Letter Sequence RAI |
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TAC:MD2125, Steam Generator Tube Integrity (Approved, Closed) |
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MONTHYEARML0633101752006-12-15015 December 2006 Request for Additional Information, Related to the Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet Project stage: RAI ML0706400582007-02-27027 February 2007 Response to Request for Additional Information Regarding Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet Project stage: Response to RAI ML0710303302007-04-10010 April 2007 Response to Request for Additional Information Regarding Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet Project stage: Response to RAI ML0714202162007-05-31031 May 2007 Issuance of Amendment Tubesheet Inspection Depth for Steam Generator Tube Inspections Project stage: Approval ML0714501052007-05-31031 May 2007 Technical Specifications Pages Re Programs and Manuals for Steam Generator Project stage: Request ML0713702092007-05-31031 May 2007 Request for Withholding Information from Public Disclosure from Response to Request for Addition Information for License Amend. Request Regarding Tubesheet Inspection Depth for Steam Generator Tube Inspections Project stage: Withholding Request Acceptance ML0713701452007-05-31031 May 2007 Request for Withholding Information from Public Disclosure from Application for License Amendment Request Regarding Tubesheet Inspection Depth for Steam Generator Tube Inspection Project stage: Withholding Request Acceptance 2007-02-27
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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[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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De cembe r 15 , 20 06 M r. P aul A. H arde n Si te V ic e P resi den t Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3-95 30 S U B JE C T:
P A L IS A D E S P L A N T - R E QU E S T F OR A D D ITIO N A L I N F OR M A TION R E L A TE D TO TH E P R OP OS E D C* L IC E N S E A M E N D M E N T R E QU E S T F OR STEA M GEN ER ATOR TUB E RE PA IR IN THE TUBE SH EE T (TAC N O. M D2 125)De ar M r. H arde n: Yo ur l etter of M ay 30 , 20 06, sub mitted an ap pl ic ati on to c han ge the P al is ade s N ucl ear Pl ant (Palisades) tec hnical specif ications r elated t o steam gen erat or tu be repair. Th e chang es w ould re v i se t h e r e p a i r cr i te ri a for t h e p o rt i o n o f th e t u b e s w i th i n t h e h o t-l e g re gi o n o f th e t u b e sh e e t.W e a re re v ie w in g y our requests , an d fin d th at a ddi tio nal i nformatio n i s n eed ed as sho w n i n th e e n cl o se d r e que st for a d d i ti o n a l i n form a ti o n (R A I). I d i sc u ss e d t h e e n cl o se d R A I w i th M s. A my Ha z el hoff of y our organi z ati on on De cembe r 13 , 20 06, and sh e a greed to re spo nd w ith in 60 day s o f rec ei pt o f thi s R AI. P le ase co ntac t me at (3 01) 415-142 3 i f y ou hav e que sti ons.
Sin ce r ely,/RA/
M ahe sh L. C haw la , P roject M ana ger P ro je ct D i re ct o ra te I II D i v i si o n o f Li ce n si n g P ro je ct M a n a gem e n t Of f ic e o f N ucl ear Re acto r R egul ati on Do cket No. 50-255 E n cl o su re: RAI c c w/e n c l: S e e n e x t p a ge M r. P aul A. H arde n De cembe r 15 , 20 06 Si te V ic e P resi den t Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3-95 30 S U B JE C T:
P A L IS A D E S P L A N T - R E QU E S T F OR A D D ITIO N A L I N F OR M A TION R E L A TE D TO TH E P R OP OS E D C* L IC E N S E A M E N D M E N T R E QU E S T F OR STEA M GEN ER ATOR TUB E RE PA IR IN THE TUBE SH EE T (TAC N O. M D2 125)De ar M r. H arde n: Yo ur l etter of M ay 30 , 20 06, sub mitted an ap pl ic ati on to c han ge the P al is ade s N ucl ear Pl ant (Palisades) tec hnical specif ications r elated t o steam gen erat or tu be repair. Th e chang es w ould re v i se t h e r e p a i r cr i te ri a for t h e p o rt i o n o f th e t u b e s w i th i n t h e h o t-l e g re gi o n o f th e t u b e sh e e t.W e a re re v ie w in g y our requests , an d fin d th at a ddi tio nal i nformatio n i s n eed ed as sho w n i n th e e n cl o se d r e que st for a d d i ti o n a l i n form a ti o n (R A I). I d i sc u ss e d t h e e n cl o se d R A I w i th M s. A my Ha z el hoff of y our organi z ati on on De cembe r 13 , 20 06, and sh e a greed to re spo nd w ith in 60 day s o f rec ei pt o f thi s R AI. P le ase co ntac t me at (3 01) 415-142 3 i f y ou hav e que sti ons.
