ML072600140

IR 05000280-07-006; 05000281-07-006; and 07200055-07-001, on 06/18/2007 - 08/03/2007, Surry Power Station Independent Spent Fuel Storage Installation (ISFSI) Dry Run and Initial Loading Inspection Report

ML072600140
Person / Time
Site:	Surry, 07200055
Issue date:	09/14/2007
From:	Vias S NRC/RGN-IV/DRP
To:	Christian D Virginia Electric & Power Co (VEPCO)
Shared Package
ML072600136	List: IR 05000280/2007006 ML072600140 ML072600147
References
IR-07-001
Download: ML072600140 (14)

See also: IR 05000280/2007006

Text

September 14, 2007Virginia Electric and Power CompanyATTN: Mr. David A. Christian

Sr. Vice President and

Chief Nuclear Officer

Innsbrook Technical Center - 2SW

5000 Dominion Boulevard

Glen Allen, VA 23060-6711SUBJECT:SURRY POWER STATION - INSPECTION REPORT NOS. 05000280/2007006;05000281/2007006; AND 07200055/2007001Dear Mr. Christian:

This inspection report covers two visits made by the United States Nuclear RegulatoryCommission (NRC) to your Surry Power Station Independent Spent Fuel Storage Installation

(ISFSI) between June 18 and August 3, 2007. The purpose of the site visits was to inspect

your dry fuel storage pre-operational testing activities and to observe your first loading of the

NUHOMS-HD storage system. The first NUHOMS-HD canister was loaded and placed in

storage at the ISFSI on August 6, 2007. The enclosed inspection report documents the results

of the inspection, which were discussed on August 2, 2007, with Mr. B. L. Stanley and other

members of your staff. Based on results of this inspection, no violations or findings of

significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, itsenclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publically Available Records (PARS) component of NRC's document system

VEPCO- 2 -(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. (The Public Electronic reading Room).Sincerely,/RA/Steven Vias, ChiefTechnical Support Branch

Division of Reactor ProjectsDocket Nos.:50-280; 50-281; 72-055License Nos.:DPR-32, DPR-37Enclosure:Surry Power Station - Independent Spent Fuel Storage Installation(ISFSI) Dry Run and Initial

Loading Inspection Report

Attachments:1.Supplemental Information2.Inspector Notes

VEPCO- 2 -

2(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. (The Public Electronic reading Room).Sincerely,/RA/Steven Vias, ChiefTechnical Support Branch

Division of Reactor ProjectsDocket Nos.:50-280; 50-281; 72-055License Nos.:DPR-32, DPR-37Enclosure:Surry Power Station - Independent Spent Fuel Storage Installation(ISFSI) Dry Run and Initial

Loading Inspection Report

Attachments:1.Supplemental Information2.Inspector NotesSUNSI Review Completed: SPA ADAMS:

O Yes G No Initials: SPA

O Publicly Available

G Non-Publicly Available

G Sensitive

O Non-SensitiveDOCUMENT NAME: RIV:DNMS:FCDBRIV:DNMS:FCDBRIV:DNMS:FCDBRIV:DRPSP AtwaterEM GarciaRL KellarMA SitekSPA by emailEMGby emailRLK2 by emailMAS3 by email09/13/0709/06/0709/13/0708/31/07SFSTSFSTSFSTC:TSB/DRPBP TripathiZL Cruz-PerezMG KarmisSJ ViasBPT by emailZLC by emailMGK by emailSJV09/07/0709/07/0709/11/0709/14/07OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax I:\RPB5\Surry\Reports\2007\Surry Inspection Report Final 9-11-07.wpd

VEPCO- 3 -cc w/encl:Chris L. Funderburk, Director

Nuclear Licensing andOperations SupportVirginia Electric & Power Company

Electronic Mail DistributionDonald E. JerniganSite Vice President

Surry Power Station

Virginia Electric & Power Company

Electronic Mail DistributionVirginia State Corporation CommissionDivision of Energy Regulation

P. O. Box 1197

Richmond, VA 23209Lillian M. Cuoco, Esq.Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail DistributionAttorney GeneralSupreme Court Building

