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Category:E-Mail
MONTHYEARML22235A7862022-08-23023 August 2022 Acceptance Review: Exemption Request from 10 CFR 20, Appendix G, LLW Shipping Investigation Requirements ML21181A1882021-06-30030 June 2021 E-mail from S. Johnston, Holtec, to A. Snyder and F. Bower, NRC - Oyster Creek Nuclear Generating Station - Readiness Status for ISFSI Only Inspection ML21175A2092021-06-24024 June 2021 E-mail from A. Sterdis to P. Longmire - Oyster Creek Nuclear Generating Station: ISFSI-only Physical Security Plan (Stating Implementation Intent) ML21162A3602021-06-11011 June 2021 E-mail Response from the State of New Jersey Regarding the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status ML21162A1172021-06-11011 June 2021 E-mail to HDI: Acceptance Review - FOF Exemption ML21168A0172021-06-10010 June 2021 E-mail from HDI: RAI Response ML21161A2572021-06-0707 June 2021 State Consultation: ISFSI-only Physical Security Plan (Email Response) ML21175A0712021-06-0202 June 2021 Issuance of Request for Additional Information: Oyster Creek Nuclear Generating Station. Request for Amendment to Technical Specifications ML21148A0562021-05-27027 May 2021 E-mail to State of New Jersey Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status ML21132A3182021-05-12012 May 2021 E-Mail from V. Gubbi, DEP to Z. Cruz, NRC - Oyster Creek Nuclear Generating Station - State of New Jersey Response to the Pending Revision to the Defueled Technical Specifications to Reflect Independent Spent Fuel Storage Installation Only ML21132A0312021-05-11011 May 2021 E-mail to State of New Jersey Informing of the Pending Revision to the Physical Security Plan to Reflect Independent Spent Fuel Storage Installation Only Status ML21119A1422021-04-28028 April 2021 E-mail to State of New Jersey Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status ML21113A0742021-04-23023 April 2021 Acceptance Review Email - April 20, 2021 Oyster Creek Request for Exemption from 10 CFR Part 73 Requirements Due to Covid ML21099A0382021-04-0808 April 2021 Email from Z. Cruz to A. Sterdis - Request for Additional Information - HDI Request for Approval of Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Facility Only Emergency Plan ML21085A4872021-03-26026 March 2021 E-mail from Z. Cruz to A. Sterdis - Acceptance Review: Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Only Permanently Defueled Technical Specifications ML21064A2432021-03-0505 March 2021 Email from Z. Cruz to A. Sterdis Acceptance Review_ Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Facility Only Emergency Plan and Emergency Action Level Scheme ML21064A2392021-03-0202 March 2021 E-mail from Z. Cruz to A. Sterdis Acceptance Review - Oyster Creek Nuclear Generating Station - Request for Approval of Independent Spent Fuel Storage Installation Only Physical Security Plan ML20345A1462020-12-0909 December 2020 E-mail - Response to Request for Additional Information: HDI Request for One-Time Exemption from Part 73, Appendix B FOF Requirements ML20335A3112020-11-30030 November 2020 Request for Additional Information Regarding Request for a one-time Exemption from Part 73, Appendix B Requirements for Oyster Creek Nuclear Generating Station ML20332A1472020-11-24024 November 2020 Acceptance Review: November 20 2020 Exemption Request from 10 CFR Part 73 Appendix B Requirements for Oyster Creek ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20279A5082020-10-0505 October 2020 Email to Holtec - Response to Notification of Oyster Creek Onsite Property Insurance Coverage ML20266G4032020-09-22022 September 2020 Acceptance Review Email - Request for Approval of HDI Fleet Decommissioning Quality Assurance Program, Revision 0 ML20134H8742020-05-12012 May 2020 Request for Additional Information Regarding Request for Temporary Exemption from Part 73, Appendix B Requirements ML20133J9182020-05-11011 May 2020 Acceptance Review Email - Oyster Creek Request for Exemption from Part 73 Qualification Requirements ML20120A0252020-04-22022 April 2020 NRR E-mail Capture - (External_Sender) Oyster Creek Sea Turtle Handling and Conservation Recommendation Obligations NRC-2019-0073, Response from NEIMA Local Community Advisory Board