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Category:Letter
MONTHYEARML0930200562009-11-12012 November 2009
10/28/2009 Summary of Meeting with NEI to Discuss Generic License Renewal Topics and Activities
ML0905400922009-03-0303 March 2009
Summary of the License Renewal Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Nuclear Energy Institute
ML0805206192008-03-0505 March 2008
Proposed License Renewal Interim Staff Guidance LR-ISG-2008-01: Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated with License Renewal Applications
ML0729504952007-11-0808 November 2007
09/25/2007 Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and the Nuclear Energy Institute License Renewal Task Force
ML0717703762007-08-29029 August 2007
Proposed License Renewal Interim Staff Guidance LR-ISG-2007-02: Changes to Generic Aging Lesson Learned Report Aging Management Program XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
ML0722706072007-08-28028 August 2007
Summary of the License Renewal Telephone Conference Call and Meeting Held Between the U.S. Nuclear Regulatory Commission Staff and the Nuclear Energy Institute License Renewal Task Force
ML0717200422007-08-0909 August 2007
Draft of Revised Inspection Procedure IP-71003, Post-Approval Site Inspection for License Renewal
ML0716401332007-08-0202 August 2007
Letter to James Riley, NEI, Regarding Final License Renewal Interim Staff Guidance LR-ISG-2006-03: Staff Guidance for Preparing Severe Accident Mitigation Alternatives Analyses
ML0716902162007-07-0909 July 2007
03/21/2007, Summary of Meeting with Nuclear Energy Institute and Industry Representatives Regarding Environmental Report Content to Support License Renewal Application Reviews
ML0631904402007-02-0808 February 2007
Ltr. to A. Marion and D. Lochbaum Proposed License Renewal Interim Staff Guidance LR-ISQ-2006-02
ML0627002362006-10-11011 October 2006
Y020060051 - Applicability of the Backfitting Rule to the Obligations of NRC Renewal Licensees Under 10 CFR 54.37(b)
ML0620502192006-07-27027 July 2006
Change of U.S. (NRC) Branch Chief an Office of (NRR) Points of Contact for Nuclear Energy Institute (NEI) and Topic of Interest
ML0611200022006-05-0303 May 2006
Proposed License Renewal Interim Staff Guidance LR-ISG-2006-01: Plant-Specific Aging Management Program for Inaccessible Areas of Boiling Water Reactor Mark I Steel Containment Drywell Shell
ML0519400572005-07-12012 July 2005
U.S. Nuclear Regulatory Commission Comments on Nuclear Energy Institute (NEI) 05-01, Severe Accident Mitigation Alternative (SAMA) Analysis Guidance Document (Revision a)
ML0512502452005-05-0505 May 2005
Staff Response to Industry Position Paper on the Interim Staff Guidance Process - Response to Letter Dated February 18, 2005
ML0502103032005-01-19019 January 2005
Negative Impact Caused by 90-day Public Comment Period and Delay in Release of NEI 95-10
ML0424407762004-08-31031 August 2004
INDUSTRY-PROPOSED Material, Environment, Aging Effects, and Program Combinations for the GALL Report Update
ML0420402542004-07-21021 July 2004
Staff Response to Industry Questions on the NRC ISG Process Document Dated December 12, 2003 - Response to Your Letter Dated February 13, 2004
ML0416000872004-05-28028 May 2004
Proposed Method of the Nuclear Energy Institute to Update the GALL Report
ML0402201242004-01-21021 January 2004
Evaluation of Proposed Interim Staff Guidance (ISG)-11: Recommendations for Fatigue Environmental Effects in a License Renewal Application
ML0235206202003-12-12012 December 2003
the Interim Staff Guidance Process
ML0331100602003-11-0303 November 2003
Addition of Aging Management Program (AMP) for Fuse Holders
ML0331005162003-11-0303 November 2003
Proposed Interim Staff Guidance (ISG)-12: Addition of Generic Aging Lessons Learned (GALL) Aging Management Program (AMP) XI.M35, ONE-TIME Inspection of SMALL-BORE Piping, for License Renewal
