IR 05000220/2012009

IR 05000220-12-009 and 05000410-12-009, on 7/23/12 - 9/19/12, NMPNPS, Preoperational Testing of ISFSI at Operating Plants, Review of 10 CFR 72.212(b) Evaluations, and Operation of ISFSI's at Operating Plants

ML12299A355
Person / Time
Site:	Nine Mile Point
Issue date:	10/25/2012
From:	Ferdas M S Decommissioning Branch I
To:	Langdon K Nine Mile Point 3 Nuclear Project
References
IR-12-009
Download: ML12299A355 (11)

Text

October 25,2012Mr. Kenneth Langdon, Site Vice PresidentNine Mile Point Nuclear Station, LLCP.O. Box 63Lycoming, NY 13093-0063

SUBJECT: NINE MILE POINT NUCLEAR STATION - NRC INDEPENDENT SPENT FUELsroRAGE TNSTALLATTON (lSFSl) INSPECTION REPORT NOS.05000220t201 2009 AN D 05000 41 0 1201 2009

Dear Mr. Langdon:

On September 14,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an ISFSIinspection at your Nine Mile Point Nuclear Station, Units 1 and 2. The enclosed inspectionreport documents the inspection results which were discussed on September 19, 2012, withKen Phy, ISFSI Project Manager, and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your license.The inspectors reviewed selected procedures and records, observed activities, and interviewedpersonnel.Based on the results of this inspection, no findings were identified.ln accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letter, itsenclosure, and your response (if any) will be available electronically for public inspection in theNRC Public Document Room or from the Publicly 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,/(" >,4A -Marc S. Ferdas. ChiefDecommissioning BranchDivision of Nuclear Materials SafetyDocket Nos. : 50-220, 50-410, 72-1036License Nos.: DPR-63, NPF-69

Enclosure:

lnspection Report 0500022012012009 and 0500041012Q12O09M

Attachment:

Supplementary Informationcc w/encl: Distribution via ListServ

SUMMARY OF FINDINGS

lR 0500022012012009 and 0500041012012009:0712312012-0911412012; Nine Mile PointNuclear Station, Units 1 and 2; Preoperational Testing of lndependent Spent Fuel Storagef nstallations (lSFSl) at Operating Plants, Review of 10 CFR 72.212(b) Evaluations, andOperation of ISFSI's at Operating Plants.This report covers the ISFSI operational dry run and initial loading inspection conducted by ateam of six NRC inspectors. The NRC's program for overseeing the safe operation ofcommercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process,"Revision 4, dated December 2006.No findings were identified.Enclosure