Questionnaire 10-30-2019 R Discenza2019-10-30030 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-30-2019 R Discenza ML19344C8022019-10-20020 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-20-2019 a Dressler ML19344C8002019-10-0909 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 W Mcmullin ML19344C7982019-10-0909 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 M Noto ML19344C7992019-10-0909 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 s Feldman ML19344C7932019-10-0909 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 C Bischoff ML19344C7962019-10-0909 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-09-2019 G Adams ML19344C7912019-10-0808 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-08-2019 J Branciforte ML19344C7902019-10-0808 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-08-2019 Anonymous ML19344C7892019-10-0505 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-05-2019 P Dressler ML19263D1222019-09-20020 September 2019 for Your Action Request for Additional Information Hdi Oyster Creek PSDAR ML19214A0452019-08-0202 August 2019 NRC to NMFS, Revised Proposed Action for Oyster Creek Endangered Species Act Section 7 Consultation ML19182A3422019-07-0101 July 2019 Transaction ML19178A0702019-06-26026 June 2019 Email to State of New Jersey - Oyster Creek - Request Comments on Proposed Amendment to Remove Reference to the Oyster Creek Cyber Security Plan and Update License Condition 2.C.(4) in the Renewed Facility License ML19196A3422019-06-20020 June 2019 Email: Courtesy Notice on the Issuance of the Oyster Creek License Transfer and Exemption (Sierra Club) ML19196A3342019-06-20020 June 2019 Email: Courtesy Notice on the Issuance of the Oyster Creek License Transfer and Exemption ML19162A2242019-06-11011 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Oyster Creek ESA Section 7 Consultation NRC-2018-0237, Comment from Paul Dressler of the Concerned Citizens for Lacey Coalition, Regarding the Oyster Creek Nuclear Plant License Transfer Application2019-06-0707 June 2019 Comment from Paul Dressler of the Concerned Citizens for Lacey Coalition, Regarding the Oyster Creek Nuclear Plant License Transfer Application ML19155A1182019-06-0404 June 2019 Incoming E-mail from State of New Jersey on the Oyster Creek Exemption for Reduced Insurances and Use of Decommissioning Trust Fund for Spent Fuel Management and Site Restoration ML19155A1192019-06-0404 June 2019 State of New Jersey Comments - Oyster Creek Conforming Amendment Associated with the Oyster Creek Generating Station License Transfer Application ML19154A0582019-05-31031 May 2019 E-mail Response from State of New Jersey Dated May 31, 2019, Notification-and-Request-Oyster Creek License Transfer Application L-2018-LLM-0002 ML19158A2912019-05-30030 May 2019 NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS ML19158A2772019-05-28028 May 2019 NRR E-mail Capture - Oyster Creek ESA Consultation: Information Requests from NMFS ML19148A4392019-05-24024 May 2019 NMFS to NRC, Requests for Additional Information to Support Oyster Creek Reinitiated Section 7 Consultation 2022-08-23
[Table view] Category:Federal Register Notice
MONTHYEARML22297A1352022-12-20020 December 2022 Part 20 App G Exemption FRN ML21362A4472022-01-26026 January 2022 EA-21-041: Enclosure to January 26, 2022, Letter to Mr. Kelly Trice, President, Holtec NRC Investigation Report & NRC Inspection Confirmatory Order; Issuance. Holtec Decommissioning International, LLC, Oyster Creek Nuclear Generating ML19168A0842019-06-26026 June 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019 ML19109A1602019-06-20020 June 2019 Federal Register Notice Announcing Order Approving Oyster Creek Nuclear Generating Station License Transfer ML19112A3182019-06-20020 June 2019 FRN - Exemption for Hdi to Use Oyster Creek Nuclear Decommissioning Trust Fund Re Request for License Transfer from Exelon ML19129A3642019-06-19019 June 2019 Off-Site Exemption FRN LRC ML19129A3212019-06-19019 June 2019 Oystercreek_Onsite Exemption Frn_Lrc ML19095A8722019-06-13013 June 2019 FRN, Exemption from the Effective Date of Exemptions from Certain Emergency Planning Requirements, Change of Adiabatic Heat-up Calculation ML19112A1122019-06-13013 June 