that the Committee communicate directly with the Division of Safety Systems. Considering the Committees mandate is to provide advice to the Commission as an independent advisory body, the Committee disagrees with the EDOs proposal. The ACRS full Committee and Subcommittee meetings are the appropriate forum for holding technical discussions and communications with specific Divisions and Offices of the NRC, including NRR, and other stakeholders.

The Committee considered the August 27, 2008, EDO response to the July 23, 2008, ACRS report on Millstone Unit 3 stretch power uprate. The Committee decided that it was satisfied with the EDO's response.

The Committee considered the August 15, 2008, EDO response to comments and recommendations included in the July 21, 2008, ACRS interim letter 4 on Chapter 3 of the NRC Staffs SER related to the ESBWR design. 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 September ACRS Meeting Member assignments and priorities for ACRS reports and letters for the September 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 workloads for ACRS members through November 2008 were discussed and 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 Containment Overpressure Credit Issue During the July 2008 meting, the ACRS was briefed by representative of the Tennessee Valley Authority (TVA) regarding the containment overpressure credit issue related to the Browns Ferry Nuclear Plant. During the meeting, members provided feedback on the information presented by TVA. Due to a lack of time, the Committee did not discuss its position on this issue at the July meeting. Consequently, Dr. Bonaca suggested that the Committee discuss this matter during the September meeting and decide on a course of action.

In addition, in the June 26, 2008 Staff Requirements Memorandum (SRM), stemming from the ACRS meeting with the Commission on June 5, 2008, the Commission directed the staff to continue working to address Committee concerns on containment overpressurization and, as necessary and appropriate, provide timely policy decision paper to the Commission to resolve the disagreement. The Committee should discuss this matter and propose a future course of action.

We understand that the NRR staff is preparing White Paper on the Containment Overpressure issue. If it is provided to the ACRS in a timely manner, it will be scheduled for discussion at the October meeting.

Summary Matrix of ACRS Reports and Letters Issued During FY 2008 The ACRS Office should submit to the Commission the annual ACRS Operating Plan and Self-Assessment on October 31, 2008. In accordance with the Commission direction in the August 6, 1999 SRM, a summary matrix of ACRS reports and letters issued during FY-2008 should also be submitted along with the Operating Plan and Self-Assessment. In order to preclude violation of the ACRS Bylaws, the Committee should authorize the ACRS Executive Director and/or his designee to summarize the FY-2008 ACRS reports and letters.

Proposed Regulatory Guides The staff issued the following Draft Regulatory Guides (DGs) for public comment:

Proposed Revision 1 to Regulatory Guide 1.47 (DG-1205),Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems Proposed Revision 1 to Regulatory Guide 1.47 (DG-1205) endorses the Institute of Electrical and Electronics Engineers (IEEE) Standard 603-1991, Criteria for Protection Systems for Nuclear Power Generating Stations, in place of IEEE Standard 279-1971 version. The IEEE Standard 603-1991 is more specific than IEEE Standard 279-1971 regarding bypassed and inoperable status indication.

Proposed Revision 1 of Regulatory Guide 1.69, (DG-1187), Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants Proposed Revision 1 to Regulatory Guide 1.69 (DG-1187) subsumes the provisions of Regulatory Guide 2.1 Shield Test Program for Evaluation of Installed Biological Shielding in Research and Training Reactors, as the staff plans to withdraw Regulatory Guide 2.1.

Proposed Revision 2 of Regulatory Guide 1.90, (DG-1197), Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons Proposed Revision 2 to Regulatory Guide 1.90 (DG-1197) cites the appropriate regulations and incorporates the appropriate level of pre-stress and inspection requirements for a 60-year plant life instead of a 40-year plant life. DG-1197 provides two acceptable alternative methods of inspecting containment structures with grouted tendons: (1) an in-service inspection (ISI) program based on monitoring the pre-stress level by means of instrumentation and (2) an ISI program based on pressure-testing the containment structure.

Proposed Revision 2 of Regulatory Guide 1.107, (DG-1196), Qualification for Cement Grouting for Prestressing Tendons in Containment Structures Proposed Revision 2 to Regulatory Guide 1.107 (DG-1196) cites the appropriate regulations, incorporates the latest technology advances in the American Society of Mechanical Engineers (ASME) code, and identifies an acceptable method to demonstrate that the proposed system (grouting of pre-stressing tendons) will provide a high level of reliability in the design and installation of the system. DG-1196 provides quality standards for using Portland cement grout to protect pre-stressing steel from corrosion.

