ML072600140
ML072600140 | |
Person / Time | |
---|---|
Site: | Surry, 07200055 ![]() |
Issue date: | 09/14/2007 |
From: | Vias S NRC/RGN-IV/DRP |
To: | Christian D A Virginia Electric & Power Co (VEPCO) |
Shared Package | |
ML072600136 | List: |
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