Advisory Committee on Reactor Safeguards

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MEMBERS OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (last updated - Oct 2006)

* Dr. Said Abdel-Khalik, Southern Nuclear Distinguished Professor, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia

* Dr. Joseph S. Armijo, Adjunct Professor of Materials Science and Engineering at the University of Nevada, Reno

* Dr. George E. Apostolakis, Professor of Nuclear Science and Engineering, Professor of Engineering Systems, Massachusetts Institute of Technology, Cambridge, Massachusetts

* Dr. Sanjoy Banerjee, Professor of Chemical Engineering, University of California at Santa Barbara, Santa Barbara, California

* Dr. Mario V. Bonaca, Retired Director, Nuclear Engineering Department, Northeast Utilities, Connecticut

* Dr. Michael Corradini, Professor and Chairman of Department of Engineering Physics, University of Wisconsin, Madison, Wisconsin

* Dr. Thomas S. Kress, Retired Head of Applied Systems Technology Section, Oak Ridge National Laboratory, Oak Ridge, Tennessee

* Mr. Otto L. Maynard, Retired Chief Executive Officer, Wolf Creek Generating Station, Kansas

* Dr. Dana A. Powers, Senior Scientist, Sandia National Laboratories, Albuquerque, New Mexico

* Dr. William J. Shack, (Vice-Chairman), Associate Director, Energy Technology Division, Argonne National Laboratory, Argonne, Illinois

* Mr. John D. Sieber, (Member-at-Large), Retired Senior Vice-President, Nuclear Power Division, Duquesne Light Company, Pittsburgh, Pennsylvania

* Dr. Graham B. Wallis, (Chairman), Sherman Fairchild Professor Emeritus, Thayer School of Engineering, Dartmouth College, Hanover, New Hampshire

ABOUT THE ACRS

The Advisory Committee on Reactor Safeguards (ACRS) was established as a statutory Committee of the Atomic Energy Commission (AEC) by a 1957 amendment to the Atomic Energy Act of 1954. The functions of the Committee are described in Sections 29 and 182b of the Act. The Energy Reorganization Act of 1974 transferred the AEC's licensing functions to the U.S. Nuclear Regulatory Commission (NRC), and the Committee has continued serving the same advisory role to the NRC.

The ACRS provides independent reviews of, and advice on, the safety of proposed or existing NRC-licensed reactor facilities and the adequacy of proposed safety standards. The ACRS reviews power reactor and fuel cycle facility license applications for which the NRC is responsible, as well as the safety-significant NRC regulations and guidance related to these facilities. On its own initiative, the ACRS may review certain generic matters or safety-significant nuclear facility items. The Committee also advises the Commission on safety-significant policy issues, and performs other duties as the Commission may request. Upon request from the U.S. Department of Energy (DOE), the ACRS provides advice on U.S. Naval reactor designs and hazards associated with the DOE's nuclear activities and facilities. In addition, upon request, the ACRS provides technical advice to the Defense Nuclear Facilities Safety Board.

ACRS operations are governed by the Federal Advisory Committee Act (FACA), which is implemented through NRC regulations at Title 10, Part 7, of the Code of Federal Regulations (10 CFR Part 7). ACRS operational practices encourage the public, industry, State and local governments, and other stakeholders to express their views on regulatory matters.

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ACRS news

February 15, 2008

ACRS to take over functions of ACNW

NRC calls it a merger between the Advisory Committee on Reactor Safeguards and the Advisory Committee on Radioactive Waste. An extra committee slot will be added, mainly in expectation for including a radiation protection expert on the committee. All of the current ACNW members will be offered roles as consultants to ACRS, and ACRS will be enlarged to include one new committee member, to bring in a health physics expert.

May 5, 2007

New this week from NRC Public Document Room

* [2007-05-05] Memo to Frank Gillespie, Providing Information on PHEBUS-FP for ACRS Meeting 543 - June 6-8, 2007. ML071240063 2007-05-04 12 2007-05-04 2007-05-04 May 4, 2007 MEMORANDUM TO: Frank P. Gillespie, Director Advisory Committee on Reactor Safeguards FROM: Farouk Eltawila, Director /RA/ C. Lui for Division of Risk Assessment and Special Projects Office of Nuclear Regulatory Research SU