Proposed Revision 2 of Regulatory Guide 3.52, (DG-3031), Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Processing and Fuel Fabrication Proposed Revision 2 to Regulatory Guide 3.52 (DG-3031) endorses the procedure contained in NUREG-1520, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility. While the regulations provide general information for filing license renewal applications, NUREG-1520 identifies the specific information to be submitted by an applicant and evaluated by the staff. This NUREG provides guidance on the information to be included in licensing applications and establishes a format for presenting the information. Using this standard format helps to ensure uniformity and completeness in the preparation of licensing applications.

Proposed Revision 3 of Regulatory Guide 10.4, (DG-0020), Guide for the Preparation of Applications for Licenses to Process Source Material Proposed Revision 3 to Regulatory Guide 10.4 (DG-0020) endorses the license application and review procedure to process source material as discussed in NUREG-1556, Consolidated Guidance about Material Licenses. While the regulations provide general information for filing license renewal applications, NUREG-1556 identifies the specific information to be submitted by an applicant and evaluated by the staff. This NUREG provides guidance on the information to be included in licensing applications and establishes a format for presenting the information. Using this standard format helps to ensure uniformity and completeness in the preparation of licensing applications.

Proposed new Regulatory Guide DG-5026, Fatigue Management for Nuclear Power Plant Personnel DG-5026 is a proposed new Regulatory Guide developed in support of 10 CFR Part 26. The draft regulatory guide endorses (with modifications) the Nuclear Energy Institute (NEI) document NEI 06-11, Revision E, Managing Personnel Fatigue at Nuclear Power Reactor Sites, dated June 2008.

Proposed Revision 4 to Regulatory Guide 1.105 (DG-1141), Setpoints for Safety-Related Instrumentation, Proposed Revision 4 to Regulatory Guide 1.105 (DG-1141) endorses the American National Standard Institute (ANSI)/ Instrumentation, Systems, and Automation Society (ISA) Standard 67.04.01-2006. This standard incorporates the current industry consensus on instrument setpoints, and the information in the Regulatory Information Summary (RIS) 2006-017, which presents the NRC staff position on the requirements of 10 CFR 50.36, "Technical Specifications, regarding limiting safety system settings during periodic testing and calibration of instrument channels.

Proposed Revision 1 to Regulatory Guide 3.16 (DG-3035), General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants, This proposed revision is a complete re-write that refers to NUREG-1718, Standard Review Plan for the Review of an Application for a Mixed Oxide (MOX) Fuel Fabrication Facility, Chapter 7, Fire Protection, regarding what information an applicant should provide with their license application.

Proposed Revision 1 to Regulatory Guide 5.12 (DG-5027), General Use of Locks in Protection and Control of Facilities and Special Nuclear Materials.

This proposed revision endorses new and revised standards, including several General Services Administration (GSA) Standards such as Federal Specification FF-L-2740A, Locks, Combination, FF-L-2890A, Lock Extension (Pedestrian Door, Deadbolt),and FF-L-2937, Amendment 1, Combination Lock, Mechanical as well as several ANSI and ASTM Standards.

Proposed New Regulatory Guide DG-1203, Containment Performance for Pressure Loads, DG-1203 is a proposed new Regulatory Guide Which describes acceptable methods for demonstrating containment performance in nuclear power plants, in accordance with the regulatory requirements of 10 CFR Part 50, Appendix A, General Design Criteria 16, Containment Design, and 50, Containment Design Basis, and 10 CFR 50.44, Combustible Gas Control for Nuclear Power Reactors.

Proposed Interim Staff Guidance The staff issued proposed Interim Staff Guidance DC/COL-ISG-06, Evaluation and Acceptance Criteria for 10 CFR 20.1406, for public comment.

DC/COL-ISG-06 is a new Interim Staff Guide which describes the evaluation and acceptance criteria that will be used by NRC staff in reaching a reasonable assurance finding that a Design Certification (DC) or Combined License (COL) applicant has demonstrated compliance with the regulatory requirements of 10 CFR Part 20.1406, Minimization of Contamination, in accordance with the guidance provided in Regulatory Guide 4.21, Minimization of Contamination and Waste Generation: Life Cycle Planning.

Withdrawal of Regulatory Guide 8.1, Radiation Symbol The NRC is withdrawing the Regulatory Guide 8.1, issued in February 1973, because it is no longer required. Regulatory Guide 8.1 references 10 CFR 20.203 which has been deleted. It also endorses ANSI Standard N2.1-1969 which was withdrawn in 1999. The Regulatory Guide is no longer required because the current 10 CFR 20.1901, Caution Signs, provides a specific description of the approved trefoil radiation symbol and no additional guidance is required.

Draft Final Regulatory Guides Draft Final Revision 2 to Regulatory Guide 10.7 (DG0017),Guide for the Preparation of Applications for Licenses for Laboratory and industrial Use of Small Quantities of Byproduct Material This Guide provides guidance on the type of information to be submitted to the staff to evaluate an application for a specific license for laboratories and industries to use small quantities of byproduct material. This Guide endorses the methods and procedures for applying for a license for laboratory and industrial use of small quantities of by product material contained in the current version of NUREG-1556, Volume 7, Consolidated Guidance About Materials Licenses:

Program-Specific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope.