Sin ce r ely,/RA/
M ahe sh L. C haw la , P roject M ana ger P ro je ct D i re ct o ra te I II D i v i si o n o f Li ce n si n g P ro je ct M a n a gem e n t Of f ic e o f N ucl ear Re acto r R egul ati on Do cket No. 50-255 E n cl o su re: RAI c c w/e n c l: S e e n e x t p a ge D IS TR IB U TION PU BL IC Ri dsOgcRp Ri dsN rrDo rlL pl 3-1 Ri dsN rrDo rlD prRidsRg n3M ailCenter LPL3-1 r/f RidsAcrs AcnwM ailCenter RidsNrr PM M Chaw la Ri dsN rrLA THarri s GM akar AD AM S Acc ess io n N umbe r: M L06 331 017 5 OF FICE LPL3-1/PM LPL3-1/LA LPL3-1/BC NA M E M Ch aw la THarri s LR aghav an DA TE 12/1 5/06 12/1 5/06 12/1 5/06OF FICI AL RECORD COPY Pa li sad es Pl ant cc: Ro bert A. Fen ech , S eni or V ic e P resi den t Nu cl ear, Fos si l, and H y dro Operati ons Co nsu mers E nergy C ompa ny 194 5 P arna ll R d.Jac kson, M I 4 920 1 A ru n a s T. U d ry s, E squ i re Co nsu mers E nergy C ompa ny 1 En er g y Plaza Jac kson, M I 4 920 1 R e gi o n a l A d mi n i st ra to r, R e gi o n I II U.S. N ucl ear Re gula tory C ommis si on Su ite 21 0 244 3 W arren v il le R oad Li sl e, IL 605 32-4 351 Su perv is or Covert T ow nship P. O. Bo x 35 Co v ert, M I 4 904 3 Of f ic e o f the Gov erno r P. O. Bo x 30 013 Lan si ng, M I 4 890 9 U.S. N ucl ear Re gula tory C ommis si on Re si den t Ins pec tor's Of f ic e Pa li sad es Pl ant 277 82 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 M i ch i gan D e p a rt me n t o f E n v i ro n me n ta l Qu a l i ty W aste an d H az ardo us M ateri al s D iv is io n Ha z ardo us W aste an d R adi ol ogica l Pro tecti on Se cti on Nuclear Facilities Unit C o n st i tu ti o n H a l l , L o w e r-L e v e l N o rt h 525 W est Al le gan S treet P.O. B ox 30 241 Lan si ng, M I 4 890 9-77 41 M ic hi gan D epa rtment o f A ttorne y Gen eral Sp eci al Li tigati on Di v is io n 5 2 5 W e st Ot ta w a S t.Si x th F lo or, G. M enn en W il li ams B ui ld in g Lan si ng, M I 4 891 3 M ic hae l B. Se ll man Pre si den t an d C hi ef Ex ecu tiv e Off ic er Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, M I 5 401 6 Jo n a th a n R o goff, E squ i re V i ce P re si d e n t, C o u n se l & S e cr e ta ry Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, W I 5 401 6 Do ugla s E. C oop er Se ni or V ic e P resi den t an d Ch ie f N ucl ear Of f ic er Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, W I 5 401 6 Ste phe n T. W aw ro, D ire ctor o f N u cl e a r A ss e ts Co nsu mers E nergy C ompa ny Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 Lau rie A. La hti , M ana ger R e gul a to ry A ff a i rs Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 ENCLOSURE R E QU E S T F OR A D D ITIO N A L I N F OR M A TION (R A I)L IC E N S E A M E N D M E N T R E QU E S T F OR R E V IS E D S TE A M GE N E R A TOR REPAIR CRIT ERIA (C* CRIT ERIA) PALISADES NUCLEAR PLANT NU CL EA R M AN AGEM EN T COM PA NY , LL C DOCK ET N O. 50-2 55 1.
The p ropo sed ame ndme nt i s i nten ded to al lo w tub es w ith flaw s to rema in i n s erv ic e i f the f law s are locat ed below a certa in depth in the hot-leg reg ion of the tube sheet. Th is w ill requi re p ropo si ng an al terna tiv e to the 40-perc ent, throu gh-w al l dep th c rite ria i n th e P a l i sa d e s' Te ch n i ca l S p e ci fic a ti o n s (TS s). P l e a se d i sc u ss y o u r p l a n s to r e v i se TS 5.5.8.c as f ol lo w s:A.
