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Category:Memoranda
MONTHYEARML23297A0532023-11-27027 November 2023 Restart Panel Charter ML20231A2202020-08-17017 August 2020 Summary of Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML16182A5142016-06-30030 June 2016 Summary of the June 23, 2016, Public Meeting Regarding Palisades Nuclear Plant ML16138A1812016-05-16016 May 2016 EA-15-039 Palisades Federal Register Memo and Order ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15127A5692015-05-0707 May 2015 Final Task Interface Agreement-Regulatory Position on Design Life of Safety-Related Structures, Systems, & Components Related to Unresolved Items at D. C. Cook, Monticello, & Palisades (TIA 2014-01) ML15054A3962015-04-0606 April 2015 Federal Register Notice on Final Director'S Decision on 10 CFR 2.206 Petition from Mr. Michael Mulligan at Palisades Nuclear Plant ML13261A2282013-09-23023 September 2013 Notice of Forthcoming Conference Call with Entergy Nuclear Operations, Inc., on Palisades Equivalent Margins Analysis ML13042A2932013-02-11011 February 2013 Meeting Summary with NRC to Discuss Nrc'S Perspectives on Leaks, and the Regulatory Requirements That Apply on the Repair of Such Leaks ML12305A4512012-12-0101 December 2012 Branch Chief Reassignment ML12306A3672012-11-0808 November 2012 Approval Memo Palisades Request for Deviation to the Reactor Oversight Process Action Matrix ML12305A5472012-11-0101 November 2012 Pre-application Meeting Notice Palisades ME9852 ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML1111107222011-05-0303 May 2011 Final Response to TIA 2011-006, Palisades Nuclear Plant Reactor Vessel Bare Metal Head Exam - Compliance with Code Case N-729-1 ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1012601282010-06-29029 June 2010 TIA Response ML1015506112010-06-0909 June 2010 Notice of Pre-Application Meeting with Entergy Nuclear Operations Inc. to Discuss Pressurized Thermal Shock Analysis ML1011604932010-04-27027 April 2010 05/12-13/2010 Notice of Meeting with Energy Nuclear Operations LLC (ENO) Regarding Response to Generic Letter 2004-02 for Palisades Nuclear Plant ML1002101862010-01-20020 January 2010 Memo to Christine. A. Lipa Response to Region III Technical Assistance Request-Palisades Plant Multi-Assembly Sealed Basket No. 4 (Msb #4) - Weld Flaw Analysis ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML0925400322009-09-17017 September 2009 Final Task Interface Agreement - Re-Evaluation of Implementation of Limiting Condition for Operation 3.0.4a, Mode Change Limitations, at Palisades Nuclear Plant (TIA2009-005) ML0912504972009-05-15015 May 2009 Summary of Telephone Conference Call Held on April 23, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 Transition Activities ML0909601482009-04-17017 April 2009 (Pnp) - Summary of Telephone Conference Call Held on March 17, 2009, Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 ... ML0905507692009-02-25025 February 2009 Notice of Pre-Application Meeting with Palisades to Discuss Spent Fuel Criticality Amendment for Palisades Nuclear Plant ML0835902692008-12-17017 December 2008 Memo 12/17/2008 Re 2006 Palisades Proposed Examination Not Available in ADAMS ML0831908362008-12-15015 December 2008 Summary of Telephone Conference Call Held on November 3, 2008, Between the NRC and Entergy Operations, Inc. Concerning Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10 CFR 50.48(C), Nat ML0833604952008-12-11011 December 2008 LIC-109 Acceptance Review for License Amendment Request for Spent Fuel Pool Region I Criticality for Palisades ML0834301532008-12-0404 December 2008 Canceled - 12/16/2008 Meeting Notice, Meeting with Entergy Nuclear Operations, Inc. (Eno), Palisades Nuclear Plant ML0823503502008-08-20020 August 2008 Memo to Christine Lipa Request for Additional Information; Region III TAR Requesting Assessment of Palisades Weld Flaw Analysis for Loaded Spend Fuel Cask Msb No. 4 (TAC A10126) ML0813000962008-05-0909 May 2008 TIA Regarding LCO 3.0.4a ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0708805192007-04-0909 April 2007 Memo J Cameron, Request for Additional Information, Region III, TAR Requesting Assessment of Palisades Weld Flaw Analysis for Loaded Spent Fuel Cask Msb No. 4, TAC No. A10126 (Dsfst 20070005) ML0707207672007-03-20020 March 2007 Encl 1 - Staff'S Response to Petitioner'S Comments to 03/20/07 - Ltr T Lodge, Counsel for Petitioners, Issuance of Director'S Decision DD-07-02 Under 10 CFR 2.206 - Palisades Nuclear Plant, Docket Nos. 72-7, 50-255 ML0706101422007-03-0909 March 2007 February 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 Cfr), Section 2.206 ML0704001932007-02-22022 February 2007 Response Memo to Task Interface Agreement 2006-004 ML0701001592007-01-29029 January 2007 December 2006 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ML0700402152007-01-22022 January 2007 Safety Evaluation by the Office of Nuclear Reactor Regulation Re Direct Transfer of Licenses from Consumers Energy Company to Entergy Nuclear Palisades, LLC and Entergy Nuclear Operations, Inc ML0635404462007-01-11011 January 2007 Memo to Commission Fm Reyes Renewal of Full-Power Operating License for the Palisades Nuclear Plant ML0634502502006-12-19019 December 2006 November 2006 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ML0617805592006-07-10010 July 2006 Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0618102812006-06-29029 June 2006 Memo 06/29/06 Palisades DRS Input to DRP IR 06-004 ML0607401012006-03-14014 March 2006 04/05/06 - Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement (Dseis) for License Renewal at Palisades Nuclear Plant (Palisades) ML0602502942006-01-25025 January 2006 Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML0601800802006-01-18018 January 2006 Notice of Forthcoming Meeting with Palisades Nuclear Plant and Nuclear Management Company (NMC) to Discuss Removing Trisodium Phosphate from the Containment at Palisades Nuclear Plant for One Cycle ML0611102682005-11-0707 November 2005 Memorandum to Marc Dapas, Riii from Edwin Hacket, NRR Re Response to Task Interface Agreement 2005-06, Regarding Licensing Basis for, and Seismic Design of, the Palisades Independent Spent Fuel Storage Installation (ISFSI) ML0530404252005-10-28028 October 2005 Summary of Telephone Conference Call Held on September 7, 2005, Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Management Company, LLC, Concerning Draft Request for Additional Information Pertaining to the Palisades Nuclea ML0520805482005-07-27027 July 2005 Forthcoming Exit Meeting with Nuclear Management Company to Present Results of the Palisades Nuclear Plant Aging Management Program and Aging Management Review Audits ML0611102662005-05-12012 May 2005 Memorandum to James Lyons, NRR, from Marc Dapas, Riii Re Request for Technical Assistance-Licensing Basis for, and Seismic Design of, the Palisades Independent Spent Fuel Storage Installation (ISFSI) Supplemental Information ML0511203112005-05-11011 May 2005 Transmittal of Summaries of Final ASP Analyses 2023-11-27