Draft Final Revision 3 to Regulatory Guide 10.8 (DG018),Guide for the Preparation of Applications for Medical Use Programs This Guide provides guidance on the type of information to be submitted to the staff for reviewing an application for material use license. This Guide endorses the methods and procedures for medical licensing applications contained in the current revision of NUREG-1556, Volume 9, Consolidated Guidance About Material Licenses: Program - Specific Guidance About Medical Use Licenses.

Draft Final Revision 2 to Regulatory Guide 10.9 (DG019),Guide for the Preparation of Applications for the Use of Self-Contained Dry Source-Storage Gamma Irradiators This guide provides guidance on the type of information to be submitted to the staff for reviewing applications of self-contained dry source-storage gamma irradiators. This Guide endorses the methods and procedures contained in NUREG-1556, Volume 5, Consolidated guidance about materials Licenses: Program-Specific guidance about Self-shielded Irradiator Licenses.

The Committee decided not to review the proposed versions of these Guides and requested an opportunity to review the draft final versions of these guides after reconciliation of public comments. Based on the review of these Guides, which incorporate public comments, Dr. Powers recommended that the Committee not review these Guides.

Informal Meetings with the NRC Staff/Interaction with the Industry Informal meetings are being arranged by the NRC staff through direct contact with the members. This is not a good practice, since it compromises the independence of the ACRS. All meetings should be arranged by the appropriate ACRS staff engineer. In accordance with the Federal Advisory Committee Act, these meetings should be used solely to gather information for use by the Committee in its decisionmaking process. During such meetings:

The members should not make recommendations or provide advice.

The members could provide their views, but it should be stated clearly that those are their personal views and do not necessarily reflect those of the full Committee.

An ACRS staff member should be present at these meetings.

No significant technical issues should be discussed. To the extent feasible, these meetings should be limited to planning purpose.

In addition, members should not contact a licensee or applicant to discuss any Committee proposed position or an individual member view on matters being or expected to be reviewed by the ACRS Committee. The appropriate ACRS staff engineer should be notified, to gather information for use by the Committee in its deliberations.

Meeting With the Commission The ACRS will meet with the Commission on Friday, November 7, 2008. After consulting with the ACRS Chairman, we informed the Office of SECY that there are no significant topics to discuss with the Commission in November and that the Commission consider postponing the meeting to March 2009.

On August 27, 2008, we received an email from SECY stating that the Commission definitely wants to meet with the ACRS in November and some of the topics the Commission would like to discuss include:

Management of the Committee, including strategies for getting qualified candidates for membership and increasing diversity among the membership.

Challenges in the coming year Committee views on power uprates for BWRs The ACRS Chairman feels that the first topic should be discussed during a meeting with individual Commissioners.

The proposed topics for meeting with the Commission are as follows:

1. Overview

• Accomplishments

• Ongoing/Future ACRS Activities, including challenges in the coming year

2.

PWR Sump Performance Issues

3.

Committee views on Power uprates for BWRs

4. TRACE Computer Code Development The Commission has requested to meet with the ACRS twice a year. To support two ACRS meetings with the Commission, the first meeting should be held in March/April and the second in October/November. SECY is seeking the Commissioners views on this proposal.

Quadripartite Working Group Meeting Frances Groupe Permanent chargé de Réacteurs Nucleaires (GPR) will host the second Quadripartite Working Group (WG) meeting in France on October 9-10, 2008 on the general topic of EPR. Drs. Bonaca and Powers, and Mr. Stetkar will be attending the meeting on behalf of ACRS. The proposed agenda, suggested topics for ACRS presentations and available draft presentations were discussed.

ACRS Retreat in 2009 The last ACRS retreat was held on January 26-27, 2006. The Committee should decide whether it would like to hold a retreat in 2009.

Impact of Continuing Resolution on FY2009 ACRS Activities The Agency is preparing to operate under a Continuing Resolution (CR) beginning October 1, 2008, and continuing March 31, 2009. If the CR does remain in effect through FY2009, all NRC Offices have been asked to identify anticipated travel related costs. ACRS travel funds will be allocated bi-weekly and travel authorizations will be approved only a week prior to actual travel start dates.

Members Issue Travel Request Dr. Ryan requests Committee approval and support to attend the NRC staffs Workshop on the Security and Continued Use of Cesium-137 Chloride Sources scheduled for September 29-30, 2008 at the Bethesda North Marriott Hotel.

The meeting was adjourned on Friday, September 5, 2008.

49713 Federal Register / Vol. 73, No. 164 / Friday, August 22, 2008 / Notices NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards 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 September 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).

