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, 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

License Nos.: DPR-32, DPR-37

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

License Nos.: DPR-32, DPR-37

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

SFST SFST SFST C:TSB/DRP

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

License: DPR-32, DPR-37

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

DBE Design Basis Earthquake

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

JPM Job Performance Measure

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

SNM Special Nuclear material

SSC Structures, Systems, and Components

SSE Safe Shutdown Earthquake

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