* [2007-05-04] Federal Register Notice Regarding the ACRS Subcommittee Meeting on - Thermal- Hydraulic Phenomena, May 15-16, 2007, Rockville, Maryland. ML071170049 2007-04-25 3 GT 350 2007-04-25 2007-05-03 April 25, 2007 MEMORANDUM TO: Cayetano Santos, Acting Branch Chief, ACRS FROM: Zena Abdullahi, Senior Staff Engineer /RA/ SUBJECT: FEDERAL REGISTER NOTICE REGARDING THE ACRS SUBCOMMITTEE MEETING ON THERMAL-HYDRAULIC PHENOMENA,

* [2007-05-04] Transcript of ACRS Subcommittee on Digital Instrumentation & Control Systems Meeting, April 18, 2007, pages 1-307. ML071230233 2007-04-18 430 NRC-1527 ACRST-3391 2007-04-18 2007-05-03 Official Transcript of Proceeding s-ms-rc33v9 NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards Subcommittee on Digital Instrumentation and Control Systems Docket Number: (not applicable

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, March 8-9, 2007, Minutes. ML071150508 2007-04-25 11 2007-04-25 2007-05-02 ML071220203+ ML071150508 i CERTIFIED Date Issued: 04/25/07 Date Certified: 04/25/07 TABLE OF CONTENTS MINUTES OF THE 540th ACRS MEETING March 8 - 9, 2007 I. Opening Remarks by the ACRS Chairman (Open) II. Technical Basis Associated wi

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, Minutes, Appendix 1 (Federal Register Notice). ML071220207 2007-05-02 2 2007-05-02 2007-05-02 ML071220203+ 7481 Federal Register / Vol. 72, No. 31 / Thursday, February 15, 2007 / Notices NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Subcommittee Meeting on Materials, Metallurgy, and Reactor Fue

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, Minutes, Appendix 2, (Agenda). ML071220209 2007-02-09 6 2007-02-09 2007-05-02 ML071220203+ February 9, 2007 SCHEDULE AND OUTLINE FOR DISCUSSION 540th ACRS MEETING MARCH 8-10, 2007 THURSDAY, MARCH 8, 2007, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND 1) 8:30 - 8:35 A.M. Opening Remarks by th

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, Minutes, Appendix 3, (Attendees). ML071220210 2007-03-08 4 2007-03-08 2007-05-02 ML071220203+ ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 540TH FULL COMMITTEE MEETING March 8-10, 2007 NRC STAFF SIGN IN FOR ACRS MEETING TodayÕs Date: March 8, 2007 PLEASE PRINT NAME NRC ORGANIZATION Tai Huang NRR/DSS/SRXB Bob Hardies R

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, Minutes, Appendix 4, (Future Agenda). ML071220215 2007-03-15 5 2007-03-15 2007-05-02 ML071220203+ March 15, 2007 SCHEDULE AND OUTLINE FOR DISCUSSION 541st ACRS MEETING APRIL 5-7, 2007 THURSDAY, APRIL 5, 2007, CONFERENCE ROOM T-2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND 1) 8:30 - 8:35 A.M. Opening Remarks by the A

* [2007-05-03] 540th Meeting of the Advisory Committee on Reactor Safeguards, Minutes, Appendix 5, (List of Handouts). ML071220220 2007-05-02 2 2007-05-02 2007-05-02 ML071220203+ APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE 540TH ACRS MEETING MARCH 8-10, 2007 [ Note: Some documents listed below may have been provided or prepared for the Committee use only. These documents must be reviewe

* [2007-05-03] ACRS Memo Transmitting Draft Safety Evaluation (SE) for GE LTR NEDC-33006P, "Maximum Extended Load Line Limit Plus." ML071200511 2007-05-01 3 PROJ0710 2007-05-01 2007-05-02 May 1, 2007 MEMORANDUM TO: Frank P. Gillespie, Executive Director Advisory Committee on Reactor Safeguards FROM: Michael J. Case, Director /RA/ Division of Policy and Rulemaking Office of Nuclear Reactor Regulation SUBJECT: G

* [2007-05-02] Transcript of 541st ACRS Meeting, on Thursday, April 5, 2007 in Rockville, MD. Pages 1-297. ML071130311 2007-04-05 420 NRC-1514 ACRST-3390 2007-04-05 2007-05-01 9 Official Transcript of ProceedingsA&r IàP '3o9 NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards 541 st Meeting Docket Number: (not applicable) POESS USING ADAMS TEMPLATE: ACRS/ACNW-0o

* [2007-05-01] 05/03-05/2007 Revised 542nd Meeting of the Advisory Committee on Reactor Safeguards - FRN. ML071100041 2007-04-20 1 CM 160 FR Citation: 04/26/2007 72 FR 20890 2007-04-20 2007-04-30 7590-01-P Federal Register Notice ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION Revised Meeting Notice The agenda for the 542nd ACRS meeting, scheduled to be held on