Thursday, September 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.-10:30 a.m.: License Renewal Application and Final SER for the Wolf Creek Generating Station, Unit 1 (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff and Wolf Creek Nuclear Operating Corporation regarding the license renewal application for the Wolf Creek Generating Station, Unit 1, and the associated NRC staffs final Safety Evaluation Report (SER).

10:45 a.m.-12:15 p.m.: Draft Final Revision 1 to Regulatory Guide 1.131, Quantification of Safety-Related Cables and Field Splices for Nuclear Power Plants (Open)The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the draft final revision 1 to Regulatory Guide 1.131 and the NRC staffs resolution of public comments.

1:15 p.m.-3:15 p.m.: TRACE Computer Code Peer Review (Open)

The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the findings of the Peer-Review Panel for the TRACE computer code and the staffs plans to address the Panels findings.

3:30 p.m.-4:30 p.m.: Anticipated Advanced Reactor Research Needs (Open)The Committee will discuss the anticipated advanced reactor research needs and related matters.

4:30 p.m.-7 p.m.: Preparation of ACRS Reports (Open)The Committee will discuss proposed ACRS reports on matters discussed during this meeting.

Friday, September 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.-10 a.m.: Quality Assessment of Selected Research Projects (Open)The Committee will hear a report by and hold discussions with the ACRS Panels which performed the quality assessment of the NRC research projects on: FRAPCON/

FRAPTRAN Code work at the Pacific Northwest National Laboratory (PNNL),

and NUREG/CR-6943, A Study of Remote Visual Methods to Detect Cracking in Reactor Components.

10:15 a.m.-11:15 a.m.: Future Activities/Report of the Planning and Procedures Subcommittee (Open/

Closed)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 and matters related to the conduct of ACRS business, including anticipated workload and member assignments.

11:15 a.m.-11:30 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.

2 p.m.-7 p.m.: Preparation of ACRS Reports (Open)The Committee will discuss proposed ACRS reports.

Saturday, September 6, 2008, Conference Room T-2b3, Two White Flint North, Rockville, Maryland 8:30 a.m.-12 p.m.: Preparation of ACRS Reports (Open)The Committee will continue its discussion of proposed ACRS reports.

12 p.m.-12:30 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.

In accordance with Subsection 10(d)

Public Law 92-463, I have determined that it may be necessary to close portions of this meeting noted above 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 pursuant to 5 U.S.C. 552b(c)(2) and (6).

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 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 VerDate Aug<31>2005 17:12 Aug 21, 2008 Jkt 214001 PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 E:\\FR\\FM\\22AUN1.SGM 22AUN1 jlentini on PROD1PC65 with NOTICES

49714 Federal Register / Vol. 73, No. 164 / Friday, August 22, 2008 / Notices 1 Attachment 1 contains sensitive information and will not be released to the public.

2 Attachment 2 contains some requirements that are SAFEGUARDS INFORMATION, and cannot be released to the public. The remainder of the requirements contained in Attachment 2 that are not SAFEGUARDS INFORMATION will be released to the public.

equipment and facilities that they use to establish the video teleconferencing link. The availability of video teleconferencing services is not guaranteed.

Dated: August 18, 2008.

Annette Vietti-Cook, Secretary of the Commission.

[FR Doc. E8-19485 Filed 8-21-08; 8:45 am]

BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION

[ EA-08-212]

In the Matter of; All Licensees Authorized To Manufacture or Initially Transfer Items Containing Radioactive Material for Sale or Distribution and Possess High-Risk Radioactive Material of Concern; Order Imposing Additional Security Measures (Effective Immediately)

I The Licensees identified in 1 to this Order hold licenses issued in accordance with the Atomic Energy Act of 1954, as amended, by the U.S. Nuclear Regulatory Commission (NRC or Commission) or an Agreement State authorizing them to manufacture or initially transfer items containing radioactive material for sale or distribution. Commission regulations at 10 CFR 20.1801 or equivalent Agreement State regulations require Licensees to secure, from unauthorized removal or access, licensed materials that are stored in controlled or unrestricted areas. Commission regulations at 10 CFR 20.1802 or equivalent Agreement State regulations require Licensees to control and maintain constant surveillance of licensed material that is in a controlled or unrestricted area and that is not in storage.

II On September 11, 2001, terrorists simultaneously attacked targets in New York, N.Y., and Washington, DC, utilizing large commercial aircraft as weapons. In response to the attacks and intelligence information subsequently obtained, the Commission issued a number of Safeguards and Threat Advisories to its Licensees in order to strengthen Licensees capabilities and readiness to respond to a potential attack on a nuclear facility. The Commission has also communicated with other Federal, State and local government agencies and industry representatives to discuss and evaluate the current threat environment in order to assess the adequacy of security measures at licensed facilities. In addition, the Commission has been conducting a review of its safeguards and security programs and requirements.