900 East Main Street

Richmond, VA 23219

VEPCO- 4 --4-Report to David A. Christian from Steven J. Vias dated September 14, 2007SUBJECT:SURRY POWER STATION - INSPECTION REPORT NOS. 05000280/2007006;05000281/2007006; AND 07200055/2007001Distribution w/encl:

S. P. Lingam, NRRC. Evans

L. Slack, RII EICS

B. Spitzberg, RIV

R. Kellar, P.E., RIV

R. Temps, NMSS/SFST

E. Ziegler, NMSS/SFST

R. Reyes, RII SRI

OE Mail

RIDSNRRDIRS

PUBLIC

Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket Nos.:50-280, 50-281, 72-055License:DPR-32, DPR-37Report No:05000280/2007006; 05000281/2007006; and 07200055/2007001Licensee:Virginia Electric and Power Company (VEPCO)Facility:Surry Power Station, Units 1 & 2Location:5850 Hog Island RoadSurry, VA 23883Dates:June 18 through August 3, 2007

Inspectors:Scott AtwaterRegion IV DNMS Inspector - Team LeaderEmilio GarciaRegion IV DNMS Inspector

Mark Sitek Region IV Resident Inspector - San Onofre

Steven ViasRegion II DRS Inspector

Michael Karmis SFST Senior Safety Inspector

Bhasker (Bob) TripathiSFST Technical Review Directorate

Zahira Cruz-PerezSFST Technical Review DirectorateCrane Licensing

Research:Ray Kellar, P.E. Region IV DNMS InspectorApproved By:Steven Vias, ChiefTechnical Support Branch

Division of Reactor ProjectsAttachments:Supplemental InformationInspector Notes

Enclosure EXECUTIVE SUMMARYSurry Power StationNRC Inspection Report 05000280/2007006; 05000281/2007006; and 07200055/2007001Virginia Electric and Power Company (VEPCO) had selected the NUHOMS-HD HorizontalModular Storage System for dry storage of spent nuclear fuel at the Surry Power Station. The

Nuclear Regulatory Commission (NRC) had certified the NUHOMS-HD cask system for storage

of irradiated fuel under Certificate of Compliance No. 72-1030 on January 10, 2007.On June 18-22, 2007, a team of 7 inspectors performed two evaluations. The first evaluationwas to determine if the ISFSI personnel had been trained, the equipment had been tested, and

the procedures had been developed to the extent necessary to safely load spent fuel into dry

storage at the ISFSI. The second evaluation was to determine if the Surry station programs

were adequate for continued maintenance and operation of the ISFSI once it was loaded. The

results of these two evaluations were discussed during a debriefing on June 22, 2007, with Mr.

Ken Grover and other members of the staff.On July 23-27, 2006, a Region IV DNMS inspector performed two evaluations. The first was todetermine if the Spent Fuel Cask Crane was in condition to safely handle the loaded transfer

cask. The second evaluation was to determine if the deficiencies identified during the team

evaluation conducted on June 18-22, 2007, had been adequately resolved and closed. The

results of these two evaluations were discussed during a debriefing on July 26, 2007, with Mr.

Matt Adams and other members of the staff.On July 30 through August 3, 2007, a Region IV DNMS inspector observed the first loading ofspent fuel into dry storage using the NUHOMS Storage System. The purpose was to verify the

first loading was performed safely, in accordance with approved procedures, and within the

Technical Specification limits. The results of this evaluation were discussed during the exit

meeting on August 2, 2007, with Mr. B. L. Stanley and other members of the staff.The following provides a summary of the results of the inspection. Details are provided in theInspector Notes contained in Attachment 2 to this report.Spent Fuel Cask Crane*The crane design features for load control were intact, operable, and properly rated for theapplication. The design features included the hoist and trolley brakes, crane remote control

system, and hoist minimum wire rope breaking strength

(Attachment 2, Crane Design, Pages 1-2).*The crane, hooks, and wire rope were inspected and maintained in accordance with theASME Code and the crane manufacturer's instructions

(Attachment 2, Crane Inspection/Maintenance, Pages 3-6).*The crane configuration had been maintained in conformance with its licensing basis(Attachment 2, Crane Licensing Basis, Pages 6-7).