2019 FRN Ea/Fonsi for Exemption for Hdi to Use the Nuclear Decommissioning Trust Fund Re Request for License Transfer from Exelon ML19093A0882019-04-26026 April 2019 FRN, Environmental Assessment and Finding of No Significant Impact Exemption from the Effective Date of Exemptions from Certain Emergency Planning Requirements, Change of Adiabatic Heat-up Calculation ML18229A0072018-12-21021 December 2018 FRN, Exemption from 10 CFR 140.11(a)(4) Related to Primary and Secondary Offsite Liability Insurance NRC-2018-0288, FRN, Exemption from 10 CFR 140.11(a)(4) Related to Primary and Secondary Offsite Liability Insurance2018-12-21021 December 2018 FRN, Exemption from 10 CFR 140.11(a)(4) Related to Primary and Secondary Offsite Liability Insurance ML18228A8502018-12-21021 December 2018 FRN, Request for Exemption from 10 CFR 50.54(w)(1) Related to Onsite Property Damage Insurance ML18323A6902018-12-0404 December 2018 Letter, Reopen the Comment Period - Notice of Consideration of Approval of Transfer of Renewed Facility Operating License and Conforming Amendment, and Opportunity for a Hearing ML18323A6612018-12-0404 December 2018 Federal Register Notice to Reopen the Comment Period - Notice of Application for Order Approving Direct Transfer of Renewed Facility License and Conforming License Amendment ML18295A7442018-10-25025 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/06/18 ML18227A0232018-10-19019 October 2018 FRN, Exemption from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv); Decommissioning Trust Funds Use and Disbursements for Spent Fuel Management and Site Restoration Activities ML18220A9712018-10-16016 October 2018 FRN, Exemption from Portions of 10 CFR 50.47 and Appendix E to 10 CFR 50 to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition (CAC MG0153; EPID L-2017-LLE-0020) NRC-2018-0167, FRN, Exemption from Portions of 10 CFR 50.47 and Appendix E to 10 CFR 50 to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition (CAC MG0153; EPID L-2017-LLE-0020)2018-10-16016 October 2018 FRN, Exemption from Portions of 10 CFR 50.47 and Appendix E to 10 CFR 50 to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition (CAC MG0153; EPID L-2017-LLE-0020) ML18254A0972018-10-16016 October 2018 Letter, Notice of Application for Order Approving Direct Transfer of License and Conforming Amendment to Oyster Creek Environmental Protection LLC and Holtec Decommissioning International LLC ML18254A1312018-10-16016 October 2018 FRN, Notice of Application for Order Approving Direct Transfer of License and Conforming Amendment to Oyster Creek Environmental Protection LLC and Holtec Decommissioning International LLC ML18194A7882018-08-0808 August 2018 Environmental Assessment and Finding of No Significant Impact Related to Request for Exemptions from Certain Emergency Planning Requirements (CAC No. MG0153; EPID L-2017-LLE-0020) NRC-2018-0136, Notice of Issuance of Exemption from Certain 10 CFR Part 50 Requirements Regarding Record Retention2018-06-26026 June 2018 Notice of Issuance of Exemption from Certain 10 CFR Part 50 Requirements Regarding Record Retention ML18122A2902018-06-26026 June 2018 Notice of Issuance of Exemption from Certain 10 CFR Part 50 Requirements Regarding Record Retention ML18149A0722018-06-0505 June 2018 Letter, Notice of Receipt, Public Meeting, and Request for Comment on Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate ML18149A0942018-06-0505 June 2018 FRN, Notice of Receipt, Public Meeting, Request for Comment, Post-Shutdown Decommissioning Activities Report NRC-2018-0058, FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304)2018-03-16016 March 2018 FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304) ML18047A4302018-03-16016 March 2018 FRN, Withdrawal of Request to Revise License Condition to Implement BWRVIP-18, Revision 2-A, BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (CAC MG0180; EPID L-2017-LLA-0304) ML16257A4962017-01-23023 January 2017 FRN: Clinton, Quad Cities, & Oyster Creek - FRN Exemption from the Requirements of 10 CFR Part 73, Sections 55(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather (CAC Nos. MF8275 NRC-2017-0014, FRN: Clinton, Quad Cities, & Oyster Creek - FRN Exemption from the Requirements