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| | issue date = 11/28/2012 | | | issue date = 11/28/2012 |
| | title = IR 05000286-12-009, on 06/27/12 - 09/25/12; Indian Point Nuclear Generating Unit 3; Operation of Inter-Unit Fuel Transfer Canister and Cask System | | | title = IR 05000286-12-009, on 06/27/12 - 09/25/12; Indian Point Nuclear Generating Unit 3; Operation of Inter-Unit Fuel Transfer Canister and Cask System |
| | author name = Ferdas M S | | | author name = Ferdas M |
| | author affiliation = NRC/RGN-I/DNMS/DB | | | author affiliation = NRC/RGN-I/DNMS/DB |
| | addressee name = Ventosa J | | | addressee name = Ventosa J |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION I21OO RENAISSANCE BOULEVARD, SUITE 1OOKING OF PRUSSIA, PENNSYLVANIA 19406.27 13November 28.2012Mr. John Ventosa. Site Vice PresidentEntergy Nuclear Operations, Inc.Indian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 1051 1-0249 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION |
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| SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 3 _ INTER-UNIT SPENT FUELTRANSFER INSPECTION REPORT NO. O5OOO28612012009 | | ==REGION I== |
| | 21OO RENAISSANCE BOULEVARD, SUITE 1OO |
| | ==SUBJECT:== |
| | INDIAN POINT NUCLEAR GENERATING UNIT 3 _ INTER-UNIT SPENT FUEL TRANSFER INSPECTION REPORT NO. O5OOO28612012009 |
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| ==Dear Mr. Ventosa:== | | ==Dear Mr. Ventosa:== |
| On September 25,2012, the U.S. Nuclear Regulatory Commission (NRC) completed aninspection of the inter-unit spent fuel transfer from Indian Point Nuclear Generating Unit 3 to Unit2. The enclosed inspection report documerlts the inspection results which were discussed onOctober 25,2012, with Don Mayer, senior nnanagement representative for this project, and othermembers of your staff.The inspection examined activities conductbd under your license as they relate to safety andcompliance with the Commission's rules anp regulations and with the conditions of your license.The inspectors reviewed selected procedurps and records, observed activities, and interviewedpersonnel.Based on the results of this inspection, no findings were identified.In accordance with 10 CFR Part 2.390 of thb NRC's "Rules of Practice," a copy of this letter, itsenclosure, and your response (if any) will bS available electronically for public inspection in theNRC Public Document Room or from the P(rblicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC website athttp://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room). | | On September 25,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the inter-unit spent fuel transfer from Indian Point Nuclear Generating Unit 3 to Unit 2. The enclosed inspection report documerlts the inspection results which were discussed on October 25,2012, with Don Mayer, senior nnanagement representative for this project, and other members of your staff. |
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| Sincerely,Docket No.:License No.:
| | The inspection examined activities conductbd under your license as they relate to safety and compliance with the Commission's rules anp regulations and with the conditions of your license. |
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| ===Enclosure:===
| | The inspectors reviewed selected procedurps and records, observed activities, and interviewed personnel. |
| cc w/encl:Marc S. Ferdas, ChiefDecommissioning BranchDivision of Nuclear Materials Safety50-286DPR-64I nspection Report 05000286/20 1 2009
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| ===w/Attachment:===
| | Based on the results of this inspection, no findings were identified. |
| Supplementary lnformationDistribution via ListServ | | |
| | In accordance with 10 CFR Part 2.390 of thb NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will bS available electronically for public inspection in the NRC Public Document Room or from the P(rblicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room). |
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| | Sincerely, Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety Docket No.: 50-286 License No.: DPR-64 Enclosure: I nspection Report 05000286/20 1 2009 w/Attachment: Supplementary lnformation cc w/encl: Distribution via ListServ |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| lR 0500028612012009;0612712012 - 0912512012; Indian Point Nuclear Generating Unit 3;Operation of Inter-Unit Fuel Transfer Canister and Cask System.This report covers the inter-unit fuel transfer operational dry run and initial fuel transferinspection conducted by a team of six NRC inspectors. The NRC's program for overseeing thesafe operation of commercial nuclear power reactors is described in NUREG-1649, "ReactorOversight Process," Revision 4, dated December 2006.No findings were identified.Enclosure | | lR 0500028612012009;0612712012 - 0912512012; Indian Point Nuclear Generating Unit 3; |
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| | Operation of Inter-Unit Fuel Transfer Canister and Cask System. |
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| 4.4045.1a.3 | | This report covers the inter-unit fuel transfer operational dry run and initial fuel transfer inspection conducted by a team of six NRC inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006. |
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| | No findings were identified. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
| orHER ACTTVTTES (OA)Other ActivitiesBackgroundOn July 13,2012, the NRC issued Amendment No. 268 to Facility Operating LicenseNo. DPR-26 for Indian Point Nuclear Generating Unit 2 (lP2) and Amendment No. 246toFacility Operating License No. DPR-64 for lP3. The amendments revised the licensesand Technical Specifications (TS) by authorizing the transfer of spent fuel from the lP3spent fuel pool (SFP) to the lP2 SFP using a newly-designed shielded transfer canister(STC) for further transfer to the onsite Independent Spent Fuel Storage Installation(rsFSr).Pre-operational Test Prooram (60845)Inspection ScopeThe inspectors evaluated Entergy's performance during NRC observed pre-operationaldry run activities that were performed in order to fulfill requirements in Appendix C Inter-Unit Fuel Transfer TS 2.3. The inspectors observed dry run activities on June 27-29(Phase l), August 8 (Phase lll), 13-15 (Phase lV), and September 13-14 (Phase ll),2012. The pre-operational dry run activities were conducted in four phases.The inspectors observed STC closure operations and preparation for transferring theSTC between units (Phase l). The inspectors verified the following activities