-3-Enclosure *The crane had been load tested and operated in accordance with the ASME Code(Attachment 2, Crane Load Testing and Crane Operation, Pages 8-11).Canister Drying and Helium Backfill Operations*The canister was vacuum dried and backfilled with helium to the pressures specified byTechnical Specifications. The drying and backfilling operations were completed within the

time limits specified (Attachment 2, Drying/Helium Backfill, Pages 12-13).Emergency Planning*The Emergency Plan had been expanded to include the ISFSI. Emergency Action Levels(EALs) had been developed for accidents involving the ISFSI.

(Attachment 2, Emergency Planning, Pages 13-14).Fire Protection*The Fire Protection Plan had been expanded to include the ISFSI, and emergency responsetraining had been provided for off-site responders (Attachment 2, Fire Protection, Page 14).Fuel Selection and Verification*The spent fuel assemblies selected for loading into the first NUHOMS-HD canister met theTechnical Specification requirements for assembly type, cladding integrity, decay heat load,

and physical design characteristics (Attachment 2, Fuel Selection/Verification, Pages 15-17).*A canister loading plan had been developed based on the combination of spent fuelassembly enrichment, burnup, cooling time and decay heat

(Attachment 2, Fuel Selection/Verification, Page 17).*The non-fuel assembly hardware (NFAH) selected for loading into the first NUHOMS-HDcanister met the Technical Specification requirements for burnup and decay heat load

(Attachment 2, Fuel Selection/Verification, Page 18).*The Technical Specification actions required for spent fuel mis-loading had beenincorporated into the loading procedure (Attachment 2, Fuel Selection/Verification, Page 18).General License Conditions*The NUHOMS-HD cask design was compatible with the Surry Power Station 10 CFR Part 50requirements. There were no items identified that required NRC review or approval prior to

use of the NUHOMS-HD system (Attachment 2, General License, Page 19).*The licensee had calculated the dose to the public at the site boundary from a worst caseaccident during ISFSI operations. The dose was within the limits allowed by 10 CFR 72.106

(Attachment 2, General License, Page19).

-4-Enclosure *The licensee had calculated the dose to the public at the site boundary from normal ISFSIoperations. The dose was within the limits allowed by 10 CFR 72.104

(Attachment 2, General License, Page 20).*The soil structure under the ISFSI pad was determined not to be subject to liquefactionduring a Safe Shutdown Earthquake (Attachment 2, General License, Page 21).*The Horizontal Storage Modules (HSMs) were placed on the ISFSI pad in an array that wasconsistent with the Technical Specifications (Attachment 2, General License, Page 21).*The NUHOMS-HD cask system design parameters were bounded by the Surry PowerStation reactor site parameters (Attachment 2, General License, Pages 21-24).Heavy Loads and Rigging*All lifts of the transfer cask and canister were made under the Surry Power Station heavyloads requirements and procedures, as documented through a 10 CFR 50.59 evaluation

(Attachment 2, Heavy Loads and Rigging, Page 25).*A safe load path had been established for transfer cask movements, meeting therequirements of NUREG 0612 (Attachment 2, Heavy Loads and Rigging, Page 25).*Maximum lifting heights had been established for the transfer cask to ensure that a dropwould not result in dose rates at the site boundary in excess of the 10 CFR Part 100 limits.

These lifting heights were consistently implemented during the first NUHOMS cask system

loading (Attachment 2, Heavy Loads and Rigging, Page 26).Procedures and Technical Specifications*Procedures were established to ensure that the NUHOMS-HD cask storage system technicalspecification requirements for inspection, maintenance, operation and surveillance were

implemented. These procedures were implemented during the first NUHOMS cask system

loading (Attachment 2, Procedures and Tech Specs, Pages 27-29).Quality Assurance*The licensee's 10 CFR Part 50 Quality Assurance Program had been expanded to includethe ISFSI. The licensee had established measures for ensuring that: instruments used to

verify compliance with the Technical Specifications were calibrated; conditions adverse to

quality were promptly identified and corrected; dry fuel storage components were properly

stored to prevent degradation; and purchased material equipment and services conformed

to procurement documents (Attachment 2, Quality Assurance, Pages 30-32).

