IR 05000286/2012009
| ML12339A250 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/28/2012 |
| From: | Ferdas M S Decommissioning Branch I |
| To: | Ventosa J Entergy Nuclear Operations |
| References | |
| IR-12-009 | |
| Download: ML12339A250 (13) | |
Text
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
SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 3 _ INTER-UNIT SPENT FUELTRANSFER INSPECTION REPORT NO. O5OOO28612012009
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).
Sincerely,Docket No.:License No.:
Enclosure:
cc w/encl:Marc S. Ferdas, ChiefDecommissioning BranchDivision of Nuclear Materials Safety50-286DPR-64I nspection Report 05000286/20 1 2009
w/Attachment:
Supplementary lnformationDistribution 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 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
4.4045.1a.3
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
.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
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
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
PARTIAL LIST OF PERSONS CONTACTEDIndian Point
- 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
A-2
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,
- 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
- 2-2036, C R- l P2-20 1
- 2-3620Maintenance Work OrdersWork Order
- 298588-41, "Transfer Spent Fuel From U3 SFP to U2 SFP, Troubleshoot U2 FSBCrane Girder Control"Work Order
- 52344241-01, "Perform Annual DCS Lift Devices lnspections"Work Order
- 00325861-02, "Return STC Back lnto the Unit 3 SFP"Attachment
- 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) Pgs43-53I 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
- STC1.PdfMove Sheet Load
- 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