wereperformed in accordance with the TS and Entergy's procedures: verification of loadingoperation conditions, dose rate monitoring, leak test of the steam generator system, freeflow water test of the STC lid connections, installation and torquing of the STC lid, leakrate test of the lid seals, establishment of steam vapor space, pressure rise test, leakrate test of the port cover plates, and installation of the HI-TRAC top lid.The inspectors observed load handling and fuel loading operations at lP3 (Phase ll).The inspectors verified the following activities were performed in accordance with the TSand Entergy's procedures: installation of the centering assembly in the HI-TRAC, use ofthe FSB overhead crane to lift the STC out of the HI-TMC and into the SFP, removingthe STC lid, installing and removing the cell blocker, installing and removing a dummyspent fuel assembly, installing the STC lid remotely, removing the STC from the SFP,dose rate monitoring of the STC lid, removal of water out of the STC, performingemergency manual crane operations, and placing the STC into the HI-TRAC.The inspectors observed inter-unit transfer between lP3 and lP2 (Phase lll). Theinspectors verified the following activities were performed in accordance with the TS andEntergy's procedures: placement of the HI-TRAC with STC on the air pallet systemoutside lP3 fuel storage building (FSB) truck bay, moving the HI-TRAC/STC into and outof the lP3 FSB using the air pallet system, use of the vertical cask transporter (VCT) toEnclosure 4transport the HI-TRAC/STC from lP3 and lP2, lowering the HI-TRAC/STC onto the lP2low profile transporter (LPT), moving the HI-TRAC/STC into lP2 using the LPT and thetugger vehicle, and using the rail system to move the HI-TRAC/STC to the stagingposition in the lP2 truck bay.The inspectors observed load handling and fuel unloading operations at Unit 2 (PhaselV). The inspectors verified the following activities were performed in accordance withthe TS and Entergy's procedures: verification of the SFP boron concentration, ventingthe pressure from the HI-TRAC cavity, removing the HI-TRAC lid, venting the pressurefrom the STC cavity, preparing the STC lid for SFP operations, use of the gantry craneto transfer the STC into the SFP, removing the STC lid under water, removing a dummyfuel assembly in the STC, removing the STC from the SFP, and performing emergencymanualgantry crane operations with the STC.The inspectors reviewed Entergy's inter-unit fuel loading, unloading, and processingprocedures to ensure that they contained commitments and requirements specified inthe operating license amendment, the safety evaluation report (SER), TS, and the HoltecLicensing Report. The inspectors also reviewed the procedures and information relatedto selection of spent fuel and non-fuel hardware for transfer in the STC. The inspectorsverified that the spent fuel and non-fuel hardware for the first transfer met the TS forloading in the STC. The inspectors also reviewed the move sheet that indicated thelocations where the assemblies and hardware were to be placed in the lP2 spent fuelpool and compared the move sheet against the requirements described in lP2 TS.The inspectors also verified that: (1) preoperational procedures for inter-unit fueltransfer activities were prepared, reviewed, and initially approved in accordance withEntergy's administrative procedures; (2) Entergy personnel conducting thepreoperational test activities had a clear understanding of their duties andresponsibilities; (3) equipment used during preoperational test activities had been testedand evaluated for its impact on plant structures, systems, and components beforeperformance of preoperational tests; (4) equipment used during preoperationaltestactivities met maintenance criteria required by the manufacturer and Entergy; (5)Entergy implemented the site radiological protection program for activities such ascontamination controls, temporary shielding, distance, and surveys (including neutronsurveys as required by the TS); and (6) Entergy performed management and qualityassurance reviews on preoperational test activities.The inspectors also reviewed corrective action reports on issues that could affectpreoperational inter-unit transfer activities to ensure that issues were entered into thecorrective action program, prioritized, and evaluated commensurate with their safetysignificance.FindinqsNo findings were identified.Enclosure
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| ===.2 a.5Initial Inter-Unit Fuel Transfer (60845)Inspection ScopeThe inspectors observed Entergy's initial inter-unit fuel transfer of 12 spent fuelassemblies from lP3 to lP2 on September 16-20, and 23-25,2012. The inspectorsverified compliance with Entergy's operating license amendment, SER, Holtec LicensingReport, TS, NRC regulations, and Entergy procedures.The inspectors attended pre-job briefs and verified that the briefs emphasized the criticalsteps and reviewed the conditions in the work areas. The inspectors interviewedpersonnel and ensured they were trained and knowledgeable regarding the tasks to beperformed. In addition, training records were reviewed to ensure personnel werequalified to perform their assigned tasks.The inspectors observed the loading of spent fuel assemblies from the lP3 SFP into theSTC, placing of the lid on the STC, and heavy load movement of the STC from the lP3SFP into the HI-TRAC in the lP3 FSB truck bay. The inspectors observed STCprocessing operations including: STC closure operations and preparation of the STC fortransfer between lP3 and lP2 (including verifying the loading operations conditions, doserate readings on the side of the HI-TRAC, leak testing of the steam generator system,free flow water test of the STC lid connections, installation and torquing of the lid studsand nuts, leak rate test of the lid seals, establishment of the steam vapor space,pressure rise test, leak rate test of the port cover plates, and installation of the HI-TRACtop lid). In addition the inspectors observed the movement of the STC from lP3 to lP2;and placing the STC and unloading spent fuel assemblies into the lP2 SFP. Duringperformance of these activities, the inspectors verified that procedure use,communication. and coordination of inter-unit fuel transfer activities met establishedstandards and requirements.The inspectors reviewed maintenance records and verified that equipment used duringoperational activities met maintenance criteria required by the manufacturer andEntergy. In addition, the inspectors verified Entergy performed management and qualityassurance reviews during initial transfer operations.The inspectors reviewed radiation protection procedures, radiation work permits(RWPs), and the established radiological controls associated with the inter-unit fueltransfer. The inspectors assessed whether workers were aware of the radiologicalconditions in their work area and the RWP controls/limits. The inspectors reviewedradiological records from the first fuel transfer to confirm that radiation survey levelsmeasuied were within limits established in the TS and consistent with values specified inthe Holtec Licensing Report.Enclosure=== | | ===4. orHER ACTTVTTES (OA)=== |