-5-Enclosure Radiation Protection*Measures were established to limit personnel exposures to as low as reasonably achievable(ALARA). Considerations for exposure and contamination control had been incorporated

into the procedures for canister gas sampling and reflooding during unloading. The transfer

cask annulus seal survey was accomplished in the proper sequence to ensure the canister

did not exit the building with contamination above the limits. The total exposure projected for

the first canister was 0.703 person-rem and the actual was 0.581 person-rem. This was

consistent with an industry range of 0.300 to 0.700 person-rem for first loadings

(Attachment 2, Radiation Protection, Pages 33-34).*Criticality prevention and monitoring during cask loading was implemented. The minimumspent fuel pool boron concentration required by Technical Specifications was established.

Criticality monitoring and alarm systems were installed in all areas where spent fuel was

handled (Attachment 2, Radiation Protection, Pages 35-36).*The licensee had performed an analysis to confirm that the limits of 10 CFR 72.104 wouldnot be exceeded during normal operation of the ISFSI when fully loaded. The Horizontal

Storage Module (HSM) dose rates had been established based on the analysis

(Attachment 2, Radiation Protection, Page 37).

Records*The licensee had established measures to ensure the 10 CFR 72.212 Report, Certificate ofCompliance, and related documents were maintained for as long as spent fuel was stored at

the ISFSI (Attachment 2, Records, Page 38).*The licensee had made the required 90 day notification to the NRC prior to loading their firstcask, and had established procedural requirements to register each cask with the NRC

within 30 days after loading (Attachment 2, Records, Pages 38-39).*The licensee had established records for Special Nuclear Material (SNM) accountability. The records were complete and included transfer of spent fuel to the ISFSI

(Attachment 2, Records, Page 39).Special Lifting Devices*The licensee had ensured that all special lifting devices were subjected to initial load testingand were incorporated into the Surry Power Station 10-year In-Service Inspection (ISI)

program for continuing compliance (Attachment 2, Special Lifting Devices, Pages 39-41).*The licensee had established procedures to ensure that all special lifting devices wereinspected prior to use and had established programs to ensure that all major maintenance or

alterations were followed by a repeat of the initial load testing

(Attachment 2, Special Lifting Devices, Pages 41-42).

-6-Enclosure Training*The NUHOMS-HD vendor (AREVA) provided training to the Surry Power Station ISFSIpersonnel. The licensee had reviewed and accepted the vendor training under the Surry

Power Station 10 CFR Part 50 Training Program. Only those personnel who had completed

all phases of the training were certified to operate the ISFSI equipment and systems

(Attachment 2, Training, Pages 43-44).*The training had been conducted in the classroom and in the field. The classroom trainingused the training modules that were developed in conformance with the NUHOMS FSAR

requirements. The field training had been conducted during the dry run training exercise

(pre-operational testing). The tasks that were taught during the dry run were consistent with

the conditions of the Certificate of Compliance. All ISFSI personnel had completed the

training (Attachment 2, Training, Pages 45-46).Welding*Hydrogen monitoring was implemented during welding of the first NUHOMS-HD canister. The canister unloading procedure required hydrogen monitoring during lid cutting.

(Attachment 2, Welding and Weld Testing, Page 48).

