IR 05000286/2012009

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

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 STATES NUCLEAR REGULATORY COMMISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE 1OO KING OF PRUSSIA, PENNSYLVANIA 19406.27 13 November 28.2012 Mr. John Ventosa. Site Vice President Entergy Nuclear Operations, Inc.Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 1051 1-0249

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,Docket No.: License No.:

Enclosure:

cc w/encl: Marc S. Ferdas, Chief Decommissioning Branch Division of Nuclear Materials Safety 50-286 DPR-64 I nspection Report 05000286/20 1 2009

w/Attachment:

Supplementary lnformation 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.

4.4045.1 a.3

REPORT DETAILS

orHER ACTTVTTES (OA)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).Pre-operational Test Prooram (60845)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 Enclosure 4 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 a.5 Initial Inter-Unit

Fuel Transfer (60845)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.Enclosure b.6 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.

Findinqs No findings were identified.

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.Attachment:

Supplementary Information 40A6 Enclosure A-1

=SUPPLEMENTARY

INFORMATION=

KEY POINTS OF CONTACT

PARTIAL LIST OF PERSONS CONTACTED Indian Point J. Defrancesco

L. Gary R. Jones M. Laham T. Linke D. Mayer R. Miller F. Mitchell W. Osmin T. Pasko C. Patterson W. Riggs T. Salentino S. Stevens J. Stewart C. Tippin S. Traditi R. Waters C. Weber NRC J. Boska D. Pickett Project Management

Quality Assurance Dry Cask Storage Project Management

Dry Cask Storage Senior Management

Representative

Project Management

Radiation

Protection

Reactor Engineering

Dry Cask Storage Supervisor

Dry Cask Storage Supervisor

Project Management

Dry Cask Storage Superintendent

Radiation

Protection

Supervisor

Radiation

Protection

Reactor Engineering

Dry Cask Storage Licensing Dry Cask Storage NRR, Project Manager NRR, Project Manager ITEMS OPEN. CLOSED. AND DISCUSSED Opened/Closed/Discussed

None Attachment

LIST OF DOCUMENTS

REVIEWED Procedures

0-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 and Functional 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 Reports cR-lp3-2012-2528, CR-tp2-2012-5203, CR-lP3-2012-2512, CR-lP3-2012-2573, CR-1P2-2012-

209, 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

2-3620 Maintenance

Work Orders

Work Order

298588-41, "Transfer Spent Fuel From U3 SFP to U2 SFP, Troubleshoot

U2 FSB Crane 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

Miscellaneous

0-NF-203, Rev 8, "lnternal Transfer of Fuel Assemblies and Inserts," Attachment

"15x15 Fuel Assembly Visual Inspection Instructions," both the instructions and sheet completed for the assemblies to be loaded into STCl CASKLOADE

R_FU EL_l N SE RT-] N FO.xls Cycle_status.xls

EN-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 showing various identified

lP3 leaking assemblies and repairs to FA X-60, dated October 3,2007

FSRT-12-19, a Westinghouse Proprietary Class 2 document titled "Summary of Sipping Results for lndian Point Unit 3 2012 Canister Sipping Campaign" dated March 9,2012

FSRT-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 12,2012 Entergy Nuclear Indian Point 2, LLC Entergy Nuclear Operations Inc. Docket No. 50-247 lndian Point Nuclear Generating Unit No.2 Amendment No. 268 To Facility Operating License No.DPR-26 Entergy Nuclear Indian Point 3, LLC Entergy Nuclear Operations Inc. Docket No. 50-286 Indian Point Nuclear Generating Unit No.3 Amendment No. 246 To Facility Operating License No.DPR-64 Holtec Information Bulletin #56 Re-examining the ANSI 14.6 Compliance of Round Bars in Lifting Apparatus Using State-ofthe-Art Finaite Element Methods Inter-Unit FuelTransfer Pre-Operational Testing and Training Exercise Plan Licensee Event Report (LER) No. 2012-002-00

Technical Specification Prohibited Condition Caused by New FuelAssemblies Stored in a Configuration Prohibited by the TS lP2_SFP_Map.xls

lP3 FSAR (Rev 4., 2011) Pgs 43-53 I P3_Fuel-Characteristics.

xls lP3_SFP_Map.xls

I P3_F U E L_CATEGO R IZATI O N-TYP E. xls Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center, Rev. 6, Holtec Report No. Hl-2094289, April2012 Move Sheet Unload

STC1.Pdf Move Sheet Load

STC1.Pdf NF-lN-10-40

a Westinghouse Proprietary Class 2 letter titled "Core ComponenUFuel Assembly Storage Compatibility Analysis for INEQ (PDM-10-107)' for lP3 and dated November 1 , 2010.The aitachment, "INEQ Core Component/FuelAssembly Storage Compatibility Summary" is dated September

2Q, 2010 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 268 to Facility Operating License No.

DPR-26 and Amendment No. 246 to Facility Operating License No.

DPR-64 Entergy Nuclear Operations, lnc. lndian Point Nuclear Generating Unit Nos. 2 and 3 Docket Nos. 50-247 and 50-286, July 2Q12 StructuralAnalysis of Shielded Transfer Canister Lifting Device for Entergy lP3, Holtec Report No. Hl-2094412

Structural Analysis of STC Lift Hook Assembly, Holtec Report No. Hl-2094435

FSB ISFSI LPT OA RWP SER SFP STC TS VCT A-4

LIST OF ACRONYMS

USED Fuel Storage Building Independent

Spent Fuel Storage Installation

Low Profile Transporter

Other Activities

Radiation

Work Permit Safety Evaluation

Report Spent Fuel Pool Shielded Transfer Canister Technical

Specifications

Vertical Cask Transporter

Attachment