* [2007-05-01] Human Reliability Analysis Models ML071140297 2007-04-23 4 GT-270 R-2247 2007-04-23 2007-04-30 ACRSR-2247 April 23, 2007 The Honorable Dale E. Klein Chairman U.S. Nuclear Regulatory Commission Washington DC 20555-0001 SUBJECT: HUMAN RELIABILITY ANALYSIS MODELS Dear Chairman Klein: In a November 8, 2006 Staff Requi

* [2007-05-01] Revision 3 to Standard Review Plan Section 4.2, "Fuel System Design" ML071140241 2007-04-23 3 GT 290 R-2246 2007-04-23 2007-04-30 ACRSR-2246 April 23, 2007 Luis A. Reyes Executive Director for Operations U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: REVISION 3 TO STANDARD REVIEW PLAN SECTION 4.2, ÒFUEL SYSTEM DESIGNÓ Dear M

* [2007-05-01] Risk-Informed Technical Specification Initiative 4B, Risk-Managed Technical-Specification (RMTS) Guidelines ML071140271 2007-04-23 2 GT-270 R-2245 2007-04-23 2007-04-30 ACRSR-2245 April 23, 2007 Luis A. Reyes Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: RISK-INFORMED TECHNICAL SPECIFICATIONS INITIATIVE 4B, RISK-MANAGED TECHNICAL

* [2007-05-01] Transcript of ACRS Materials, Metallurgy and Reactor Fuels Subcommittee on Tuesday, April 3, 2007 in Rockville, MD. Pages 1-155. ML071100139 2007-04-03 259 NRC-1512 ACRST-3388 2007-04-03 2007-04-30 Official Transcript of Proceedings-ACRST-733( NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards Materials, Metallurgy and Reactor Fuels Subcommittee Docket Number: (not applicable) PROCE

April 21, 2007

New this week from NRC Public Document Room

* [2007-04-21] FRN - Meeting of ACRS Subcommittee on Planning and Procedures, May 2, 2007. ML071030108 2007-04-10 3 CM-230 2007-04-10 2007-04-20 April 10, 2007 MEMORANDUM TO: Cayetano Santos, Acting Branch Chief, ACRS/ACNW FROM: Sam Duraiswamy, ACRS /RA/ SUBJECT: FEDERAL REGISTER NOTICE REGARDING THE MEETING OF THE ACRS SUBCOMMITTEE ON PLANNING AND PROCEDURES, MAY 2, 20

* [2007-04-21] ACRS Committee and Consultant Reports ML071020323 2007-04-13 3 AA110 2007-04-13 2007-04-20 April 13, 2007 MEMORANDUM TO: Andrew L. Bates, Advisory Committee Management Officer FROM: Jenny M. Gallo, Chief Operations Support Branch, ACRS SUBJECT: ACRS COMMITTEE AND CONSULTANT REPORTS The enclosed documents were prepared

* [2007-04-19] 05/03-05/2007 - 542nd Meeting of the Advisory Committee on Reactor Safeguards - Federal Register Notice ML071020017 2007-04-12 4 CM 160 2007-04-12 2007-04-18 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 o

* [2007-04-19] Press Release-07-050: NRC Advisory Committee On Reactor Safeguards To Meet In Rockville, Maryland, May 3-5. ML071080252 2007-04-18 1 Press Release-07-050 2007-04-18 2007-04-18 NRC NEWS U.S. NUCLEAR REGULATORY COMMISSION Office of Public Affairs Telephone: 301/415-8200 Washington, D.C. 20555-0001 E-mail: opa@nrc.gov Web Site: http://www.nrc.gov No. 07-050 April 18, 2007 NRC ADVISORY COMM

* [2007-04-17] 04/19/2007, Forthcoming Closed Meeting with General Electric Nuclear Energy (GENE), Preparation for Upcoming Advisory Committee on Reactor Safeguards Meetings on Proprietary Topical Report NEDC-33173P, "Applicability of GE Methods to Expanded.... ML070920464 2007-04-16 5 PROJ0710 2007-04-16 2007-04-16 April 16, 2007 MEMORANDUM TO: Stacey L. Rosenberg, Chief Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation FROM: Michelle C. Honcharik, Project Manager /RA/ Special Projects Branch

* [2007-04-17] Transcript of ACRS Reliability and Probabilistic Risk Assessment Subcommittee on Thursday, March 22, 2007 in Rockville, MD. Pages 1-303. ML070960071 2007-03-22 372 ACRST-3386 NRC-1497 2007-03-22 2007-04-16 Official Transcript of Proceedings AScr-735 J' NUCLEAR REGULATORY COMMISSION Title: Advisory Committee on Reactor Safeguards Reliability and Probabilistic Risk Assessment Subcommittee Docket Number: (not applicable