Attachment 1Page 1 of 3Supplemental InformationPARTIAL LIST OF PERSONS CONTACTEDLicensee PersonnelD. Anderson - Health PhysicistL. Baker - Supervisor, Nuclear Shift Operations

A. Barbee - Manager, Training

W. Belcher - Nuclear Security Shift Supervisor

T. Brookmire - Supervisor, Nuclear Engineering

J. Costello - Supervisor, Emergency Preparedness

J. Curry - Supervisor, Materials Verification

R. Dillard, Jr. - Fire Protection Engineering Programs - Appendix R

A. Ewell - Supervisor, Fuel Handling

M. Fanguy - Lead Reactor Engineer

W. Ford - Senior Instructor

B. Garber - Supervisor, Licensing

J. Grau - Manager, Nuclear Oversight

F. Grover - Manager, Operations

D. Jernigan - Site Vice President

R. Johnson - Supervisor, Operations Support

L. Jones - Manager, Radiation Protection and Chemistry

J. Keithley - Supervisor, Health Physics Technician Services

J. Knapp - Nuclear Specialist

J. Kubovcik - Unit Supervisor

M. Laidlow - Fuel Accountability and Inspection Specialist

A. LeClerc - Supervisor, Materials Verification

J. Lyons - Control Room Operator

T. Nieme, Nuclear Engineer III, Licensing

T. Ragland - Supervisor, Health Physics Operations

C. Redman - Supervisor, Records

R. Robins - Engineer, Nuclear Fuels

K. Robinson - Mechanic

L. Rollings - Station ALARA Coordinator

R. Savedge, Emergency Preparedness Specialists-Offsite Coordinator

L. Hilbert-Semmes - Corrective Action Program Manager

R. Simmons - Acting Plant Manager

K. Sloane - Plant Manager

B. Stanley - Acting Plant Manager

J. Sukosky - Health Physicist II

B. Taylor - Senior Instructor

B. Wakeman - Engineer III, Corporate Nuclear Analysis and FuelsD. Williams - Supervisor, Nuclear Site Safety

J. Wright - Health Physics Shift Supervisor

A. Xenakis - Control Room Operator

C. Zalesiak, Engineer III, Corporate Civil Engineering

R. Szczypinski, Jr. - Mechanic

Attachment 1Page 2 of 3Contractor PersonnelJ. Boshoven - Senior Project Manager, TransnuclearB. Cheek - Health Physics Technician

W. Rodgers - Project Engineer, Transnuclear

B. Speckline - Supervisor, Fuel Handling - North AnnaINSPECTION PROCEDURES USED60854.1Pre-operational Testing of Independent Spent Fuel Storage Installations atOperating Plants60855.1Operation of an Independent Spent Fuel Storage Installation at Operating Plants

60856.1Review of 10 CFR 72.212(b) Evaluations at Operating PlantsLIST OF ITEMS OPENED, CLOSED, AND DISCUSSEDOpened and Closed

None.DiscussedNone. LIST OF ACRONYMS USEDALARAAs Low As Reasonably AchievableANSIAmerican National Standards Institute

ASMEAmerican Society of Mechanical Engineers

BPRABurnable Poison Rod Assembly

CoCCertificate of Compliance

dpmDisintegrations Per Minute

DBEDesign Basis Earthquake

EABExclusion Area Boundary

EALEmergency Action Level

EPIPEmergency Plan Implementing Procedure

GWD/MTUGigawatt Days per Metric Ton Uranium

HSMHorizontal Storage Module

ISFSIIndependent Spent Fuel Storage Installation

ISIIn-Service Inspection

JPMJob Performance Measure

kWKilowatt

LLWSFLow Level Waste Storage Facility

Attachment 1Page 3 of 3M&TEMeasuring and Test EquipmentMBRMaterial Balance Report

mslMean Sea Level

NCRNon-Conformance Report

NFAHNon Fuel Assembly Hardware

NRCNuclear Regulatory Commission

ppmParts Per Million

psfPounds Per Square Foot

PTLiquid Penetrant Testing

RCCRod Control Cluster

ref-cc/secReference Cubic Centimeters Per Second

RWPRadiation Work Permit

SATSystematic Approach to Training

SERSafety Evaluation Report

SNMSpecial Nuclear material

SSCStructures, Systems, and Components

SSESafe Shutdown Earthquake

SSISoil Structure Interaction

TEDETotal Effective Dose Equivalent

TERTechnical Evaluation Report

TPAThimble Plug Assembly

UFSARUpdated Final Safety Analysis Report

VPIVibration Suppression Insert

wt. %Weight Percent