As a result of its consideration of current safeguards and license requirements, as well as a review of information provided by the intelligence community, the Commission has determined that certain additional security measures are required to be implemented by Licensees as prudent measures to address the current threat environment. Therefore, the Commission is imposing the requirements set forth in Attachment 2 2 on certain Manufacturing and Distribution Licensees identified in of this Order who currently possess, or have near term plans to possess, high-risk radioactive material of concern. These requirements, which supplement existing regulatory requirements, will provide the Commission with reasonable assurance that the public health and safety and common defense and security continue to be adequately protected in the current threat environment. Attachment 3 of this Order contains the requirements for fingerprinting and criminal history record checks for individuals when a licensees reviewing official is determining access to Safeguards Information or unescorted access to the radioactive materials. These requirements will remain in effect until the Commission determines otherwise.

The Commission concludes that the security measures must be embodied in an Order consistent with the established regulatory framework. Furthermore, the Commission has determined that some of the security measures contained in of this Order contain Safeguards Information and will not be released to the public as per the NRCs Order Imposing Requirements for the Protection of Certain Safeguards Information (EA-08-161), regarding the protection of Safeguards Information. The Commission hereby provides notice that it intends to treat all violations of the requirements contained in Attachment 2 to the NRCs Order Imposing Requirements for the Protection of Certain Safeguards Information (EA-08-161), applicable to the handling and unauthorized disclosure of Safeguards Information as serious breaches of adequate protection of the public health and safety and the common defense and security of the United States. Access to Safeguards Information is limited to those persons who have established a need-to-know the information, are considered to be trustworthy and reliable, have been fingerprinted and undergone a Federal Bureau of Investigation (FBI) identification and criminal history records check in accordance with the NRCs Order Imposing Fingerprinting and Criminal History Records Check Requirements for Access to Safeguards Information (EA-08-162). A need-to-know means a determination by a person having responsibility for protecting Safeguards Information that a proposed recipients access to Safeguards Information is necessary in the performance of official, contractual, or licensee duties of employment.

Individuals who have been fingerprinted and granted access to Safeguards Information by the reviewing official under the NRCs Order Imposing Fingerprinting and Criminal History Records Check Requirements for Access to Safeguards Information (EA-08-162) do not need to be fingerprinted again for purposes of being considered for unescorted access.

This Order also requires that a reviewing official must consider the results of the Federal Bureau of Investigations criminal history records check in conjunction with other applicable requirements to determine whether an individual may be granted or allowed continued unescorted access.

The reviewing official may be one that has previously been approved by NRC in accordance with the Order Imposing Fingerprinting and Criminal History Records Check Requirements for Access to Safeguards Information (EA 162). Licensees may nominate additional reviewing officials for making unescorted access determinations in accordance with NRC Orders EA-08-162. The nominated reviewing officials must have access to Safeguards Information or require unescorted access to the radioactive material as part of their job duties.

To provide assurance that Licensees are implementing prudent measures to achieve a consistent level of protection to address the current threat environment, Manufacturing and Distribution Licensees identified in to this Order shall implement the requirements identified in Attachments 2 and 3 to this Order. In addition, pursuant to 10 CFR 2.202, I VerDate Aug<31>2005 17:12 Aug 21, 2008 Jkt 214001 PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 E:\\FR\\FM\\22AUN1.SGM 22AUN1 jlentini on PROD1PC65 with NOTICES

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 Appendix II August 15, 2008 AGENDA 555th ACRS MEETING SEPTEMBER 4-6, 2008 THURSDAY, SEPTEMBER 4, 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.

License Renewal Application and Final SER for the Wolf Creek Generating Station, Unit 1 (Open) (JDS/PW) 2.1)

Remarks by the Subcommittee Chairman 2.2)

Briefing by and discussions with representatives of the NRC staff and Wolf Creek Nuclear Operating Corporation regarding the license renewal application for the Wolf Creek Generating Station, Unit 1, and the associated NRC staffs final Safety Evaluation Report (SER).

Members of the public may provide their views, as appropriate.

10:30 - 10:45 A.M.

• • • BREAK ***

3) 10:45 - 12:15 P.M.

Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants (Open) (OLM/CEA) 3.1)

Remarks by the Subcommittee Chairman 3.2)

Briefing by and discussions with representatives of the NRC staff regarding the draft final revision 1 to Regulatory Guide 1.131 and the NRC staffs resolution of public comments.

Representatives of the nuclear industry and members of the public may provide their views, as appropriate.

12:15 - 1:15 P.M.

• • • LUNCH ***

4) 1:15 -3:15 P.M.

