IR 05000395/2014009
| ML14325A539 | |
| Person / Time | |
|---|---|
| Site: | Summer, 07201038  (NPF-012) |
| Issue date: | 11/21/2014 |
| From: | Mark Kowal NRC/RGN-II/DRS/EB3 |
| To: | Gatlin T South Carolina Electric & Gas Co |
| Linda K. Gruhler 404-997-4633 | |
| References | |
| IR 14002, IR 14009 | |
| Download: ML14325A539 (11) | |
Text
November 21, 2014
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT OF FUEL HANDLING CRANE FOR USE DURING INDEPENDENT SPENT FUEL STORAGE INSTALLATION ACTIVITIES - 05000395/2014009 AND 07201038/2014002
Dear Mr. Gatlin:
On October 24, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Virgil C. Summer Nuclear Station, Unit 1, of the fuel handling crane which will be used during Independent Spent Fuel Storage Installation (ISFSI) activities. On that day, the NRC inspector discussed the results of this inspection with Mr. Larry Bennett and members of your staff. The inspection was conducted in accordance with Inspection Procedure (IP) 60854, Preoperational Testing of Independent Spent Fuel Storage Installations at Operating Plants, and covered aspects associated with the preparation of the crane to move spent fuel into the ISFSI facility, and consisted of field observations, extensive examination of procedures and documents, and interviews with personnel. The enclosed report presents the results of the inspection.
No NRC-identified or self-revealing findings were identified during the inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public inspections, exemptions, requests for withholding, of the NRCs Rules of Practice, a copy of this letter, its Enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS) component of NRCs Agencywide Documents Access and Management System (ADAMS);
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Mark G. Kowal, Acting Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-395 and 72-1038 License No. NPF-12
Enclosure:
IR 05000395/2014009 and 07201038/2014002 w/Attachment: Supplementary Information
REGION II==
Docket Nos:
50-395 and 72-1038
License No:
Report Nos:
05000395/2014009 and 07201038/2014002
Licensee:
South Carolina Electric & Gas (SCE&G) Company
Facility:
Virgil C. Summer Nuclear Station, Unit 1
Location:
P.O. Box 88
Jenkinsville, SC 29065
Dates:
October 20 - 24, 2014
Inspector:
Robert Carrion, Senior Reactor Inspector (Section 4OA5)
Approved by:
Mark Kowal, Acting Chief
Engineering Branch 3
Division of Reactor Safety
SUMMARY
Inspection Report (IR) 05000395/2014009; 07201038/2014002; 10/20/2014 - 10/24/2014:
Virgil C. Summer Nuclear Station, Unit 1; Fuel Handling Crane Inspection Report
This report covers a 1-week period of inspection by a senior reactor inspector from the Region II office. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
NRC-Identified and Self-Revealing Findings
No findings were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
Summary of Plant Status
Unit 1 operated at Rated Thermal Power during the period of this inspection.
Management of the Virgil C. Summer Nuclear Station, Unit 1, selected the HI-STORM (Holtec International STORage Module) FW (Flood and Wind) dry cask storage system for spent fuel storage at the onsite Independent Spent Fuel Storage Installation (ISFSI). The system is licensed by the U.S. Nuclear Regulatory Commission as Certificate of Compliance (CoC)
No. 1032, Amendment 0.
The Virgil C. Summer ISFSI consists of a 36-inch thick concrete pad on which several vertical concrete casks (the HI-STORM FWs) are placed. The HI-STORM FW casks serve as an overpack for the multi-purpose canisters (MPCs), which contain the spent fuel. Each MPC can store up to 37 pressurized water reactor fuel assemblies. During transfer operations and during the drying, helium backfilling, and welding of the MPC; the MPC is placed into a transfer cask (designated as the HI-TRAC VW) to provide shielding for protection of personnel. The MPC is loaded with spent fuel, drained of water, vacuum dried, filled with helium gas, and sealed by welding while in the HI-TRAC VW. Upon completion of the welding, the HI-TRAC VW (loaded with the MPC) is then moved from the cask handling facility (CHF) and placed on top of the HI-STORM FW in the stackup configuration, and the MPC is transferred from the HI-TRAC VW into the HI-STORM FW. The loaded HI-STORM FW is subsequently conveyed to the ISFSI pad via the Vertical Cask Transporter (VCT).