of 10 CFR Part 73, Sections 55(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather (CAC Nos. MF2017-01-23023 January 2017 FRN: Clinton, Quad Cities, & Oyster Creek - FRN Exemption from the Requirements of 10 CFR Part 73, Sections 55(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather (CAC Nos. MF8275 ML16257A5172016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 20162016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML14335A6482015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6302015-01-15015 January 2015 G20110262 - Final Response to Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units NRC-2015-0009, G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units2015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units NRC-2014-0917, Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 20142014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 ML14247A1542014-09-0505 September 2014 Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 16, 2014 ML14177A6452014-06-27027 June 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations ML14099A2172014-04-28028 April 2014 FRN on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI NRC-2013-0288, Request for Exemption from Emergency Preparedness Title 10 of the Code of Federal Regulations Part 50, Appendix E2013-12-30030 December 2013 Request for Exemption from Emergency Preparedness Title 10 of the Code of Federal Regulations Part 50, Appendix E ML13291A0852013-12-30030 December 2013 Request for Exemption from Emergency Preparedness Title 10 of the Code of Federal Regulations Part 50, Appendix E ML13290A6932013-12-30030 December 2013 Request for Exemption from Emergency Preparedness Title 10 of the Code of Federal Regulations Part 50, Appendix E ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML12250A8462012-11-0909 November 2012 Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements NRC-2010-0200, Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements2012-11-0909 November 2012 Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements NRC-2009-0320, Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements2012-10-15015 October 2012 Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements ML12250A8002012-10-15015 October 2012 Correction to Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R Requirements 2022-12-20
[Table view] |
Text
Richard Conte \ 4 J 3 *\/ 2.
r From: Richard Conte Sent: Tuesday, April 22, 2008 7:23 AM To: Neil Sheehan; Darrell Roberts; Marsha Gamberoni
Subject:
FW: RIS and FRN Attachments: C__WINDOWSShelINew_NRCADAMSDesktopCacheML0809502351.pdf; ML0810805620.doc FYI Richard J. Conte Chief, Engineering Branch No. 1, DRS, Reg. I Xb)(6)
Off, 610-337-5183 From: Marjorie McLaughlin Sent: Tuesday, April 22, 2008 7:11 AM To: Ronald Bellamy; Richard Conte
Subject:
FW: RIS and FRN FYI Marjorie McLaughlin NRC Region I State Liaison Officer 475 Allendale Road King of Prussia, PA 19406 Phone: 610-337-5240 Fax: 610-337-5349 From: Louise Lund Sent: Monday, April 21, 2008 5:47 PM To: Eugene Dacus; Tom Blount; Samson Lee; Nell Sheehan; Donnie Ashley; Mary Baty; Marjorie McLaughlin
Subject:
FW: RIS and FRN Attached is the RIS for comment and the associated FRN on the fatigue methodology issue ... the FRN is publicly available in ADAMS (I just checked), and contains the text of the RIS for comment From: Martin Murphy Sent: Monday, April 21, 2008 5:30 PM To: Louise Lund; Edward Williamson; Bo Pham
Subject:
RIS and FRN the RIS and FRN can be found with the following ADAMS accession #s: ML080950235 and ML081080562 or attached Umtancordace wt"the FreeftheF 1 tIo=
.Act, exempinsl S01 , --
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[7590-01 -P1 NUCLEAR REGULATORY COMMISSION Proposed Generic Communication FATIGUE ANALYSIS OF NUCLEAR POWER PLANT COMPONENTS AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of opportunity for public comment.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is proposing to issue a regulatory issue summary (RIS) to inform licensees of an analysis methodology used to demonstrate compliance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) fatigue acceptance criteria that could be nonconservative if not correctly applied.