TRACE Computer Code Peer Review (Open) (SB/DB) 4.1)

Remarks by the Subcommittee Chairman 4.2)

Briefing by and discussions with representatives of the NRC staff regarding the findings of the Peer-Review Panel for the TRACE computer code and the staffs plans to address the Panels findings.

Representatives of the nuclear industry and members of the public may provide their views, as appropriate.

3:15 - 3:30 P.M.

• • • BREAK ***

5) 3:30 - 4:30 P.M.

Anticipated Advanced Reactor Research Needs (Open) (MLC/MB)

Discussions among the ACRS members regarding the anticipated advanced reactor research needs and related matters.

6) 4:30 - 7:00 P.M.

Preparation of ACRS Reports (Open)

Discussion of proposed ACRS reports on:

6.1)

License Renewal Application for the Wolf Creek Generating Station, Unit 1 (JDS/PW) 6.2)

Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants (OLM/CEA) 6.3)

TRACE Computer Code Peer Review (SB/DB)

FRIDAY SEPTEMBER 5, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

7) 8:30 - 8:35 A.M.

Opening Remarks by the ACRS Chairman (Open) (WJS/CS/SD)

8) 8:35 - 10:00 A.M.

Quality Assessment of Selected Research Projects (Open) (DAP/HPN) 8.1)

Remarks by the Subcommittee Chairman 8.2)

Report by and discussions with members of the ACRS Panels which performed the quality assessment of the NRC research projects on: FRAPCON / FRAPTRAN Code work at the Pacific Northwest National Laboratory (PNNL),

and NUREG/CR - 6943, A Study of Remote Visual Methods to Detect Cracking in Reactor Components.

10:00 - 10:15 A.M.

• • • BREAK ***

9) 10:15 - 11:15 A.M.

Future ACRS Activities/Report of the Planning and Procedures Subcommittee (Open/Closed) (WJS/AFD/SD) 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.

[NOTE: A portion of this meeting may be closed pursuant to 5 U.S.C. 552b (c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.]

10) 11:15 - 11:30 A.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.

11) 11:30 - 12:00 P.M.

Subcommittee Reports (Open) 11.1) Report by and discussions with the Chairman of the ACRS Subcommittee on ESBWR regarding the review the PRA associated with the ESBWR that was discussed during the Subcommittee meeting on August 21-22, 2008.

(MLC/HJV).

11.2) Report by and discussions with the Chairman of the ACRS Subcommittee on Materials, Metallurgy, and Reactor Fuels regarding various matters associated with reactor fuels that were discussed during the Subcommittee meeting on September 3, 2008, (JSA/CLB).

12:00 - 2:00 P.M.

• • • LUNCH ***

12) 2:00 - 7:00 P.M.

Preparation of ACRS Reports (Open)

Continued discussion of proposed ACRS reports on:

12.1) License Renewal Application for the Wolf Creek Generating Station, Unit 1 (JDS/PW) 12.2) Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants (OLM/CEA) 12.3) TRACE Computer Code Peer Review (SB/DB)

SATURDAY SEPTEMBER 6, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

13) 8:30 - 12:00 P.M.

Preparation of ACRS Reports (Open)

(10:30-10:45 A.M. BREAK) Continue discussion of proposed ACRS reports listed under Item 11.

14) 12:00 - 12:30 P.M.

Miscellaneous (Open) (WJS/AFD)

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.

Appendix III 555th ACRS Meeting List of Attendees June 4, 2008 NAME NRC ORGANIZATION 1

H. Esmaili RES 2

S. Wong NRR 3

J. Foster RES 4

T. Kolb NRR 5

C. Hinten RES 6

E. Goldfeiz RES 7

R. Jenkins RES 8

B. Wagner RES 9

S. Lai RES 10 D. ONeal RES 11 M. Stutzke RES 12 P. Appignani RES 13 J. Monninger RES 14 D. Marksberry RES 15 S. Sancaletar RES 16 A. Kurtzky RES 17 M. Fravonovich NRR 18 D. Helton RES 19 C. Lui RES 20 G. Testaye NRO 21 T. Roy NRO 22 S. Arora NRO 23 P. Hearn NRO 24 S. Lu NRO 25 J. Rycyna NRO 26 M. Canova NRO 27 J. Donohue NRO 28 F. Forty NRO 29 D. Dube NRO 30 H. Phen NRO

555th ACRS Meeting List of Attendees June 4, 2008 29 J. Colaccino NRO 30 B. Schnetzler NSIR 31 T. Reed NRR D. Rahn NMSS 33 N. Gilles NRO 34 P. Madden NRO 35 P. Holahan NSIR 36 J. Zimmerman NRR 37 S. Ali RES 38 B. Richter NRR 39 R. Lois NRR