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information ML23055A1542023-02-24024 February 2023 Attachment: Request for Additional Information on the Palisades PSDAR ML22292A2582022-10-31031 October 2022 PDEP-EAL Amendment RAI ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21274A4172021-10-0505 October 2021 Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information Inspection Report 05000255/2021004 ML21028A4092021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv) ML21028A0552021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20133K0562020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML19357A2752019-12-23023 December 2019 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011 ML19226A2932019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant ML19226A2922019-08-0505 August 2019 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425 ML19122A4852019-04-29029 April 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications ML19009A5392019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML19009A5382018-12-12012 December 2018 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML18337A1382018-11-30030 November 2018 NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7 ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18309A1342018-11-0808 November 2018 Supplemental Information Needed for Acceptance or Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-425, Revision 3 ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18081A2962018-03-22022 March 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305) ML18059A8202018-02-28028 February 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML17335A1042017-11-30030 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266) ML17118A3342017-04-18018 April 2017 E-Mailed Request for Information Dated 04/18/2017 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part B Items (Exf) ML17118A3312017-04-18018 April 2017 E-Mailed Request for Information Dated 04/18/17 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part a Items ML17072A2752017-03-10010 March 2017 NRR E-mail Capture - Palisades Nuclear Plant - Final Request for Additional Information Regarding Relief Request No. RR 4-25 ML16238A0302016-08-29029 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Control Rod Drive Exercise Surveillance ML16130A0762016-05-11011 May 2016 Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternative Repair Criterion on the Steam Generator Tubes ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15258A2432015-09-0101 September 2015 NRC Supplement to NRC Letter - Notification of NRC Inspection and Request for Information Dated May 1, 2015 - Palisades Nuclear Plant ML15149A2462015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15072A2542015-03-19019 March 2015 Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company ML15022A1382015-01-22022 January 2015 E-Mail - Palisades Request for Information ML15016A1842015-01-20020 January 2015 Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a ML15012A3052015-01-15015 January 2015 Request for Additional Information Regarding the License Amendment Request for an Equivalent Margin Analysis Completed in Accordance with 10 CFR 50, Appendix G ML14318A4002014-12-17017 December 2014 Vermont Yankee Nuclear and Big Rock Point - Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company (Tac Nos. MF3218 - MF3221) ML14157A3642014-06-0505 June 2014 CDBI Request for Information ML13353A0422013-12-16016 December 2013 NRR E-mail Capture - Request for Additional Information - Palisades - Proposed Revision to Palisades Site Emergency Plan (SEP) Emergency Response Organization (ERO) MF2321 ML13312A4232013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report ML13051A7772013-02-19019 February 2013 Request for Additional Information, 2012 SG Inspection Report ML12314A4222012-11-0808 November 2012 ME8074 - Request for Additional Information Regarding Replacement of Spent Fuel Pool Region I Storage Racks ML12278A3862012-10-0404 October 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs ML12206A4042012-07-24024 July 2012 Request for Additional Information (Revised) - Palisades - SFP Rerack LAR - ME8074 ML12206A3322012-07-19019 July 2012 E-mail Combined Request for Additional Information for Several Branches of NRR for the Submittal on Palisades re-sack LAR ML12121A7032012-04-27027 April 2012 Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination - ME8492 ML1209604492012-04-0505 April 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Request for Additional Information, Revise Quality Assurance Program Manual and Staff Qualification Technical Specificat ML12068A3882012-04-0202 April 2012 Request for Additional Information Regarding License Renewal Commitment to Submit Alloy 600 Program ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic 2023-02-24
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April 9, 2007 MEMORANDUM TO: Jamnes L. Cameron, Branch Chief Division of Nuclear Material and Safety, Region III FROM: Gordon Bjorkman, Branch Chief /RA/
Spent Fuel Storage and Transportation Division, NMSS
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION; REGION III TAR REQUESTING ASSESSMENT OF PALISADES WELD FLAW ANALYSIS FOR LOADED SPENT FUEL CASK MSB NO. 4 TAC No. A10126 The Division of Spent Fuel Storage and Transportation (SFST) staff finds that additional information is required in order to complete the ongoing TAR for assessing the adequacy of the Palisades weld flaw analysis for loaded spent fuel cask MSB No. 4.