This Federal Register notice is available through the NRC's Agencywide Documents Access and Management System (ADAMS) under accession number ML081080652.
DATES: Comment period expires [60 days after FRN is published]. Comments submitted after this date will be considered if it is practical to do so, but assurance of consideration cannot be given except for comments received on or before this date.
ADDRESSEES: Submit written comments to the Chief, Rulemaking, Directives and Editing Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Mail Stop T6-D59, Washington, DC 20555-0001, and cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to NRC Headquarters, 11545 Rockville Pike (Room T-6D59), Rockville, Maryland, between 7:30 am and 4:15 pm on Federal workdays.
FOR FURTHER INFORMATION, CONTACT: John R. Fair at 301-415-2759 or by email at John. Faira-nrc.pov
SUPPLEMENTARY INFORMATION:
NRC REGULATORY ISSUE
SUMMARY
2008-XX FATIGUE ANALYSIS OF NUCLEAR POWER PLANT COMPONENTS ADDRESSEES All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
INTENT The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to inform licensees of an analysis methodology used to demonstrate compliance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) fatigue acceptance criteria that could be nonconservative if not correctly applied.
BACKGROUND INFORMATION Title 10 of the Code of FederalRegulations (10 CFR) Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," requires that applicants for license renewal perform an evaluation of time-limited aging analyses relevant to structures, systems, and components within the scope of license renewal. The fatigue analysis of the reactor coolant pressure boundary components is an issue that involves time-limited assumptions. In addition, the staff has provided guidance in NUREG-1800, Rev. 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," issued September 2005.
NUREG-1 800, Rev. 1, specifies that the effects of the reactor water environment on fatigue life be evaluated for a sample of components to provide assurance that cracking because of fatigue will not occur during the period of extended operation. Since the reactor water environment has a significant impact on the fatigue life of components, many license renewal applicants have performed supplemental detailed analyses to demonstrate acceptable fatigue life for these components.
10 CFR 50.55a, "Codes and Standards," specifies the ASME Code requirements for operating reactors. Some operating facilities may have performed supplemental detailed analysis of components because of new loading conditions identified after the plant began operation.
SUMMARY
OF ISSUE The staff identified a concern regarding the methodology used by some license renewal applicants to demonstrate the ability of nuclear power plant components to withstand the cyclic loads associated with plant transient operations for the period of extended operation. This particular analysis methodology involves the use of the Green's function to calculate the fatigue usage during plant transient operations such as startups and shutdowns.
The Green's function approach involves performing a detailed stress analysis of a component to calculate its response to a step change in temperature. This detailed analysis is used to establish an influence function, which is subsequently used to calculate the stresses caused by the actual plant temperature transients. This methodology has been used to perform fatigue calculations and as input for on-line fatigue monitoring programs. The Green's function methodology is not in question. The concern involves a simplified input for applying the Green's function in which only one value of stress is used for the evaluation of the actual plant transients. The detailed stress analysis requires consideration of six stress components, as discussed in ASME Code,Section III, Subsection NB, Subarticle NB-3200. Simplification of the analysis to consider only one value of the stress may provide acceptable results for some applications ; however, it also requires a great deal of judgment by the analyst to ensure that the simplification still provides a conservative result.
The staff has requested that recent license renewal applicants that have used this simplified Green's function methodology perform confirmatory analyses to demonstrate that the simplified Green's function analyses provide acceptable results. The confirmatory analyses retain all six stress components. To date, the confirmatory analysis of one component, a boiling-water
reactor feedwater nozzle, indicated that the simplified input for the Green's function did not produce conservative results in the nozzle bore area when compared to the detailed analysis.
However, the confirmatory analysis still demonstrated that the nozzle had acceptable fatigue usage.
Licensees may have also used the simplified Green's function methodology in operating plant fatigue evaluations for the current license term. For plants with renewed licenses, the staff is considering additional regulatory actions if the simplified Green's function methodology was used.