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| | 4045 Other Activities Background On July 13,2012, the NRC issued Amendment No. 268 to Facility Operating License No. DPR-26 for Indian Point Nuclear Generating Unit 2 (lP2) and Amendment No. 246to Facility Operating License No. DPR-64 for lP3. The amendments revised the licenses and Technical Specifications (TS) by authorizing the transfer of spent fuel from the lP3 spent fuel pool (SFP) to the lP2 SFP using a newly-designed shielded transfer canister (STC) for further transfer to the onsite Independent Spent Fuel Storage Installation (rsFSr). |
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| | ===.1 Pre-operational Test Prooram=== |
| | {{IP sample|IP=IP 60845}} |
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| | ====a. Inspection Scope==== |
| | The inspectors evaluated Entergy's performance during NRC observed pre-operational dry run activities that were performed in order to fulfill requirements in Appendix C Inter-Unit Fuel Transfer TS 2.3. The inspectors observed dry run activities on June 27-29 (Phase l), August 8 (Phase lll), 13-15 (Phase lV), and September 13-14 (Phase ll),2012. The pre-operational dry run activities were conducted in four phases. |
| | |
| | The inspectors observed STC closure operations and preparation for transferring the STC between units (Phase l). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: verification of loading operation conditions, dose rate monitoring, leak test of the steam generator system, free flow water test of the STC lid connections, installation and torquing of the STC lid, leak rate test of the lid seals, establishment of steam vapor space, pressure rise test, leak rate test of the port cover plates, and installation of the HI-TRAC top lid. |
| | |
| | The inspectors observed load handling and fuel loading operations at lP3 (Phase ll). |
| | |
| | The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: installation of the centering assembly in the HI-TRAC, use of the FSB overhead crane to lift the STC out of the HI-TMC and into the SFP, removing the STC lid, installing and removing the cell blocker, installing and removing a dummy spent fuel assembly, installing the STC lid remotely, removing the STC from the SFP, dose rate monitoring of the STC lid, removal of water out of the STC, performing emergency manual crane operations, and placing the STC into the HI-TRAC. |
| | |
| | The inspectors observed inter-unit transfer between lP3 and lP2 (Phase lll). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: placement of the HI-TRAC with STC on the air pallet system outside lP3 fuel storage building (FSB) truck bay, moving the HI-TRAC/STC into and out of the lP3 FSB using the air pallet system, use of the vertical cask transporter (VCT) to transport the HI-TRAC/STC from lP3 and lP2, lowering the HI-TRAC/STC onto the lP2 low profile transporter (LPT), moving the HI-TRAC/STC into lP2 using the LPT and the tugger vehicle, and using the rail system to move the HI-TRAC/STC to the staging position in the lP2 truck bay. |
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| | The inspectors observed load handling and fuel unloading operations at Unit 2 (Phase lV). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: verification of the SFP boron concentration, venting the pressure from the HI-TRAC cavity, removing the HI-TRAC lid, venting the pressure from the STC cavity, preparing the STC lid for SFP operations, use of the gantry crane to transfer the STC into the SFP, removing the STC lid under water, removing a dummy fuel assembly in the STC, removing the STC from the SFP, and performing emergency manualgantry crane operations with the STC. |
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| | The inspectors reviewed Entergy's inter-unit fuel loading, unloading, and processing procedures to ensure that they contained commitments and requirements specified in the operating license amendment, the safety evaluation report (SER), TS, and the Holtec Licensing Report. The inspectors also reviewed the procedures and information related to selection of spent fuel and non-fuel hardware for transfer in the STC. The inspectors verified that the spent fuel and non-fuel hardware for the first transfer met the TS for loading in the STC. The inspectors also reviewed the move sheet that indicated the locations where the assemblies and hardware were to be placed in the lP2 spent fuel pool and compared the move sheet against the requirements described in lP2 TS. |
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| | The inspectors also verified that: |
| | : (1) preoperational procedures for inter-unit fuel transfer activities were prepared, reviewed, and initially approved in accordance with Entergy's administrative procedures; |
| | : (2) Entergy personnel conducting the preoperational test activities had a clear understanding of their duties and responsibilities; |
| | : (3) equipment used during preoperational test activities had been tested and evaluated for its impact on plant structures, systems, and components before performance of preoperational tests; |
| | : (4) equipment used during preoperationaltest activities met maintenance criteria required by the manufacturer and Entergy; |
| | : (5) Entergy implemented the site radiological protection program for activities such as contamination controls, temporary shielding, distance, and surveys (including neutron surveys as required by the TS); and |
| | : (6) Entergy performed management and quality assurance reviews on preoperational test activities. |
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| | The inspectors also reviewed corrective action reports on issues that could affect preoperational inter-unit transfer activities to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance. |
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| | Findinqs No findings were identified. |
| | |
| | ===.2 Initial Inter-Unit Fuel Transfer=== |
| | {{IP sample|IP=IP 60845}} |
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| | ====a. Inspection Scope==== |