During our review of the fatigue crack growth calculation, it was noted that one input variable was fixed at a possibly non-conservative value. As a consequence of this assumption, the associated fatigue crack growth rates could also be non-conservative. The result could thus under-predict the eventual flaw size, possibly by a very significant margin. Consequently, attached is a request for additional information in regards to this calculation.
Please contact Jerry Chuang, Senior Structural Engineer, of my staff at 301-415-8586, if you require clarification of this issue.
Enclosure:
Request for Additional Information
April 9, 2007 MEMORANDUM TO: Jamnes L. Cameron, Branch Chief Division of Nuclear Material and Safety, Region III FROM: Gordon Bjorkman, Branch Chief /RA/
Spent Fuel Storage and Transportation Division, NMSS
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION; REGION III TAR REQUESTING ASSESSMENT OF PALISADES WELD FLAW ANALYSIS FOR LOADED SPENT FUEL CASK MSB NO. 4 TAC No. A10126 The Division of Spent Fuel Storage and Transportation (SFST) staff finds that additional information is required in order to complete the ongoing TAR for assessing the adequacy of the Palisades weld flaw analysis for loaded spent fuel cask MSB No. 4.
During our review of the fatigue crack growth calculation, it was noted that one input variable was fixed at a possibly non-conservative value. As a consequence of this assumption, the associated fatigue crack growth rates could also be non-conservative. The result could thus under-predict the eventual flaw size, possibly by a very significant margin. Consequently, attached is a request for additional information in regards to this calculation.
Please contact Jerry Chuang, Senior Structural Engineer, of my staff at 301-415-8586, if you require clarification of this issue.
Enclosure:
Request for Additional Information DISTRIBUTION:
NMSS r/f SFST r/f JChuang MDebose GHornseth BWhite MGryglak ML070880519 OFC: SFST SFST SFST SFST NAME: JChuang MDebose GHornseth GBjorkman DATE: 04/05/2007 04/05/2007 04/05/2007 04/09/2007 OFFICIAL AGENCY RECORD
REQUEST FOR ADDITIONAL INFORMATION Palisades Weld Flaw Analysis for Loaded Spent Fuel Cask MSB No. 4 Model No. VSC-24
Reference:
Licensee supplied calculation EA-FC-864-50, Appendix 2 to MSB No. 4 Structure Integrity Assessment, page 18.
Issue:
The fatigue crack growth analysis set a fixed value of R at 0.9 in a fatigue crack growth law provided by ASME Section XI, Article A-4000 for all stress cycles. Provide fatigue crack growth data for a surface crack in ASTM SA-516, Grade 70 ferritic steel for the range of 0.9 < R < 1.0 and re-analyze the case using the data to demonstrate that the final crack length determined by the referenced calculation is conservative.
Background:
The Division of Spent Fuel and Storage and Transportation (SFST) staff reviewed the fatigue crack growth calculation for an initial semi-circular surface crack present in the MSB No. 4, considering 50 years of cyclic service conditions. The calculations assumed all loading cycles had a constant R value of 0.9. However, due to the level of residual stresses imposed in the assumptions, it appears to the staff that most of the loading cycles are in the range of 0.9 < R < 1.0.
It is well known that higher values of R yield a larger crack growth rate per cycle for a fixed stress amplitude. Thus, fatigue crack growth data for a semi-circular surface crack in ASTM SA-516, Grade 70 ferritic steel for this R-range (0.9 < R < 1.0), in air, at room temperature are needed. Using such data, a new analysis should be performed to show that the final calculated crack sizes at the end of a 50 year service life remain stable.
Absent such data and re-analysis, the SFST staff are unable to determine if the flaw propagation after 50 years of cyclic loads would remain stable, thus assuring the integrity of the cask.