ML0322505792003-08-12012 August 2003
Proposed Interim Staff Guidance (ISG)-15: Revision of Generic Aging Lessons Learned (GALL) Aging Management Program (AMP) XI.E2, Electrical Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Instrumentation Circuits
ML0318106302003-06-30030 June 2003
Request for Additional Information for Proposed Interim Staff Guidance (ISG)-11: Recommendations for Fatigue Environmental Effects in a License Renewal Application
ML0318101422003-06-27027 June 2003
Resource Needs for License Renewal Application Reviews
ML0313207982003-05-12012 May 2003
Proposed Interim Staff Guidance (ISG)-16: Time-Limited Aging Analyses (Tlaas) Supporting Information for License Renewal Applications
ML0310805272003-04-18018 April 2003
Resource Needs for License Renewal Application Reviews
ML0310104232003-04-0808 April 2003
Proposed Interim Staff Guidance (ISG) on Identification and Treatment of Housing for Active Components for License Renewal
ML0309900522003-04-0707 April 2003
Standardized Format for License Renewal Applications (MB7344)
ML0308300952003-03-21021 March 2003
Staff Comments to Industry Guidance on Revised 54.4 (a)(2) Scoping Criterion (Non-Safety Affecting Safety) for License Renewal
ML0306905122003-03-10010 March 2003
Interim Staff Guidance (ISG) - 5 on the Identification and Treatment of Electrical Fuse Holders for License Renewal
ML0235005162002-12-16016 December 2002
Consolidated List of Commitments for License Renewal
ML0234401702002-12-0303 December 2002
Enclosures 2 and 3 - Interim Staff Guidance (ISG)-04: Aging Management of Fire Protection Systems for License Renewal
ML0234401372002-12-0303 December 2002
Interim Staff Guidance (ISG)-04: Aging Management of Fire Protection Systems for License Renewal
L-84-001, Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter)2002-11-13013 November 2002
Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter)
ML0231904792002-11-13013 November 2002
Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter)
ML0228004112002-09-25025 September 2002
Response to Letter License Renewal Appeals Process & Rules of Engagement
ML0221203832002-07-30030 July 2002
Staff Guidance for Updating the Improved License Renewal Guidance Documents
ML0220600482002-07-24024 July 2002
Nuclear Regulatory Commission'S Review Schedule of EPRI Technical Report, Guidelines for Addressing Fatigue Environmental Effects in License Renewal Application, (MRP-47), Draft Revision G
ML0220602902002-07-24024 July 2002
Observations from Nuclear Energy Institute (NEI) License Renewal Demonstration Project & Comments from Advisory Committee on Reactor Safety Safeguards (ACRS) Letter Which May Result in Changes to NEI 95-10, Revision 3
ML0219205182002-07-11011 July 2002
Staff Comments to Industry Response on Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal
ML0219107222002-07-10010 July 2002
07/10/2002 Letter Re Reactor License Renewal Brochure, NUREG/BR-0291
ML0213703202002-05-16016 May 2002
Proposed Staff Guidance on the Identification and Treatment of Electrical Fuse Holders for License Renewal
ML0209801942002-04-0505 April 2002
Staff Response to Industry'S Proposed Revisions of Chapters II and III Generic Aging Lessons Learned (GALL) Report on Aging Management of Concrete Elements
ML0209204642002-04-0101 April 2002
Nuclear Energy Inst. & Union of Concerned Scientists - Staff Guidance on Scoping of Equipment Relied on to Meet Requirements of Standard Blackout (SBO) for License Renewal
ML0206001002002-03-0101 March 2002
Proposed Staff Guidance on Scoping of Equipment Relied on to Meet the Requirements of the Station Blackout (SBO) Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3))
ML0203204912002-01-28028 January 2002
Enclosure to Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal
ML0203204532002-01-28028 January 2002
Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal
ML0203002942002-01-28028 January 2002
Proposed Staff Guidance on Scoping of Equipment Relied on to Meet the Requirements of the Station Blackout Rule (10 CFR 50.63) for License Renewal That Was Issued for Comments on November 14, 2001
2009-03-03
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Text
May 18, 2001 Mr. Douglas J. Walters Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, DC 20006-3708
SUBJECT:
PLAN AND SCHEDULE FOR NUCLEAR ENERGY INSTITUTE (NEI) ON CONTINUED DIALOG TOPICS IN THE GENERIC AGING LESSONS LEARNED (GALL) REPORT
Dear Mr. Walters:
During the license renewal steering committee meeting with NEI on April 18, 2001, the staff discussed one follow-up issue concerning the license renewal guidance documents that may involve both NEI and NRC staffs effort. The issue involves a continued dialog with NEI on the five topics identified by NEI in the GALL report. To help reach a common understanding of these topics and to begin dialog for a prompt resolution, the staff has enclosed a summary of each of the topics that represents current staff understanding.
In order to ensure the success of the continued dialog on these five topics in a timely manner, NEI is requested to provide a plan and schedule for its completion. If you have any questions regarding this matter, please contact Peter Kang at 301-415-2779.
Sincerely,
/RA/
Christopher I. Grimes, Chief License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Project No. 690
Enclosure:
As stated c w/encl: See next page
Mr. Douglas J. Walters Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, DC 20006-3708
SUBJECT:
PLAN AND SCHEDULE FOR NUCLEAR ENERGY INSTITUTE (NEI) ON CONTINUED DIALOG TOPICS IN THE GENERIC AGING LESSONS LEARNED (GALL) REPORT
Dear Mr. Walters:
During the license renewal steering committee meeting with NEI on April 18, 2001, the staff discussed one follow-up issue concerning the license renewal guidance documents that may involve both NEI and NRC staffs effort. The issue involves a continued dialog with NEI on the five topics identified by NEI in the GALL report. To help reach a common understanding of these topics and to begin dialog for a prompt resolution, the staff has enclosed a summary of each of the topics that represents current staff understanding.
In order to ensure the success of the continued dialog on these five topics in a timely manner, NEI is requested to provide a plan and schedule for its completion. If you have any questions regarding this matter, please contact Peter Kang at 301-415-2779.
Sincerely,
/RA/
Christopher I. Grimes, Chief License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Project No. 690
Enclosure:
As stated c w/encl: See next page ML011410321 Distribution: See next page Document Name: C:\LRSC.wpd *See previous concurrence OFFICE RLSB LA RLSB NAME P Kang EGHylton P T Kuo DATE 05/03/01 04/26/01* 05/03/01 IQMB:BC DSSA:D DE:D RLSB:BC TQuay G Holahan JRStrosnider CIGrimes 05/03/01 05/09/01 05/16/01 05/18/01 OFFICIAL RECORD COPY
DISTRIBUTION: ML011410321 HARD COPY RLSB RF E. Hylton E-MAIL:
PUBLIC J. Johnson W. Borchardt D. Matthews C. Carpenter C. Grimes W. Beckner B. Zalcman J. Strosnider G. Bagchi K. Manoly W. Bateman J. Calvo S. Rosenberg G. Holahan T. Collins B. Boger G. Galletti B. Thomas J. Moore R. Weisman M. Mayfield S. Bahadur A. Murphy W. McDowell S. Droggitis S. Duraiswami RLSB Staff A. Thadani R. Zimmerman C. Julian R. Gardner D. Chyu M. Modes J. Vora
NUCLEAR ENERGY INSTITUTE Project No. 690 cc:
Mr. Joe Bartell Mr. Robert Gill U.S. Department of Energy Duke Energy Corporation NE-42 Mail Stop EC-12R Washington, D.C. 20585 P.O. Box 1006 Charlotte, NC 28201-1006 Mr. Richard P. Sedano, Commissioner State Liaison Officer Mr. Charles R. Pierce Department of Public Service Southern Nuclear Operating Co.