3

REPORT DETAILS

4. OTHER ACTTVTTTES (OA)4OA5 Other Activities.1 Preooerational Test Proqram (60854, 60854.1. and 60856)a. Inspection ScopeThe inspectors evaluated NMPNS's performance during NRC observed pre-operationaldry run activities that were performed in order to fulfill requirements in TechnicalSpecifications (TS) 1.1.6. The inspectors observed NMPNS dry run activities on July 23-26,2012, and August 27-31,2012. During the first week the inspectors observed caskprocessing activities including: blowdown, vacuum drying, helium backfilling, reflooding,gas sampling, welding, non-destructive examinations, and helium leak testing. Duringthe second week the inspectors observed canister loading operations including:insertion and removal of the dry shielded canister (DSC) from the transfer cask (TC),movement of the TC/DSC into the spent fuel pool, movement of a dummy fuel assemblyinto several locations in the DSC, removal of the TC/DSC from the spent fuel pool,moving of the TCIDSC to the cask processing area, down-ending the TC onto thetransporter, transporting the TC to the ISFSI pad, and retrieving and inserting a weightedDSC into a horizontalstorage module (HSM).The inspectors reviewed DSC loading, unloading, and processing procedures to ensurethat they contained commitments and requirements specified in the Certificate ofCompliance (CoC), TS, Final SafetyAnalysis Report (FSAR), and Title 10 of the Code ofFederal Regulations (CFR) Part7Z. The inspectors reviewed the ISFSI seismiccalculations and the analysis of the heavy haul path from the reactor building to the ISFSIpad. Also, the inspectors reviewed fuel selection procedures to ensure theyappropriately incorporated the requirements in the TS.The inspectors evaluated NMPNS's compliance with the requirements of 10 CFR 72.212and 10 CFR72.48. The inspectors verified NMPNS's written evaluations were inaccordance with 10 CFR72.212(bX2Xi) and confirmed: (1) the conditions set forth in theCoC had been met prior to use, (2) the ISFSI pad had been designed to support the loadof stored casks, and (3) the radiological requirements of 72.104 had been met. Theinspectors verified that applicable reactor site parameters, such as fire and explosions,tornadoes, wind-generated missile impacts, seismic qualifications, lightning, flooding andtemperature, had been evaluated for acceptability with bounding values specified in theFSAR and the NRC Safety Evaluation Report (SER). The inspectors also verified that a50.59 evaluation of the construction and operation of the ISFSI and plant interfaces werenot required and that ISFSI related work activities would not impact the safe operation ofNine Mile Point. Units 1 and 2.Enclosure b.a.4FindinqsNo findings were identified.Initial Loadinq of the ISFSI (60855 and 60855.1)Inspection ScopeThe inspectors observed and evaluated the licensee's loading of the first of six DSCsassociated with the initial ISFSI dry cask campaign on September 10-14, 2O12. Theinspectors also reviewed the licensee's planned activities related to long-term operationand monitoring of the lSFSl. The inspectors verified compliance with the CoC, TS,regulations, and station procedures.The inspectors observed the heavy load movement of the TC and loaded DSC from thespent fuel pool to the cask decontamination and processing area. The inspectors alsoobserved DSC processing operations including: decontamination and surveying, welding,non-destructive weld examinations, DSC draining, vacuum drying, and helium backfilling.During performance of these activities, the inspectors verified that procedure use,communication. and coordination of ISFSI activities met established standards andrequirements.The inspectors reviewed the licensee's program associated with fuel characterizationand selection for storage. The inspectors reviewed the first cask fuel selection packageto verify that the licensee was loading fuel in accordance with the CoC, TS, andprocedures.The inspectors reviewed radiation protection procedures and radiation work permits(RWPs) associated with the ISFSI loading campaign. The inspectors also reviewed theestablished radiological controls. The inspectors assessed whether workers were awareof the radiological conditions in their work area and the RWP controls/limits. Theinspectors reviewed radiological records from the first DSC loading to confirm thatradiation survey levels measured were within limits specified by the TS and consistentwith values specified in the FSAR.The inspectors performed a walk-down of the heavy haul path and toured the ISFSI padto assess the material condition of the pad and the HSMs. The inspectors also verifiedthat transient combustibles were not being stored on the ISFSI pad or the vicinity of theHSMs. The inspectors also confirmed that vehicle entry onto the ISFSI pad wascontrolled in accordance with procedures.The inspectors reviewed corrective action reports and the associated follow-up actionsthat were generated since NMPNS started planning for their initial ISFSI campaign toensure that issues were entered into the corrective action program, prioritized, andevaluated commensurate with their safety significance.Enclosure b.5FindinssNo findings were identified.Meetinqs. includino ExitOn September 19, 2012, the team presented the results via telephone to Ken Phy, ISFSIProject Manager, and Madhav Shanbhag, Licensing Engineer. The inspectors verifiedthat no proprietary information was retained by the inspectors or documented in thisreport.Attachment: Supplementary InformationEnclosure A-1

SUPPLEMENTARY INFORMATION

KEY POINTS OF CONTACT

PARTIAL LIST OF PERSONS CONTACTEDNMPNS

D. Bensel, Reactor EngineerG.Connor, Design Engineer

J. DeSando, Fleet MaintenanceJ.Henry, Radiation ProtectionJ.Jock, ISFSI ForemanJ.Kidd, Quality AssuranceM.Lavery, ISFSI Supervisor

P. Mills, Radiation ProtectionJ.Olmundsen, ISFSI SupervisorS.Penney, Reactor EngineerK.Phy, ISFSI Project ManagerM.Philippon, Plant General ManagerA.Ross, Reactor EngineerM.Shanbhag, Licensing EngineerT.Sollenberger, Radiation Protection .,

NRC Personnel

D.Dempsey, Resident InspectorE.Miller, Resident InspectorITEMS OPEN. CLOSED. AND DISCUSSEDOpened/Closed/DiscussedNone

LIST OF DOCUMENTS REVIEWED

ProcedureslNER-FU-045, Rev. 3,'lSFSl Bundle Characterization Data for NMP1 and NMP2"CNG-AM-1.01 -1006, "Qualification and Certification of NDE Personnel"CNG-MN-1.01-1003, Rev. 00400, "Load Handling"CNG-PR-2.01 -1 000, Revision 00200, "Document Control"CNG-PR-3.01 -1 000, Revision 00201, "Records Management"N1-ST-D2001, "lSFSl Daily Checks"N2-PM-SO14 Revision 15, "Building Rounds"Attachment