555th ACRS Meeting List of Attendees June 5, 2008 NAME NRC ORGANIZATION 1

E. ODonnell RES 2

E. Roach NRO 3

J. Shaperow RES 4

J. Mitchell RES

555th ACRS Meeting List of Attendees June 6, 2008 NAME NRC ORGANIZATION 1

J. Thompson NRP 2

W. Ward NRO 3

N. Otto NRO 4

M. Takacs NRO 5

J. Perez RES 6

J. Schmidt NRR 7

J. Honcharik NRO 8

E. Reichelt NRO 9

R. Clement NRO 10 L. Monica NRO 11 D. Dube NRO 12 L. Burkhart NRO 13 H. Boltman NRO 14 S. Schroer NRO 15 R. Chazell NRO 16 Y. Wong NRO 17 P. Hearn NRO 18 G. Hammer NRO 19 Y. G.

NRO 20 A. Drozd NRO 21 S. Monagene NRO 22 R. Landry NRO 23 M. Yoder NRR 24 P. Klein NRR 25 D. McGovern NRO 26 J. Barr RES 27 B. Ruland NRR 28 A. Hiser NRR 29 J. Burke RES 30 M. Galloway NRR 31 R. Artchizel NRR 32 T. Koshy RES

555th ACRS Meeting List of Attendees June 4, 2008 NAME OUTSIDE ORGANIZATION 1

D. Algama Mitsubishi Nuclear Energy Systems 2

R. Pederson AREVA NP 3

V. Fregunese AREVA NP 4

M. Parece AREVA NP 5

S. Sloan AREVA NP 6

R. Salm AREVA NP 7

M. Carpenter AREVA NP 8

P. Baker AREVA NP 9

J. Tucker AREVA NP 10 J. Mihalak Uniston Nuclear Energy 11 C. Tally AREVA 12 M. Owens AREVA 13 T. Oswald AREVA 14 R. Sgarro PPL Nuclear Development 15 J. McLella NARP 16 G. Zyby Alion Science & Technology 17 D. Fischer NUMARK Associates

555th ACRS Meeting List of Attendees June 5, 2008 NAME OUTSIDE ORGANIZATION 1

M. Purnell TVA Licensing 2

J. D. Wolcott TVA Licensing

555th ACRS Meeting List of Attendees 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 555th ACRS MEETING, SEPTEMBER 4-6, 2008 Agenda Item 2:

License Renewal Application and Final SER for the Wolf Creek Generating Station, Unit 1

1.

Proposed Schedule

2.

Status Report

3.

Subcommittee Meeting Minutes

4.

SBO Open Items (WCNOC Letter 3/29/08)

5.

Open Item 4.3 (WCNOC Letter 11/30/07)

6.

Metal Fatigue Open Items (WCNOC Letter 5/15/08)

7.

Metal Fatigue Open Items (WCNOC Letter 6/9/08)

Agenda Item 3:

Draft Final Revision 1 to Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants

8.

Table of Contents

9.

Proposed Agenda

10.

Status Report

11.

Draft Final Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants, Rev. 1

12.

Redline strikeout in June 2007 DG -1132 to July 2008 Draft Final Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants, Rev.1

13.

Redline strikeout from July to September 2008 Draft Final Regulatory Guide 1.131, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants, Rev. 1

14.

Response to Public Comments for Draft Regulatory DG - 1132, Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants, Proposed Revision to Regulatory Guide 1.131, Rev.1

15.

IEEE Standard 383-2003, IEEE Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations

Agenda Item 4:

TRACE Computer Code Peer Review

16.

Table of Contents

17.

Proposed Schedule

18.

Status Report

19.

Memorandum, Dated June 18, 2008, from Farouk Eltawila, Director, Division of Safety Analysis, Office of Nuclear Regulatory Research, to Frank Gillespie, Executive Director, ACRS,

Subject:

TRANSMITTAL OF SUPPORT DOCUMENTS FOR THE TRACE COMPUTER CODE BRIEFING ON JULY 7, 2008 (ML081640398

20.

Theory Manual (ML071000097)

21.

Assessment Manual and Appendices A, B and C (ML071200456, ML071200466, ML071200473

22.

Users Manual Volumes 1 (ML071200473) and 2 (ML071720510); Draft Reports from Peer Reviewers: Dominique Bestion (ML081640540), Peter Griffith (ML081640551),

Marv Thurgood (ML081640564), and George Yadigaroglu (ML081640560)

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 September 11, 2008 Appendix V AGENDA 556th ACRS MEETING OCTOBER 2-4, 2008 THURSDAY, OCTOBER 2, 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 - 10:00 A.M.