| | The inspectors observed Entergy's initial inter-unit fuel transfer of 12 spent fuel assemblies from lP3 to lP2 on September 16-20, and 23-25,2012. The inspectors verified compliance with Entergy's operating license amendment, SER, Holtec Licensing Report, TS, NRC regulations, and Entergy procedures. |
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| | The inspectors attended pre-job briefs and verified that the briefs emphasized the critical steps and reviewed the conditions in the work areas. The inspectors interviewed personnel and ensured they were trained and knowledgeable regarding the tasks to be performed. In addition, training records were reviewed to ensure personnel were qualified to perform their assigned tasks. |
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| | The inspectors observed the loading of spent fuel assemblies from the lP3 SFP into the STC, placing of the lid on the STC, and heavy load movement of the STC from the lP3 SFP into the HI-TRAC in the lP3 FSB truck bay. The inspectors observed STC processing operations including: STC closure operations and preparation of the STC for transfer between lP3 and lP2 (including verifying the loading operations conditions, dose rate readings on the side of the HI-TRAC, leak testing of the steam generator system, free flow water test of the STC lid connections, installation and torquing of the lid studs and nuts, leak rate test of the lid seals, establishment of the steam vapor space, pressure rise test, leak rate test of the port cover plates, and installation of the HI-TRAC top lid). In addition the inspectors observed the movement of the STC from lP3 to lP2; and placing the STC and unloading spent fuel assemblies into the lP2 SFP. During performance of these activities, the inspectors verified that procedure use, communication. and coordination of inter-unit fuel transfer activities met established standards and requirements. |
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| | The inspectors reviewed maintenance records and verified that equipment used during operational activities met maintenance criteria required by the manufacturer and Entergy. In addition, the inspectors verified Entergy performed management and quality assurance reviews during initial transfer operations. |
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| | The inspectors reviewed radiation protection procedures, radiation work permits (RWPs), and the established radiological controls associated with the inter-unit fuel transfer. The inspectors assessed whether workers were aware of the radiological conditions in their work area and the RWP controls/limits. The inspectors reviewed radiological records from the first fuel transfer to confirm that radiation survey levels measuied were within limits established in the TS and consistent with values specified in the Holtec Licensing Report. |
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| | The inspectors reviewed corrective action reports and the associated follow-up actions that were generated since the pre-operational dry run activities to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance. |
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| b.6The inspectors reviewed corrective action reports and the associated follow-up actionsthat were generated since the pre-operational dry run activities to ensure that issueswere entered into the corrective action program, prioritized, and evaluatedcommensurate with their safety significance.FindinqsNo findings were identified.Meetinqs, includinq ExitOn October 25,2012, the team presented the results via telephone to Don Mayer, thesenior management representative for the inter-unit fuel transfer project;Joe Defrancesco, prgect manager; and other Entergy personnel. Bridget Frymire,Power Systems Operations Specialist for the New York State Department of PublicService, also participated in the exit meeting. The inspectors verified that no proprietaryinformation was retained by the inspectors or documented in this report.Attachment: Supplementary Information40A6Enclosure A-1
| | Findinqs No findings were identified. |
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| | 40A6 Meetinqs, includinq Exit On October 25,2012, the team presented the results via telephone to Don Mayer, the senior management representative for the inter-unit fuel transfer project; Joe Defrancesco, prgect manager; and other Entergy personnel. Bridget Frymire, Power Systems Operations Specialist for the New York State Department of Public Service, also participated in the exit meeting. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report. |
| | : Supplementary Information |
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| =SUPPLEMENTARY INFORMATION= | | =SUPPLEMENTARY INFORMATION= |
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| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
| PARTIAL LIST OF PERSONS CONTACTEDIndian Point | | |
| : [[contact::J. DefrancescoL. GaryR. JonesM. LahamT. LinkeD. MayerR. MillerF. MitchellW. OsminT. PaskoC. PattersonW. RiggsT. SalentinoS. StevensJ. StewartC. TippinS. TraditiR. WatersC. WeberNRCJ. BoskaD. PickettProject ManagementQuality AssuranceDry Cask StorageProject ManagementDry Cask StorageSenior Management RepresentativeProject ManagementRadiation ProtectionReactor EngineeringDry Cask Storage SupervisorDry Cask Storage SupervisorProject ManagementDry Cask Storage SuperintendentRadiation Protection SupervisorRadiation ProtectionReactor EngineeringDry Cask StorageLicensingDry Cask StorageNRR]], Project ManagerNRR, Project ManagerITEMS OPEN. CLOSED. AND DISCUSSEDOpened/Closed/DiscussedNoneAttachment
| | PARTIAL LIST OF PERSONS CONTACTED |
| A-2
| | Indian Point |
| | J. Defrancesco Project Management |
| | L. Gary Quality Assurance |
| | R. Jones Dry Cask Storage |
| | M. Laham Project Management |
| | T. Linke Dry Cask Storage |
| | D. Mayer Senior Management Representative |
| | R. Miller Project Management |
| | F. Mitchell Radiation Protection |
| | W. Osmin Reactor Engineering |
| | T. Pasko Dry Cask Storage Supervisor |
| | C. Patterson Dry Cask Storage Supervisor |
| | W. Riggs Project Management |
| | T. Salentino Dry Cask Storage Superintendent |
| | S. Stevens Radiation Protection Supervisor |
| | J. Stewart Radiation Protection |
| | C. Tippin Reactor Engineering |
| | S. Traditi Dry Cask Storage |
| | R. Waters Licensing |
| | C. Weber Dry Cask Storage |
| | NRC |
| | : [[contact::J. Boska NRR]], Project Manager |
| | : [[contact::D. Pickett NRR]], Project Manager |
| | ITEMS OPEN. CLOSED. AND DISCUSSED |
| | Opened/Closed/Discussed |
| | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| Procedures0-FTR-401-GEN, Rev. 0 "Special Lifting Devices lnspection"0-FTR-402-GEN. Rev.3 "STC Movement Between Unit 2 and Unit 3"0-FTR-403-GEN. Rev.3 "lnter-Unit Fuel Transfer Abnormal Event Procedure"0-FTR-404-G E N, Rev. 0 " I nter-Unit Fuel Transfer Readiness Guidelines"0-RP-RWP-430, Rev.1 "Radiological Controls for Inter-Unit Wet Fuel Transfer,0612512012"2-DCS-006-GEN, Rev.8 "Vertical Cask Transporter (VCT) Operation"2-DCS-026-GEN, Rev.6'FSB 110 Ton X-SAM Gantry Crane Operations"2-FTR-001-GEN, Rev.5 "Unit 2 STC Unloading Operations"2-SOP-17.12, Rev.16 "Spent Fuel Handing Machine and Spent Fuel Pit Operations"3-FTR-003-GEN, Rev.2 "Air Pad Operation for Unit 3"3-FTR-005-GEN, Rev.0 "Ancillary Equipment Pre-Operational Inspection andFunctional Checks"3-FTR-006-GEN, Rev.6 "Unit 3 STC Loading and Sealing Operations"3-NF-322. Rev. 1 "Fuel Selection for Wet Fuel Transfer in the Shielded Transfer Caniste/'3-SOP-CM-002, Rev.21 "Fuel Storage Building Crane Operation"EN-DC-215, Rev. 3 "Fuel Selection for Dry Cask Storage"EN-RP-141-01, Rev.4 "Job Coverage Using Remote Monitoring Technology"EN-RP-204, Rev.6 "Special Monitoring Requirements"MSLT-STC-PCI, Rev. 4107-O0 "STC Helium Mass Spectrometer Leak Test Procedure"Calculations"Miscellaneous Calculations in Support of STC Operations, Holtec Report No. Hl-2125189,06t25t2012"Corrective Action Condition ReportscR-lp3-2012-2528, CR-tp2-2012-5203, CR-lP3-2012-2512, CR-lP3-2012-2573,
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| : CR-1P2-2012-5209, CR-tp2-2012-5154, CR-tp2-2012-5189, CR-tP2-2012-5187, CR-lP2-2012-5191, CR-lP2-2012-5192, CR-lp3-2012-2625, CR-lP3-2012-2660, CR-lP3-2012-2584, CR-lP3-2012-2706,cR-lp3-2012-2711, CR-lp3-2012-2724, CR-tP3-2012-2878, CR-lP3-2012-2912, CR-lP2-2012-5882, C R-l P3-20 1 2-1 387, C R-! P3-20 I
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| : 2-2036, C R- l P2-20 1
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| : 2-3620Maintenance Work OrdersWork Order
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| : 298588-41, "Transfer Spent Fuel From U3 SFP to U2 SFP, Troubleshoot U2 FSBCrane Girder Control"Work Order
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| : 52344241-01, "Perform Annual DCS Lift Devices lnspections"Work Order
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| : 00325861-02, "Return STC Back lnto the Unit 3 SFP"Attachment
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| : A-3Miscellaneous0-NF-203, Rev 8, "lnternal Transfer of Fuel Assemblies and Inserts," Attachment 18 "15x15 FuelAssembly Visual Inspection Instructions," both the instructions and sheet completed for theassemblies to be loaded into STClCASKLOADE R_FU EL_l N SE RT-] N FO.xlsCycle_status.xlsEN-DC-215_ATT 9.5.pdf (completed information sheets for the SNF assemblies in the first STC,sTcl)FA X-60 REPAIR DOC.pdf, a Westinghouse Proprietary Class 2 document portion showingvarious identified lP3 leaking assemblies and repairs to FA X-60, dated October 3,2007FSRT-12-19, a Westinghouse Proprietary Class 2 document titled "Summary of Sipping Resultsfor lndian Point Unit 3 2012 Canister Sipping Campaign" dated March 9,2012FSRT-12-21_ITTR Repair.pdf, a Westinghouse Proprietary Class 2 document with Subject line"tnstrument Tube Tie Rod Installation at Indian Point Unit 3" and dated March 12,2012Entergy Nuclear Indian Point 2, LLC Entergy Nuclear Operations Inc. Docket No. 50-247 lndianPoint Nuclear Generating Unit No.2 Amendment No. 268 To Facility Operating License No.DPR-26Entergy Nuclear Indian Point 3, LLC Entergy Nuclear Operations Inc. Docket No. 50-286 IndianPoint Nuclear Generating Unit No.3 Amendment No. 246 To Facility Operating License No.DPR-64Holtec Information Bulletin #56 Re-examining the ANSI 14.6 Compliance of Round Bars inLifting Apparatus Using State-ofthe-Art Finaite Element MethodsInter-Unit FuelTransfer Pre-Operational Testing and Training Exercise PlanLicensee Event Report (LER) No. 2012-002-00 Technical Specification Prohibited ConditionCaused by New FuelAssemblies Stored in a Configuration Prohibited by the TSlP2_SFP_Map.xlslP3 FSAR (Rev 4., 2011) Pgs 43-53I P3_Fuel-Characteristics. xlslP3_SFP_Map.xlsI P3_F U E L_CATEGO R IZATI O N-TYP E. xlsLicensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point EnergyCenter, Rev. 6, Holtec Report No. Hl-2094289, April2012Move Sheet Unload
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| : STC1.PdfMove Sheet Load
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| : STC1.PdfNF-lN-10-40 a Westinghouse Proprietary Class 2 letter titled "Core ComponenUFuel AssemblyStorage Compatibility Analysis for INEQ (PDM-10-107)' for lP3 and dated November 1 , 2010.The aitachment, "INEQ Core Component/FuelAssembly Storage Compatibility Summary" isdated September 2Q, 2010Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 268to Facility Operating License No.
| |
| : DPR-26 and Amendment No. 246 to Facility OperatingLicense No.
| |
| : DPR-64 Entergy Nuclear Operations, lnc. lndian Point Nuclear GeneratingUnit Nos. 2 and 3 Docket Nos. 50-247 and 50-286, July 2Q12StructuralAnalysis of Shielded Transfer Canister Lifting Device for Entergy lP3, Holtec ReportNo. Hl-2094412Structural Analysis of STC Lift Hook Assembly, Holtec Report No. Hl-2094435Attachment
| |
| : FSBISFSILPTOARWPSERSFPSTCTSVCTA-4
| |
| ==LIST OF ACRONYMS==
| |
| : [[USEDF]] [[uel Storage BuildingIndependent Spent Fuel Storage InstallationLow Profile TransporterOther ActivitiesRadiation Work PermitSafety Evaluation ReportSpent Fuel PoolShielded Transfer CanisterTechnical SpecificationsVertical Cask TransporterAttachment]]
| |
| }} | | }} |
|
|---|
Category:Inspection Report
MONTHYEARIR 05000003/20230032023-11-21021 November 2023
NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003
IR 05000003/20230022023-08-22022 August 2023
NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002
IR 05000003/20230012023-05-22022 May 2023
Unions 1, 2 and 3 - NRC Inspection Report Nos. 05000003/2023001, 05000247/2023001, 05000286/2023001, and 07200051/2023001
IR 05000003/20234012023-05-10010 May 2023
NRC Security Decommissioning Inspection Report Nos. 05000003/2023401, 05000247/2023401, and 05000286/2023401
IR 05000003/20220042023-03-13013 March 2023
NRC Inspection Report Nos. 05000003/2022004, 05000247/2022004, 05000286/2022004, and 07200051/2022002
IR 05000003/20220022022-11-17017 November 2022
NRC Inspection Report Nos. 05000003/2022002, 05000003/2022003, 05000247/2022002, 05000247/2022003, 05000286/2022002, 05000286/2022003, and 07200051/2022001
IR 05000003/20224022022-10-28028 October 2022
Reissued NRC Security Decommissioning Inspection Report Nos. 05000003/2022402, 05000247/2022402, and 05000286/2022402 (Letter Only)
IR 05000003/20224012022-05-25025 May 2022