* [2007-04-17] Transcript of the Meeting of the Subcommittee on Reliability and Risk Assessment, March 23, 2007, Rockville, MD, Pages 1-157. ML070960438 2007-03-23 214 NRC-1498 ACRST-3387 2007-03-23 2007-04-16 Official Transcript of ProceedigsA C 7 I NUCLEAR REGULATORY COMMISSION Title: Meeting of the Subcommittee on Reliability and Risk Assessment Docket Number: (None provided) PROCESS USING ADAMS TEMPLATE: ACRS/ACNW-00

February 22, 2007

Dealing with the Dissimilar Metal Weld Issue

On March 8, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to hear presentations by and hold discussions with representatives of the NRC staff, their contractors, and the Nuclear Energy Institute regarding the technical basis for the proposed regulatory action for dealing with the dissimilar metal weld issue stemming from the Wolf Creek pressurizer weld flaws, as well as the industry activities associated with this matter. ACRS announced that a portion of this session may be closed to discuss industry proprietary information. This will be the first subject covered that day, and is slated for 8:35 am to 10:15 am. The meeting is to be held at NRC's Rockville Maryland headquarters -- building TWFN, in conference room T-2B3.

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

Proposed Revisions to Standard Review Plan (SRP) sections on Accident Analysis and BWR Core Stability

On March 8, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to hear presentations by and hold discussions with representatives of the NRC staff regarding proposed revisions to SRP Sections 15.0, Accident Analysis - Introduction, and 15.9, BWR Core Stability. This session is slated for 10:30 am to noon. The meeting is to be held at NRC's Rockville Maryland headquarters -- building TWFN, in conference room T-2B3.

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

PWR Sump Performance - the chemical effects head loss tests

On March 8, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to hear presentations by and hold discussions with representatives of the NRC staff regarding final results of the chemical effects head loss tests in a pressurized water reactor (PWR) sump pool environment, and related matters. This session is slated for 1:30 pm to 3:30 pm. The meeting is to be held at NRC's Rockville Maryland headquarters -- building TWFN, in conference room T-2B3.

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

N-plants - Technology Neutral Licensing Framework

On March 8, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to hear presentations by and hold discussions with representatives of the NRC staff regarding the Technology Neutral Licensing Framework, and the Commission request in the November 8, 2006 Staff Requirements Memorandum that the ACRS provide its views to the Commission with respect to the staffÕs work on Technology Neutral Licensing Framework with the focus on ensuring the value of such an approach versus the development of a licensing framework for specific designs. This session is slated for 3:45 pm to 5:15 pm. The meeting is to be held at NRC's Rockville Maryland headquarters -- building TWFN, in conference room T-2B3.

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

ACRS considering report on the TRACE thermal-hydraulic system analysis code

On March 8, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to discuss proposed ACRS reports on matters considered during this meeting, as well as a proposed ACRS report on the TRACE thermal-hydraulic system analysis code. This session is slated for 5:30 pm to 7:00 pm. The meeting is to be held at NRC's Rockville Maryland headquarters -- building TWFN, in conference room T-2B3.

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

ACRS to discuss safeguards and security strategies for new reactor designs

On March 9, 2007, the Advisory Committee on Reactor Safeguards (ACRS) is scheduled to hear presentations by and hold discussions with representatives of the NRC staff regarding the research on mitigating strategies for new reactor designs. This session will be closed to public, to protect information classified as National Security information as well as safeguards information pursuant to 5 U.S.C. 552b(c)(1) and (3).

[Source: Meeting Notice for Federal Register, 540th Meeting of the Advisory Committee on Reactor Safeguards -- ML070400481]

March 27, 2004

The agenda for ACRS meeting on April 15-17 includes license renewal application for the R.E. Ginna nuclear power plant, and proposed options and recommendations for containment structures of non-light-water reactors. Complete agenda will be made available at http://www.nrc.gov/reading-rm/doc-collections/acrs/agenda/2004 [Source: NRC Office of Public Affairs, "NRC Advisory Committee on Reactor Safeguards to meet April 15-17 in Rockville, Maryland", press release 04-037, March 25, 2004 -- ACN ML040860077]

March 26, 2004

* Sump strainer clogging - ACRS issues of interest re draft Rev. 3 of Reg Guide 1.82

* ACRS - Essentially consultants to NRC



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