Ind ic ate there i s a n a lte rnati v e to the 40-perc ent repa ir cri teri a.B.
D efine the rep ai r cri teri a i n th e h ot-l eg tub esh eet regio n (i.e., d epth be lo w w hi ch f la w s ma y r e ma i n i n s e rv i ce , a n d t h e s ta rt i n g p o i n t for th e d e p th me a su re me n t).C.
D efine the rep ai r cri teri a for th e re gion of the ho t-le g tube she et i n w hi ch nei ther the al terna te re pai r cri teri a n or th e 4 0-pe rcen t thro ugh-w al l cri teri a a ppl y (i.e., tu bes w ith fla w s w i th i n t h e C* d i st a n ce w i l l b e p l u gged o n d e te ct i o n).D.
S tate that al l f la w s l oca ted bel ow thi s d epth may rema in i n s erv ic e, re gardl ess of si z e.2.
Pro pos ed TS 5.5.8.d defin es the porti on of tube that must b e i nsp ecte d, "from 12
.5 i nch es bel ow the tub e-to-tu bes hee t ex pan si on trans iti on in le t to the tube-to-tub esh eet w el d a t the tube ou tle t . . . ." Si nce the C* cri teri a i s a n a lte rnate rep ai r cri teri a ra ther than an in s p e c t io n cr it e r ia , it do e s no t ch a n g e t h e ob j e c t iv e in t h e cu r r e n t T S 5.5.8.d t o de t e c t f la ws f rom the inlet tube-to-tube sheet w eld to the out let tube-t o-t ubeshe et wel d. If the C* crit eria is pro perl y de f in ed as an al terna te re pai r cri teri a (a s d is cus sed i n #1 a bov e), th en in spe cti on bel ow the C* d is tanc e i n th e h ot-l eg regio n w oul d n o l onger be requi red bec aus e o f th e p h ra se , ". . . a n d t h a t ma y s a ti sfy t h e a p p l i ca b l e t u b e r e p a i r cr i te ri a" i n TS 5.5.8.d. Please discuss your plans to m odif y prop osed T S 5.5.8.d t o rem ove the r ef eren ce to th e C*di stan ce and res tore the w ordi ng ap prov ed in the Tech ni cal S pec ifica tio ns Task Force 44 9 amen dmen t (i.e., ". . . from the tub e-to-tu bes hee t w el d a t the tub e i nl et to the tub e-to-tube she et w el d a t the tub e o utl et, a nd that may sa tis f y. . . ."). In ad di tio n, th e s taff no tes that the 12.5-in ch C* di stan ce is mea sure d from the top of the tub esh eee t or the botto m of th e e x p a n si o n t ra n si ti o n , w h i ch e v e r i s l o w e r.3.
The b asi c p remi se of the C* amen dmen t i s th at th ere is a 12.5-in ch, non-f la w ed porti on of the tube full y ex pan ded i nto the tube she et. To en sure the regi on remai ns f ree of f la w s, a n inspect ion of 100 percent of the inservice tubes in the upper reg ion of the tube sheet w ill n e e d t o b e p e r fo r me d e v e r y 2 4 e ffe c t i v e fu l l-p o w e r m o n t h s , o r o n e r e fu e l i n g o u t a ge in terv al , w hi che v er i s l ess. A s a res ul t, pl eas e d is cus s y our pl ans to rev is e y our prop ose d TS 5.5.8.d to a dd thi s i nsp ecti on requi rement (e.g., by ad di ng a para graph 5.5.8.d.4). The sta f f notes t hat if an additional parag raph 5.5.8.d.4 is added, it w ill need to be ref eren ced in 5.5.8.d (i.e., "In a d d i ti o n t o me e ti n g th e r e qui re me n ts o f d.1 , d.2 , d.3 , a n d d.4 b e l o w . . . .").4.
Pl eas e c onfirm th at s tructu ral an d l eakage i ntegri ty w il l be ass ess ed if si gnifica nt in di cati ons are found w ith in the i nsp ecte d re gion of the tub esh eet. The staff rec ogni z es that the cur rent approac h of plugg ing f law s on detect ion w ithin the C* distan ce should p r o vi d e a h ig h le ve l o f co n f id e n c e t h a t no po t e n t ia l l e a k in g or st r u c t u r a ll y s ig n if ic a n t f la ws ar e id en t if ied in t his re g ion. Ho wever , su ch an a pp r oa ch ca n no t ens ur e it w it h c er t ain t y.5.