BACKFIT DISCUSSION This RIS informs addressees of a potential nonconservative calculation methodology and reminds them that the ASME Code fatigue analysis should be performed properly. For license renewal, metal fatigue is evaluated as a time-limited aging analysis in accordance with 10 CFR 54.21(c). The associated staff review guidance appears in Section 4.3, "Metal Fatigue Analysis," of NUREG-1 800, Rev. 1. For operating reactors, the ASME Code requirements appear in 10 CFR 50.55a. This RIS does not impose a new or different regulatory staff position.
It requires no action or written response and, therefore, is not a backfit under 10 CFR 50.109, "Backfitting." Consequently, the NRC staff did not perform a backfit analysis.
FEDERAL REGISTER NOTIFICATION A notice of opportunity for public comment on this RIS was not published in the Federal Register because the RIS is informational.
CONGRESSIONAL REVIEW ACT The NRC has determined that this RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. 801-808) and; therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT This RIS does not contain information collection requirements that are subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
CONTACT Please direct any questions about this matter to the technical contacts listed below.
Michael J. Case, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Technical Contacts: Kenneth C. Chang, NRR John R. Fair, NRR 301-415-1913 301-415-2759 E-mail: Kenneth.Chan-a)nrc.gov E-mail: John.Fairanrc.gov Note: The NRC' s generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
END OF DRAFT REGULATORY ISSUE
SUMMARY
Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.,ov/NRC/ADAMS/index.html. If you do not have access to ADAMS or if you have problems in accessing the documents in ADAMS, contact the NRC Public Document Room (PDR) reference staff at 1-800-397-4209 or 301-415-4737 or by e-mail to pdr(Cnrc.,ov.
Dated at Rockville, Maryland, this 15th day of April 2008.
FOR THE NUCLEAR REGULATORY COMMISSION IRA/
Martin C. Murphy, Chief Generic Communications Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION
'OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001 April 11, 2008 NRC REGULATORY ISSUE
SUMMARY
2008-10 FATIGUE ANALYSIS OF NUCLEAR POWER PLANT COMPONENTS ADDRESSEES All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
INTENT The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to inform licensees of an analysis methodology used to demonstrate compliance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) fatigue acceptance criteria that could be nonconservative if not correctly applied.
BACKGROUND INFORMATION Title 10 of the Code of FederalRegulations (10 CFR) Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," requires that applicants for license renewal perform an evaluation of time-limited aging analyses relevant to structures, systems, and components within the scope of license renewal. The fatigue analysis of the reactor coolant pressure boundary components is an issue that involves time-limited assumptions. In addition, the staff has provided guidance in NUREG-1800, Rev. 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," issued September 2005.
NUREG-1 800, Rev. 1, specifies that the effects of the reactor water environment on fatigue life be evaluated for a sample of components to provide assurance that cracking because of fatigue will not occur during the period of extended operation. Since the reactor water environment has a significant impact on the fatigue life of components, many license renewal applicants have performed supplemental detailed analyses to demonstrate acceptable fatigue life for these components.
10 CFR 50.55a, "Codes and Standards," specifies the ASME Code requirements for operating reactors. Some operating facilities may have performed supplemental detailed analysis of components because of new loading conditions identified after the plant began operation.
ML080950236
RIS 2008-10 Page 2 of 4
SUMMARY
OF ISSUE The staff identified a concern regarding the methodology used by some license renewal applicants to demonstrate the ability of nuclear power plant components to withstand the cyclic loads associated with plant transient operations for the period of extended operation. This particular analysis methodology involves the use of the Green's function to calculate the fatigue usage during plant transient operations such as startups and shutdowns.
The Green's function approach involves performing a detailed stress analysis of a component to calculate its response to a step change in temperature. This detailed analysis is used to establish an influence function, which is subsequently used to calculate the stresses caused by the actual plant temperature transients. This methodology has been used to perform fatigue calculations and as input for on-line fatigue monitoring programs. The Green's function methodology is not in question. The concern involves a simplified input for applying the Green's function in which only one value of stress is used for the evaluation of the actual plant transients.
