ML072600140
| 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: |
| References | |
| IR-07-001 | |
| Download: ML072600140 (14) | |
See also: IR 05000280/2007006
Text
September 14, 2007
Virginia Electric and Power Company
ATTN: Mr. David A. Christian
Sr. Vice President and
Chief Nuclear Officer
Innsbrook Technical Center - 2SW
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT: SURRY POWER STATION - INSPECTION REPORT NOS. 05000280/2007006;
05000281/2007006; AND 07200055/2007001
Dear Mr. Christian:
This inspection report covers two visits made by the United States Nuclear Regulatory
Commission (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, its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publically Available Records (PARS) component of NRCs 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, Chief
Technical Support Branch
Division of Reactor Projects
Docket Nos.: 50-280; 50-281;72-055
Enclosure:
Surry Power Station - Independent Spent Fuel Storage Installation(ISFSI) Dry Run and Initial
Loading Inspection Report
Attachments: 1. Supplemental Information
2. Inspector Notes
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, Chief
Technical Support Branch
Division of Reactor Projects
Docket Nos.: 50-280; 50-281;72-055
Enclosure:
Surry Power Station - Independent Spent Fuel Storage Installation(ISFSI) Dry Run and Initial
Loading Inspection Report
Attachments: 1. Supplemental Information
2. Inspector Notes
SUNSI Review Completed: SPA ADAMS: O Yes G No Initials: SPA
O Publicly Available G Non-Publicly Available G Sensitive O Non-Sensitive
DOCUMENT NAME:
RIV:DNMS:FCDB RIV:DNMS:FCDB RIV:DNMS:FCDB RIV:DRP
SP Atwater EM Garcia RL Kellar MA Sitek
SPA by email EMG by email RLK2 by email MAS3 by email
09/13/07 09/06/07 09/13/07 08/31/07
BP Tripathi ZL Cruz-Perez MG Karmis SJ Vias
BPT by email ZLC by email MGK by email SJV
09/07/07 09/07/07 09/11/07 09/14/07
OFFICIAL 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 and
Operations Support
Virginia Electric & Power Company
Electronic Mail Distribution
Donald E. Jernigan
Site Vice President
Surry Power Station
Virginia Electric & Power Company
Electronic Mail Distribution
Virginia State Corporation Commission
Division of Energy Regulation
P. O. Box 1197
Richmond, VA 23209
Lillian M. Cuoco, Esq.
Senior Counsel
Dominion Resources Services, Inc.
Electronic Mail Distribution
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
VEPCO --4-
4-
Report to David A. Christian from Steven J. Vias dated September 14, 2007
SUBJECT: SURRY POWER STATION - INSPECTION REPORT NOS. 05000280/2007006;
05000281/2007006; AND 07200055/2007001
Distribution w/encl:
S. P. Lingam, NRR
C. 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
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.: 50-280, 50-281,72-055
Report No: 05000280/2007006; 05000281/2007006; and 07200055/2007001
Licensee: Virginia Electric and Power Company (VEPCO)
Facility: Surry Power Station, Units 1 & 2
Location: 5850 Hog Island Road
Surry, VA 23883
Dates: June 18 through August 3, 2007
Inspectors: Scott Atwater Region IV DNMS Inspector - Team Leader
Emilio Garcia Region IV DNMS Inspector
Mark Sitek Region IV Resident Inspector - San Onofre
Steven Vias Region II DRS Inspector
Michael Karmis SFST Senior Safety Inspector
Bhasker (Bob) Tripathi SFST Technical Review Directorate
Zahira Cruz-Perez SFST Technical Review Directorate
Crane Licensing Ray Kellar, P.E. Region IV DNMS Inspector
Research:
Approved By: Steven Vias, Chief
Technical Support Branch
Division of Reactor Projects
Attachments: Supplemental Information
Inspector Notes
Enclosure
EXECUTIVE SUMMARY
Surry Power Station
NRC Inspection Report 05000280/2007006; 05000281/2007006; and 07200055/2007001
Virginia Electric and Power Company (VEPCO) had selected the NUHOMS-HD Horizontal
Modular 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 evaluation
was 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 to
determine 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 of
spent 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 the
Inspector 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 the
application. 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 the
ASME Code and the crane manufacturers 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).
Enclosure
-3-
- 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 by
Technical 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 response
training 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 the
Technical 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 fuel
assembly 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-HD
canister 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 been
incorporated 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 50
requirements. 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 case
accident during ISFSI operations. The dose was within the limits allowed by 10 CFR 72.106
(Attachment 2, General License, Page19).
Enclosure
-4-
- The licensee had calculated the dose to the public at the site boundary from normal ISFSI
operations. 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 liquefaction
during 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 was
consistent with the Technical Specifications (Attachment 2, General License, Page 21).
- The NUHOMS-HD cask system design parameters were bounded by the Surry Power
Station 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 heavy
loads 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 the
requirements 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 drop
would 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 technical
specification 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 licensees 10 CFR Part 50 Quality Assurance Program had been expanded to include
the 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).
Enclosure
-5-
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 minimum
spent 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 would
not 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 of
Compliance, 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 first
cask, 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 testing
and 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 were
inspected 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).
Enclosure
-6-
Training
- The NUHOMS-HD vendor (AREVA) provided training to the Surry Power Station ISFSI
personnel. 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 training
used 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).
Enclosure
Supplemental Information
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
D. Anderson - Health Physicist
L. 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 Fuels
D. 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
Page 1 of 3 Attachment 1
Contractor Personnel
J. Boshoven - Senior Project Manager, Transnuclear
B. Cheek - Health Physics Technician
W. Rodgers - Project Engineer, Transnuclear
B. Speckline - Supervisor, Fuel Handling - North Anna
INSPECTION PROCEDURES USED
60854.1 Pre-operational Testing of Independent Spent Fuel Storage Installations at
Operating Plants
60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants
60856.1 Review of 10 CFR 72.212(b) Evaluations at Operating Plants
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None.
Discussed
None.
LIST OF ACRONYMS USED
ALARA As Low As Reasonably Achievable
ANSI American National Standards Institute
ASME American Society of Mechanical Engineers
BPRA Burnable Poison Rod Assembly
CoC Certificate of Compliance
dpm Disintegrations Per Minute
EAB Exclusion Area Boundary
EAL Emergency Action Level
EPIP Emergency Plan Implementing Procedure
GWD/MTU Gigawatt Days per Metric Ton Uranium
HSM Horizontal Storage Module
ISFSI Independent Spent Fuel Storage Installation
ISI In-Service Inspection
kW Kilowatt
LLWSF Low Level Waste Storage Facility
Page 2 of 3 Attachment 1
M&TE Measuring and Test Equipment
MBR Material Balance Report
msl Mean Sea Level
NCR Non-Conformance Report
NFAH Non Fuel Assembly Hardware
NRC Nuclear Regulatory Commission
ppm Parts Per Million
psf Pounds Per Square Foot
PT Liquid Penetrant Testing
RCC Rod Control Cluster
ref-cc/sec Reference Cubic Centimeters Per Second
RWP Radiation Work Permit
SAT Systematic Approach to Training
SER Safety Evaluation Report
SSC Structures, Systems, and Components
SSI Soil Structure Interaction
TEDE Total Effective Dose Equivalent
TER Technical Evaluation Report
TPA Thimble Plug Assembly
UFSAR Updated Final Safety Analysis Report
VPI Vibration Suppression Insert
wt. % Weight Percent
Page 3 of 3 Attachment 1