License Renewal Application and Final Safety Evaluation Report (SER) for the Shearon Harris Nuclear Power Plant, Unit 1 (Open) (JS/PW) 2.1)

Remarks by the Subcommittee Chairman 2.2)

Briefing by and discussions with representatives of the NRC staff and Carolina Power & Light Company regarding the license renewal application for the Shearon Harris Nuclear Power Plant, Unit 1, and the associated NRC staffs final Safety Evaluation Report (SER).

Members of the public may provide their views, as appropriate.

10:00 - 10:15 A.M.

• • • BREAK ***

3) 10:15 -12:15 P.M.

Status of Resolution of Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance (Open) (SB/DAW/DB) 3.1)

Remarks by the Subcommittee Chairman 3.2)

Briefing by and discussions with representatives of the NRC staff and PWR Owners Group regarding the staff and industry activities associated with the resolution of GSI-191.

Representatives of the nuclear industry and members of the public may provide their views, as appropriate.

12:15 - 1:15 P.M.

• • • LUNCH ***

4) 1:15 - 3:15 P.M.

Selected Chapters of the SER Associated with the Economic Simplified Boiling Water Reactor (ESBWR) Design Certification Application (Open/Closed) (MLC/HJV) 4.1)

Remarks by the Subcommittee Chairman 4.2)

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).]

3:15 - 3:30 P.M.

• • • BREAK ***

5) 3:30 - 4:00 P.M.

Quality Assessment of Selected Research Projects (Open)

(DAP/HPN) 5.1)

Remarks by the Subcommittee Chairman 5.2)

Discussion of the draft final report on the quality assessment of the NRC research projects on: FRAPCON /

FRAPTRAN Code work at the Pacific Northwest National Laboratory (PNNL), and NUREG/CR - 6943, A Study of Remote Visual Methods to Detect Cracking in Reactor Components.

6) 4:00 - 5:15 P.M.

Historical Perspectives and Insights on Reactor Consequence Analyses (Open) (WJS/HPN)

Discussion of the draft White Paper prepared by Dr. Nourbakhsh, ACRS Senior Technical Advisor, regarding historical perspectives and insights on reactor consequence analyses.

5:15 - 5:30 P.M.

• • • BREAK ***

7) 5:30 - 7:00 P.M.

Preparation of ACRS Reports (Open)

Discussion of proposed ACRS reports on:

7.1)

License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 (JS/PW) 7.2)

Status of Resolution of Generic Safety Issue - 191 (SB/DAW/DB) 7.3)

Selected Chapters of the SER Associated with the ESBWR Design Certification Application (MLC/HJV)

FRIDAY, OCTOBER 3, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

8) 8:30 - 8:35 A.M.

Opening Remarks by the ACRS Chairman (Open) (WJS/CS/SD)

9) 8:35 - 9:30 A.M.

Future ACRS Activities/Report of the Planning and Procedures Subcommittee (Open/Closed) (WJS/EMH/SD) 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.

[NOTE: A portion of this meeting may be closed pursuant to 5 U.S.C. 552b (c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.]

10) 9:30 - 9:45 A.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.

11) 9:45 - 10:00 A.M.

Subcommittee Reports (Open) 11.1) Report by and discussions with the Chairman of the ACRS Subcommittee on Materials, Metallurgy, and Reactor Fuels regarding Proposed Supplemental Pressurized Thermal Shock Rule (10 CFR 50.61) that was discussed during the Subcommittee meeting on October 1, 2008. (WJS/CLB) 11.2) Report by and discussions with the Chairman of the ACRS Subcommittee on Reliability and PRA regarding the draft final NUREG-1855, Guidance on the Treatment of Uncertainties in Risk-Informed Decisionmaking, that was discussed during the Subcommittee meeting on September 30, 2008. (GEA/HJV) 10:00 - 10:15 A.M.

• • • BREAK ***

12) 10:15 - 11:30 A.M.

Preparation for Meeting with the Commission on November 7, 2008 (Open) (WJS, et al. /EMH, et al.)

Discussion of proposed topics for meeting with the Commission on November 7, 2008.

11:30 - 12:30 P.M.

• • • LUNCH ***

13) 12:30 - 7:00 P.M.

Preparation of ACRS Reports (Open)

Continued discussion of proposed ACRS reports on:

13.1) License Renewal Application for the Shearon Harris Nuclear Power Plant, Unit 1 (JS/PW) 13.2) Status of Resolution of Generic Safety Issue - 191 (SB/DAW/DB) 13.3) Selected Chapters of the SER Associated with the ESBWR Design Certification Application (MLC/HJV)

SATURDAY, OCTOBER 4, 2008, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

14) 8:30 - 1:00 P.M.

Preparation of ACRS Reports (Open)

(10:30-10:45 A.M. BREAK) Continue discussion of the proposed ACRS reports listed under Item 13.

15) 1:00 - 1:30 P.M.

Miscellaneous (Open) (WJS/EMH)

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.