NRC Security Decommissioning Inspection Report Nos. 05000003/2022401, 05000247/2022401, and 05000286/2022401
IR 05000003/20220012022-05-25025 May 2022
NRC Inspection Report Nos. 05000003/2022001, 05000247/2022001, and 05000286/2022001
IR 05000003/20210042022-03-0404 March 2022
NRC Inspection Report Nos. 05000003/2021004, 05000247/2021004, 05000286/2021004, and 07200051/2021001
IR 05000003/20210032021-11-0909 November 2021
NRC Inspection Report Nos. 05000003/2021003, 05000247/2021003, and 05000286/2021003
IR 05000003/20210022021-08-0404 August 2021
NRC Inspection Report Nos. 05000003/2021002, 05000247/2021002, and 05000286/2021002
IR 05000286/20210022021-06-0707 June 2021
Integrated Inspection Report 05000286/2021002
IR 05000286/20214022021-05-0505 May 2021
Security Baseline Inspection Report 05000286/2021402
IR 05000003/20210012021-04-21021 April 2021
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2 - NRC Inspection Report No. 05000003/2021001 and 05000247/2020001
IR 05000286/20210012021-04-15015 April 2021
Integrated Inspection Report 05000286/2021001
IR 05000286/20200062021-03-0303 March 2021
Annual Assessment Letter for Indian Point Energy Center, Unit 3 (Report 05000286/2020006)
IR 05000247/20200142021-02-0101 February 2021
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 2 NRC Inspection Report No. 05000247/2020014
IR 05000286/20200042021-01-28028 January 2021
Integrated Inspection Report 05000286/2020004
IR 05000003/20200012020-12-0808 December 2020
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2, NRC Inspection Report No. 05000003/2020001 and 05000247/2020013
IR 05000286/20200032020-10-28028 October 2020
Integrated Inspection Report 05000286/2020003
IR 05000286/20200102020-09-16016 September 2020
Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000286/2020010
IR 05000286/20200052020-08-31031 August 2020
Updated Inspection Plan for Indian Point Energy Center, Unit 3 (Inspection Report 05000286/2020005)
IR 05000247/20200022020-08-10010 August 2020
Integrated Inspection Report 05000247/2020002 and 05000286/2020002
IR 05000286/20200122020-07-27027 July 2020
Design Basis Assurance Inspection (Programs) Inspection Report 05000286/2020012
IR 05000247/20020102020-05-12012 May 2020
Final ASP Analysis - Indian Point 2 (IR 050002472002010)
IR 05000247/20200012020-04-29029 April 2020
Integrated Inspection Report 05000247/2020001 and 05000286/2020001
IR 05000247/20190062020-03-0303 March 2020
Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Report 05000247/2019006 and 05000286/2019006)
IR 05000247/20190042020-02-10010 February 2020
Integrated Inspection Report 05000247/2019004 and 05000286/2019004
IR 05000003/20190012020-01-16016 January 2020
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2019001
IR 05000247/20190122020-01-0909 January 2020
Temporary Instruction 2515/194 Inspection Report 05000247/2019012 and 05000286/2019012
IR 05000247/20194112020-01-0909 January 2020
Material Control and Accounting Program Inspection Report 05000247/2019411 and 05000286/2019411 (Cover Letter Only)
IR 05000247/20194032019-11-0505 November 2019
Cyber Security Inspection Report 05000247/2019403 and 05000286/2019403 (Cover Letter Only)
IR 05000247/20190032019-11-0404 November 2019
Integrated Inspection Report 05000247/2019003 and 05000286/2019003
IR 05000247/20194102019-10-0202 October 2019
Security Inspection Report 05000247/2019410 and 05000286/2019410 (Cover Letter Only)
IR 05000247/20190102019-09-26026 September 2019
Biennial Problem Identification and Resolution Inspection Report 05000247/2019010 and 05000286/2019010
IR 05000247/20190052019-08-28028 August 2019
Updated Inspection Plan (Inspection Report 05000247/2019005 and 05000286/2019005)
IR 05000247/20190022019-08-13013 August 2019
Integrated Inspection Report 05000247/2019002 and 05000286/2019002
IR 05000247/20190112019-07-0909 July 2019
Design Basis Assurance Inspection (Programs) Inspection Report 05000247/2019011 and 05000286/2019011
IR 05000247/20190012019-05-13013 May 2019
Integrated Inspection Report 05000247/2019001 and 05000286/2019001
ML19130A0422019-05-0808 May 2019
Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000247/2019403 and 05000286/2019403
IR 05000247/20193012019-04-18018 April 2019
Initial Operator Licensing Examination Report 05000247/2019301
IR 05000247/20180062019-03-0404 March 2019
Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Reports 05000247/2018006 and 05000286/2018006)
IR 05000247/20180042019-02-0707 February 2019
Integrated Inspection Report 05000247/2018004 and 05000286/2018004
IR 05000247/20180102019-01-15015 January 2019
Design Bases Assurance Inspection (Teams) Report 05000247/2018010 and 05000286/2018010
IR 05000247/20180022019-01-0909 January 2019
Errata for Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018002 and 05000286/2018002
IR 05000247/20184102018-12-0606 December 2018
Security Inspection Report 05000247/2018410 and 05000286/2018410 (Cover Letter Only)
IR 05000247/20182012018-11-27027 November 2018
NRC Inspection Report 05000247/2018201 and 05000286/2018201
IR 05000247/20180032018-11-0808 November 2018
Integrated Inspection Report 05000247/2018003 and 05000286/2018003
IR 05000003/20180012018-10-25025 October 2018
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2018001 Dated October 25, 2018
2023-08-22
[Table view]
Category:Letter
MONTHYEARML24011A1982024-01-12012 January 2024
ISFSI, Notice of Organization Change for Site Vice President
ML23342A1082024-01-0909 January 2024
Independent Spent Fuel Storage Installation Security Inspection Plan
ML23353A1742023-12-19019 December 2023
ISFSI, Emergency Plan, Revision 23-04
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
ML23339A0442023-12-0505 December 2023
Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan
ML23326A1322023-12-0505 December 2023
Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan
ML23338A2262023-12-0404 December 2023
Signed Amendment No. 27 to Indemnity Agreement No. B-19
ML23356A0212023-12-0101 December 2023
American Nuclear Insurers, Secondary Financial Protection (SFP) Program
ML23242A2772023-11-30030 November 2023
NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs
ML23338A0482023-11-30030 November 2023
ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28
ML22339A1572023-11-27027 November 2023
Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E
IR 05000003/20230032023-11-21021 November 2023
NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003
ML23100A1172023-11-17017 November 2023
NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition
ML23050A0032023-11-17017 November 2023
Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage
ML23100A1252023-11-17017 November 2023
Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement
ML23100A1432023-11-16016 November 2023
Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286)
ML23064A0002023-11-13013 November 2023
NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme 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
ML23306A0992023-11-0202 November 2023
and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7)
ML23063A1432023-11-0101 November 2023
Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50
ML23292A0262023-10-19019 October 2023
LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI
ML23289A1582023-10-16016 October 2023
Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit
ML23270A0082023-09-27027 September 2023
Registration of Spent Fuel Casks
ML23237A5712023-09-22022 September 2023
09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
ML23242A2182023-09-12012 September 2023
IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286)
ML23250A0812023-09-0707 September 2023
Registration of Spent Fuel Casks
ML23255A0142023-08-31031 August 2023
LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report
IR 05000003/20230022023-08-22022 August 2023
NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002
ML23227A1852023-08-15015 August 2023
Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme
ML23222A1442023-08-10010 August 2023
Registration of Spent Fuel Casks
ML23208A1642023-07-26026 July 2023
Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater
ML23200A0422023-07-19019 July 2023
Registration of Spent Fuel Casks
ML23235A0602023-07-17017 July 2023
LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
ML23194A0442023-07-11011 July 2023
Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan
ML23192A1002023-07-11011 July 2023
Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme
ML23171B0432023-06-23023 June 2023
Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment
ML23118A0972023-06-0606 June 2023
06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River
ML23144A3512023-05-25025 May 2023
Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site
ML23144A3522023-05-25025 May 2023
Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site
ML23144A3412023-05-25025 May 2023
Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site
ML23144A3472023-05-25025 May 2023
David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site
ML23144A3402023-05-25025 May 2023
Melvin Israel of New York Email Against Treated Water Release from Indian Point Site
ML23144A3542023-05-25025 May 2023
Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site
ML23144A3532023-05-25025 May 2023
John Shaw of New York Email Against Treated Water Release from Indian Point Site
2024-01-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION I
21OO RENAISSANCE BOULEVARD, SUITE 1OO
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT 3 _ INTER-UNIT SPENT FUEL TRANSFER INSPECTION REPORT NO. O5OOO28612012009
Dear Mr. Ventosa:
On September 25,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the inter-unit spent fuel transfer from Indian Point Nuclear Generating Unit 3 to Unit 2. The enclosed inspection report documerlts the inspection results which were discussed on October 25,2012, with Don Mayer, senior nnanagement representative for this project, and other members of your staff.
The inspection examined activities conductbd under your license as they relate to safety and compliance with the Commission's rules anp regulations and with the conditions of your license.
The inspectors reviewed selected procedurps and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings were identified.
In accordance with 10 CFR Part 2.390 of thb NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will bS available electronically for public inspection in the NRC Public Document Room or from the P(rblicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room).
Sincerely, Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety Docket No.: 50-286 License No.: DPR-64 Enclosure: I nspection Report 05000286/20 1 2009 w/Attachment: Supplementary lnformation cc w/encl: Distribution via ListServ
SUMMARY OF FINDINGS
lR 0500028612012009;0612712012 - 0912512012; Indian Point Nuclear Generating Unit 3;
Operation of Inter-Unit Fuel Transfer Canister and Cask System.
This report covers the inter-unit fuel transfer operational dry run and initial fuel transfer inspection conducted by a team of six NRC inspectors. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.
No findings were identified.
REPORT DETAILS
4. orHER ACTTVTTES (OA)
4045 Other Activities Background On July 13,2012, the NRC issued Amendment No. 268 to Facility Operating License No. DPR-26 for Indian Point Nuclear Generating Unit 2 (lP2) and Amendment No. 246to Facility Operating License No. DPR-64 for lP3. The amendments revised the licenses and Technical Specifications (TS) by authorizing the transfer of spent fuel from the lP3 spent fuel pool (SFP) to the lP2 SFP using a newly-designed shielded transfer canister (STC) for further transfer to the onsite Independent Spent Fuel Storage Installation (rsFSr).
.1 Pre-operational Test Prooram
a. Inspection Scope
The inspectors evaluated Entergy's performance during NRC observed pre-operational dry run activities that were performed in order to fulfill requirements in Appendix C Inter-Unit Fuel Transfer TS 2.3. The inspectors observed dry run activities on June 27-29 (Phase l), August 8 (Phase lll), 13-15 (Phase lV), and September 13-14 (Phase ll),2012. The pre-operational dry run activities were conducted in four phases.
The inspectors observed STC closure operations and preparation for transferring the STC between units (Phase l). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: verification of loading operation conditions, dose rate monitoring, leak test of the steam generator system, free flow water test of the STC lid connections, installation and torquing of the STC lid, leak rate test of the lid seals, establishment of steam vapor space, pressure rise test, leak rate test of the port cover plates, and installation of the HI-TRAC top lid.
The inspectors observed load handling and fuel loading operations at lP3 (Phase ll).
The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: installation of the centering assembly in the HI-TRAC, use of the FSB overhead crane to lift the STC out of the HI-TMC and into the SFP, removing the STC lid, installing and removing the cell blocker, installing and removing a dummy spent fuel assembly, installing the STC lid remotely, removing the STC from the SFP, dose rate monitoring of the STC lid, removal of water out of the STC, performing emergency manual crane operations, and placing the STC into the HI-TRAC.