The c al cul ati on of the in spe cti on di stan ce f or th e h ot-l eg tub esh eet regio n u sed the l ow er 95-p erce nt p redi cti on bou nd f or th e me asu red and pro jected smoo th-bo re, "first-sl ip"pul lo ut v al ues pl otted i n F igure 3 of Enc lo sure 4 to y our M ay 30 , 20 06, le tter. As di scu sse d in the R AI resp ons es to p rev io us C* rev ie w s (i.e., S ecti on 2.1.4 i n E ncl osu re 6 of y our M ay 30, 200 6, l etter), use of the l oad at "f irs t sl ip" as sumes tha t the "first mo v e" re sul ts from gri p p e r sl i p p a ge o r o th e r mo v e me n t b e si d e s mo v e me n t o f th e t u b e w i th i n t h e t u b e sh e e t. Si nce thi s a ssu mpti on abo ut th e "first mov e" w as not v eri f ie d, a nd giv en that al l tube s sho ul d re si st p ul lo ut from the tub esh eet, con f irm that if the force-pe r-uni t-le ngth for the most l imi tin g spec ime n, b ase d o n l oad at "f irs t mov e," w ere use d to de termin e th e re quire d le ngth o f ex pan ded tub ed nee ded to resi st p ul lo ut, th is l ength w oul d s til l be le ss than the p ro p o se d i n sp e ct i o n d i st a n ce (1 2.5 i n ch e s). T he staf f notes t hat in Section 2.
4.3 of Enclosure 6 (which addresse s the f irst-slip crit eria f or s mooth-b ore sampl es), the f in al tw o p aragraph s e x pl ai n th at e v en if the re w ere no ex pl ans io n re si dua l con tact pres sure be tw een a tube an d tu bes hee t i n th e P al is ade s s team genera tors, a l ength of 6.75 in che s i s e nou gh to resi st th e th ree-ti mes n ormal op erati ng di f f eren tia l pres sure. The di scu ssi on id enti f ie s d iff eren tia l thermal ex pan si on and e x p a n si o n fro m t h e t u b e i n te rn a l p re ss u re a s th e s o u rc e s o f th e r e si st a n ce t o t u b e p u l l o u t. Al thou gh thi s w as referred to as the "most ex treme c ase ," i t i s n ot c le ar i f the eff ect of tube she et b ow w as in cl ude d. Pl eas e d is cus s w heth er y our ev al uati on con si dere d th e e f f e c t of t u b e s h e e t bo w.6.
For the Ri nghal s te st d ata, the f irs t-sl ip pu ll out v al ues pl otted i n F igure 3 of Enc lo sure 4 w ere proje cted from the measu red, max imu m-lo ad v al ues. P le ase di scu ss the eff ect on Fi gure 3 an d y our le akage an al y ses i f a con serv ati v e b oun d (i.e., 9 5-pe rcen t pre di cti on in terv al) w ere use d to pro ject th e first-s li p l oad v al ues for the R in ghal s d ata.7.
The s taff no tes that the page numb ers li sted on the co v er s hee ts o f E ncl osu res 2 a nd 3 (pages 5.5.8-11 and 5.5.8-12) do no t match the pa ge nu mbers on the botto m of the e n c l o s e d T S p a ge s (p a ge s 5.0-1 1 a n d 5.0-1 2). P l e a s e c l a r i fy w h i c h a r e t h e c o r r e c t p a ge numb ers f or th ese TS p ages. In a ddi tio n, th e s taff no tes that prop ose d TS page 5.0-1 2 sho ul d i den tify the "P rov is io ns f or S G tube i nsp ecti ons. (co nti nue d)" a s i tem "d" rathe r tha n i te m "e."8.
Accor ding to Section 2.
5 of Enclosure 4, the prop osed inspect ion distance of 12.5 inches is bas ed on add in g the 0.28-in ch non-des tructi v e e x ami nati on ax ia l-p osi tio n u nce rtai nty to the v a l u e s o f "J o i n t L e n gth t h a t M e e ts L e a kage C ri te ri a ," (1 2.2 4 a n d 1 2.2 5 i n ch e s). H o w e v e r, si nce 12.25 + 0.2 8 = 12.5 3, i t w oul d b e c ons erv ati v e to us e a v al ue of 12.6 in che s ra ther than 12.5 i nch es. P le ase di scu ss y our pl ans to modi f y y our prop osa l to u se 12.6 i nch es as the prop ose d d is tanc e for th e a lte rnate rep ai r cri teri a (a nd in spe cti on) in the ho t-le g region o f th e t u b e sh e e t.