112 State Street 40 Inverness Center Parkway Drawer 20 BIN B064 Montipelier, Vermont 05620-2601 Birmingham, AL 35242 National Whistleblower Center Mr. David Lochbaum 3238 P Street, N.W. Union of Concerned Scientists Washington, DC 20007-2756 1707 H Street, NW Suite 600 Mr. Stephen T. Hale Washington, DC 20006-3919 Florida Power & Light Company 9760 S.W. 344 Street Mr. Garry Young Florida City, Florida 33035 Entergy Operations, Inc.
Arkansas Nuclear One 1448 SR 333 GSB-2E Russellville, Arkansas 72802
- 1. Individual Plant Examination (IPE) or Individual Plant Examination for External Events (IPEEE) as a source document to consider for scoping
ÿ NEI considers it inappropriate for an applicant to establish a license renewal scoping and screening criterion that relies on plant-specific probabilistic analyses like IPEs and IPEEEs since they are not part of the Current Licensing Basis and only reflect the estimated core damage frequency for the plant configuration at that time.
ÿ NEI contends that IPEs and IPEEEs may contain recommendations to modify the plant, revise procedures, or develop training to further reduce the estimated core damage frequency but these recommendations are to be implemented only after approved under a 10 CFR 50.59 or 10 CFR 50.90 review.
ÿ Standard Review Plan for License Renewal, page 2.1-3 states that although the License Renewal Rule is deterministic, probabilistic methods, on a plant-specific basis, may help assess the relative importance of structures and components subject to an aging management review by drawing attention to specific vulnerabilities.
ÿ Reviewing an IPE or IPEEE can help a reviewer determine what equipment is relied on for mitigation of design basis and severe accidents.
Enclosure
- 2. Operating experience with cracking of small-bore piping
ÿ NEIs position is that Inservice Inspections (ISI) and Chemistry Control at BWRs are adequate as an aging management program. Operating experience does not justify doing more.
ÿ GALL recommends a volumetric one-time inspection for evidence of no cracking to verify the effectiveness of chemistry control. The one-time inspection augments the aging management program consisting of primary water chemistry and inservice inspections for Class 1 components at BWRs.
- 3. Management of loss of preload on reactor vessel internals bolting using the loose parts monitoring system
ÿ NEI believes that ISI Visual Inspections are adequate for management of loss of preload on reactor vessel internals bolting.
ÿ GALL recommends that loss of preload on reactor vessel internals bolting be managed by ISI and loose parts monitoring.
ÿ NRC staff accepted Westinghouse Owners Group topical report WCAP-14577 which recommends loose parts monitoring as one of the surveillance techniques used to detect loss of preload and other aging effects on certain reactor vessel internals components as part of several aging management programs
ÿ ASME Code,Section XI, Category B-N-3 requires visual inspections of core support structures every 10 years.
- 4. Operating experience with cracking in bolting
ÿ NEIs position is that crack initiation/growth due to stress corrosion cracking for carbon steel closure bolting is not an aging effect/mechanism.
ÿ GALL recommends that crack initiation/growth be managed by the EPRI bolting integrity program
- 5. Inspection of fire protection systems
ÿ NEIs position is that National Fire Protection Association (NFPA) Codes are adequate for managing aging effects in fire water systems
ÿ NFPA Codes do not provide guidance for assessing internal corrosion of fire water systems which are not routinely subject to flow.
ÿ GALL recommends continuous system monitoring, internal inspection, and flow testing of fire water systems to ensure that corrosion (including microbiological influenced corrosion (MIC)) and biofouling are not occurring.