The detailed stress analysis requires consideration of six stress components, as discussed in ASME Code,Section III, Subsection NB, Subarticle NB-3200. Simplification of the analysis to consider only one value of the stress may provide acceptable results for some applications; however, it also requires a great deal of judgment by the analyst to ensure that the simplification still provides a conservative result.
The staff has requested that recent license renewal applicants that have used this simplified Green's function methodology perform confirmatory analyses to demonstrate that the simplified Green's function analyses provide acceptable results. The confirmatory analyses retain all six stress components. To date, the confirmatory analysis of one component, a boiling-water reactor feedwater nozzle, indicated that the simplified input for the Green's function did not produce conservative results in the nozzle bore area when compared to the detailed analysis.
However, the confirmatory analysis still demonstrated that the nozzle had acceptable fatigue usage.
Licensees may have also used the simplified Green's function methodology in operating plant fatigue evaluations for the current license term. For plants with renewed licenses, the staff is considering additional regulatory actions if the simplified Green's function methodology was used.
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RIS 2008-10 Page 3 of 4 BACKFIT DISCUSSION This RIS informs addressees of a potential nonconservative calculation methodology and reminds them that the ASME Code fatigue analysis should be performed properly. For license renewal, metal fatigue is evaluated as a time-limited aging analysis in accordance with 10 CFR 54.21(c). The associated staff review guidance appears in Section 4.3, "Metal Fatigue Analysis," of NUREG-1 800, Rev. 1. For operating reactors, the ASME Code requirements appear in 10 CFR 50.55a. This RIS does not impose a new or different regulatory staff position.
It requires no action or written response and, therefore, is not a backfit under 10 CFR 50.109, "Backfitting." Consequently, the NRC staff did not perform a backfit analysis.
FEDERAL REGISTER NOTIFICATION A notice of opportunity for public comment on this RIS was not published in the FederalRegister because the RIS is informational.
CONGRESSIONAL REVIEW ACT The NRC has determined that this"RIS is not a rule as designated by the Congressional Review Act (5 U.S.C. §§801-808) and; therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT This RIS does not contain information collection requirements that are subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
RIS 2008-10 Page 4 of 4 CONTACT Please direct any questions about this matter to the technical contacts listed below.
IRA!
Michael J. Case, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Technical Contacts: Kenneth C. Chang, NRR John R. Fair, NRR 301-415-1913 301-415-2759 E-mail: kxc2(.Nrc.gov E-mail: irffnrc.Qov Note: The NRC's generic communications may be found on the NRC public Web site, http://www.nrc.,qov, under Electronic Reading Room/Document Collections.
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RIS 2008-10 Page 4 of 4 CONTACT Please direct any questions about this matter to the technical contacts listed below.
IRA!
Michael J. Case, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Technical Contacts: Kenneth C. Chang, NRR John R. Fair, NRR 301-415-1913 301-415-2759 E-mail: kxc2(,Nrc.qov E-mail: irft&nrc.gov Note: NRC's generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
DISTRIBUTION: RIS R/F NRRADES Distribution NRRADR ADAMS ACCESSION NO.: ML080950235 OFFICE DE/NRR/EMCB BC/DLR/RER1 TECH EDITOR BC/DE/EMCB AD/NRR/DLR DD/NRR/DE NAME JFair KChang JMedoff for HChang KManoly SLee PHiland DATE 4/7/08 4/7/08 4/08/08 4/7/08 4/8/08 4/09/08 OFFICE DD/NRR/DORL BC/DE/EMBI BC/DE/EMB2 OE OGC/NLO OGC/CRA NAME CHaney AHsia JDixon-Herrity SMagruder EWilliams SHamrick DATE 4/10/08 4/10/08 4/10/08 4/09/08 4/11/08 OFFICE PMDA/IMT OIS LA/DPR/PGCB DPR/PGCB BC/DPR/PGCB D/DPR NAME LHill TDonnell CHawes AMarkley MMurphy MCase DATE 4/09/08 4/10/08 4/11/08 4/11/08 4/11/08 4/11/08 OFFICIAL RECORD COPY