The inspectors observed inter-unit transfer between lP3 and lP2 (Phase lll). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: placement of the HI-TRAC with STC on the air pallet system outside lP3 fuel storage building (FSB) truck bay, moving the HI-TRAC/STC into and out of the lP3 FSB using the air pallet system, use of the vertical cask transporter (VCT) to transport the HI-TRAC/STC from lP3 and lP2, lowering the HI-TRAC/STC onto the lP2 low profile transporter (LPT), moving the HI-TRAC/STC into lP2 using the LPT and the tugger vehicle, and using the rail system to move the HI-TRAC/STC to the staging position in the lP2 truck bay.
The inspectors observed load handling and fuel unloading operations at Unit 2 (Phase lV). The inspectors verified the following activities were performed in accordance with the TS and Entergy's procedures: verification of the SFP boron concentration, venting the pressure from the HI-TRAC cavity, removing the HI-TRAC lid, venting the pressure from the STC cavity, preparing the STC lid for SFP operations, use of the gantry crane to transfer the STC into the SFP, removing the STC lid under water, removing a dummy fuel assembly in the STC, removing the STC from the SFP, and performing emergency manualgantry crane operations with the STC.
The inspectors reviewed Entergy's inter-unit fuel loading, unloading, and processing procedures to ensure that they contained commitments and requirements specified in the operating license amendment, the safety evaluation report (SER), TS, and the Holtec Licensing Report. The inspectors also reviewed the procedures and information related to selection of spent fuel and non-fuel hardware for transfer in the STC. The inspectors verified that the spent fuel and non-fuel hardware for the first transfer met the TS for loading in the STC. The inspectors also reviewed the move sheet that indicated the locations where the assemblies and hardware were to be placed in the lP2 spent fuel pool and compared the move sheet against the requirements described in lP2 TS.
The inspectors also verified that:
- (1) preoperational procedures for inter-unit fuel transfer activities were prepared, reviewed, and initially approved in accordance with Entergy's administrative procedures;
- (2) Entergy personnel conducting the preoperational test activities had a clear understanding of their duties and responsibilities;
- (3) equipment used during preoperational test activities had been tested and evaluated for its impact on plant structures, systems, and components before performance of preoperational tests;
- (4) equipment used during preoperationaltest activities met maintenance criteria required by the manufacturer and Entergy;
- (5) Entergy implemented the site radiological protection program for activities such as contamination controls, temporary shielding, distance, and surveys (including neutron surveys as required by the TS); and
- (6) Entergy performed management and quality assurance reviews on preoperational test activities.
The inspectors also reviewed corrective action reports on issues that could affect preoperational inter-unit transfer activities to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance.
Findinqs No findings were identified.
.2 Initial Inter-Unit Fuel Transfer
a. Inspection Scope
The inspectors observed Entergy's initial inter-unit fuel transfer of 12 spent fuel assemblies from lP3 to lP2 on September 16-20, and 23-25,2012. The inspectors verified compliance with Entergy's operating license amendment, SER, Holtec Licensing Report, TS, NRC regulations, and Entergy procedures.
The inspectors attended pre-job briefs and verified that the briefs emphasized the critical steps and reviewed the conditions in the work areas. The inspectors interviewed personnel and ensured they were trained and knowledgeable regarding the tasks to be performed. In addition, training records were reviewed to ensure personnel were qualified to perform their assigned tasks.
The inspectors observed the loading of spent fuel assemblies from the lP3 SFP into the STC, placing of the lid on the STC, and heavy load movement of the STC from the lP3 SFP into the HI-TRAC in the lP3 FSB truck bay. The inspectors observed STC processing operations including: STC closure operations and preparation of the STC for transfer between lP3 and lP2 (including verifying the loading operations conditions, dose rate readings on the side of the HI-TRAC, leak testing of the steam generator system, free flow water test of the STC lid connections, installation and torquing of the lid studs and nuts, leak rate test of the lid seals, establishment of the steam vapor space, pressure rise test, leak rate test of the port cover plates, and installation of the HI-TRAC top lid). In addition the inspectors observed the movement of the STC from lP3 to lP2; and placing the STC and unloading spent fuel assemblies into the lP2 SFP. During performance of these activities, the inspectors verified that procedure use, communication. and coordination of inter-unit fuel transfer activities met established standards and requirements.
The inspectors reviewed maintenance records and verified that equipment used during operational activities met maintenance criteria required by the manufacturer and Entergy. In addition, the inspectors verified Entergy performed management and quality assurance reviews during initial transfer operations.
The inspectors reviewed radiation protection procedures, radiation work permits (RWPs), and the established radiological controls associated with the inter-unit fuel transfer. The inspectors assessed whether workers were aware of the radiological conditions in their work area and the RWP controls/limits. The inspectors reviewed radiological records from the first fuel transfer to confirm that radiation survey levels measuied were within limits established in the TS and consistent with values specified in the Holtec Licensing Report.
The inspectors reviewed corrective action reports and the associated follow-up actions that were generated since the pre-operational dry run activities to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance.
b.
Findinqs No findings were identified.
40A6 Meetinqs, includinq Exit On October 25,2012, the team presented the results via telephone to Don Mayer, the senior management representative for the inter-unit fuel transfer project; Joe Defrancesco, prgect manager; and other Entergy personnel. Bridget Frymire, Power Systems Operations Specialist for the New York State Department of Public Service, also participated in the exit meeting. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
- Supplementary Information
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
PARTIAL LIST OF PERSONS CONTACTED
Indian Point
J. Defrancesco Project Management
L. Gary Quality Assurance
R. Jones Dry Cask Storage
M. Laham Project Management
T. Linke Dry Cask Storage
D. Mayer Senior Management Representative
R. Miller Project Management
F. Mitchell Radiation Protection
W. Osmin Reactor Engineering
T. Pasko Dry Cask Storage Supervisor
C. Patterson Dry Cask Storage Supervisor
W. Riggs Project Management
T. Salentino Dry Cask Storage Superintendent
S. Stevens Radiation Protection Supervisor
J. Stewart Radiation Protection
C. Tippin Reactor Engineering
S. Traditi Dry Cask Storage
R. Waters Licensing
C. Weber Dry Cask Storage
NRC
- J. Boska NRR, Project Manager
- D. Pickett NRR, Project Manager
ITEMS OPEN. CLOSED. AND DISCUSSED
Opened/Closed/Discussed
None
LIST OF DOCUMENTS REVIEWED