A-2NMP-

NDEP-PT-3.00, Rev. 01900, "Dye Penetrant Inspection"NMP-NDEP-SP-7.02, Revision 01 100, "Visual Examination of Welding Operations"NMP - Vendor Procedure -

MSLT-DSC0NMP, Rev. 0, "Helium Mass Spectrometer Leak TestProcedure"S-MMP-ISFSl-001, Rev. 00100,'lSFSl Equipment Preparation"S-MMP-ISFSl-002 Rev. 00100, "Dry Shielded Canister Pre-Use Inspection"S-MMP-lSFSl-003, Rev. 00000, "DSC Loading Operations"S-MMP-lSFSl-004, Rev. 00000, "DSC Sealing Operations"S-MMP-lSFSl-005, Rev. 00000, "Site Cask Transportation"S-MMP-lSFSl-006, Rev. 00000, "HSM Operations"S-MMP-lSFSl-007, Rev. 00000,'DSC Unsealing Operations"S-MMP-lSFSl-008, Rev. 00000,'DSC Unloading Operations"S-MMP-lSFSl-009, Rev. 00100, "Transfer Cask Annualand Pre-Use Inspection"S-MMP-lSFSl-010, Rev. 00000,'lSFSl Shipping Logistics"S-MMP-lSFSl-011 Revision 0, .lSFSl Abnormal Events"S-REP-S, Rev. 0, "Fuel Selection for

NUHOMS-618T Type A Basket DSC'S-REP-7, Rev. 0, 'NUHOMS DSC Verification and Inspection"S-RPIP-3.0, Rev. 01800, "Radiological Surveys"S-RPIP-5.1, Rev. 01000, "Dosimetry Use Placement and Dose Tracking"S-RPIP-5.3, Rev. 05, "Neutron Dose Assessment"CalculationsW-1-129, "Concrete Heavy Haul Path For lSFSl"W-1-134, "Underground Utilities Evaluation for The Nine Mile Point lSFSl, Phase 2"H21C11 1, Rev. 0, "Decay Heat Calculation for lSFSl"SORX261CMO1, "Evaluation For ISFSI Related Activities"SORX340CS09, "Spent Fuel Pool Structure Analysis For High Density Rack"SORX261CS06, "Evaluation Of Transfer Cask For Seismic Stability"Corrective Action Condition ReportsCR-20 1

2-002237, C R-2 0 1

2-0070 53, a n d C R-20 1

2-008494Drawinos09-000007, ISFSI Storage Area, Final Site Layout09-000008, ISFSI Pad and Approach Slabs09-00001 1, ISFSI Storage Area Grounding PlanMaintenance Work OrdersWork Order - C91432655Attachment

A-3MiscellaneousConstellation Energy Generation Group, LLC, "Quality Assurance Topical Report" Revision 6Duke Energy Letter to NRC, Cask Certificate of Compliance, Docket No. 72-1004, 30-DayReport for Higher Canister Heat Loading per General Requirement Section 1.1.7, datedAug ust 8, 2007 (ML07 2340622)lndependent Spent Fuel Storage installation Pre-Operational Testing Exercise Dry Run Plan,Welding Documents:

NMP-PQR-210R,

NMP-WPS-8-8-B-104, and

NMP-WPS-8-8-BA-102NMPNS Engineering Change Package 10-00034 revision 0, lmplement Dry Fuel Storage atNMP-ISFSl, Licensing ,212 Analyses, Programs, Procedures, and lmplementation ChangesNine Mile Point (Design Criteria Document 115 revision 1), Criteria for Seismic AnalysisProgress Energy Letter to NRC, "Registration and Use of Cask to Store Spent Fuel and SystemThermal Performance Assessment," dated February 24,2011 (ML1 10670429)Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation 10CFR72.212Evaluation Report for Docket 72-1036RWP-1 12014, ISFSI ActivitiesUpdated Final Safety Analysis Report for the Standardized NUHOMS@ Horizontal ModularSystem for lrradiated Nuclear Fuel in accordance with CoC Number 1004, Transnuclear ReportNo.: NUH-003

LIST OF ACRONYMS

USEDCF [[R Code of Federal RegulationsCoC Certificate of ComplianceDSC Dry Shielded CanisterFSAR Final Safety Analysis ReportHSM Horizontal Storage ModuleISFSI Independent Spent Fuel Storage InstallationNMPNS Nine Mile Point Nuclear StationNRG Nuclear Regulatory CommissionOA Other ActivitiesRWP Radiation Work PermitSER Safety Evaluation ReportTC Transfer CaskTS Technical SpecificationsAttachment]]