Procedures governing the lifting of heavy loads incorporated requirements specified in NRC regulations and industry standards. Controls governing the lifting, handling, and movement of heavy loads were addressed in approved procedures. Maintenance and testing activities for the Fuel Handling Crane, to ensure the ability of the equipment to safely handle anticipated loads, were performed and documented in accordance with approved procedures. Crane operators were qualified per industry standards and the associated documentation was available for verification.
OTHER ACTIVITIES
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, Emergency Preparedness, Public Radiation Safety, and Occupational Radiation Safety
4OA5 Other Activities
Preoperational Testing of an Independent Spent Fuel Storage Installation (60854)
a. Inspection Scope
The NRC inspector reviewed the licensees implementation of the control of heavy loads program for independent spent fuel storage installation (ISFSI) operations, including procedures and inspection, testing, and maintenance documentation associated with the crane, wire rope, slings, etc. The inspector also reviewed the responsibilities for employees, including operators and riggers, who participate in the lifting process, including personnel training and planning of lifts.
The inspector verified that the licensee had modified its fuel handling crane by installing a new trolley to upgrade the crane to single-failure proof, and that the modified fuel handling crane was certified and documented by the manufacturer to conform to the requirements of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, and NUREG-0554, Single-Failure-Proof Cranes for Nuclear Power Plants. The inspector reviewed the results of the licensees functional tests to verify compliance with the NUREG requirements, and noted that the crane retained its original 125-ton capacity.
The inspector also reviewed the results of the Factory Acceptance Test (FAT) and selected crane design features for compliance to the NUREG requirements, and determined that, for those features reviewed, the crane met the single-failure proof criteria established by the NRC. The inspector noted that the crane, slings, and wire rope had been load tested, and operated in accordance with the applicable American Society of Mechanical Engineers (ASME) Code, ASME B30.2-2005 Overhead and Gantry Cranes, ASME B30.9-2006, Slings, NUREG-0554, and NUREG-0612.
The inspector reviewed work orders associated with the loading and functional testing of special lifting devices used for ISFSI activities, and determined that the crane, hooks, and wire rope were inspected, tested, and maintained in accordance with the ASME Code, NUREG-0554, NUREG-0612, and the crane manufacturers recommendations.
The inspector walked down the fuel handling building to directly observe the material condition of the crane and its components (bridge, trolley, rails, limit switches, rail stops, etc.), and interviewed the ISFSI Program Manager to discuss the planned sequence to be employed during the MPC loading and transfer activities, in and around, the fuel handling building.
The inspector also interviewed the Crane Maintenance Supervisor to verify that the crane inspection, maintenance, and testing programs were in accordance with ASME and NUREG requirements, and that crane operators meet the qualifications required by the ASME Code and have been trained to carry out the ISFSI operations. The inspector reviewed records of crane inspections, maintenance, and testing, as well as records of crane operator qualifications for compliance to Code standards.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On October 24, 2014, the inspector presented the inspection report results to Mr. Larry Bennett and other members of the licensee staff. The licensee acknowledged the results of these inspections. The inspector confirmed that inspection activities discussed in this report did not contain proprietary material, and all proprietary material was returned to the licensee.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- J. Andrescavage, ISFSI Program Manager
- R. Antonow, CBI/ISFSI Project Manager
- L. Bennett, Manager, Project Management Organization
- T. Johnson, Manager, Outage Management
- R. Russell, SCE&G Design Engineering
- T. Stewart, Nuclear Licensing Engineer
- R. Sturkie, Maintenance Supervisor
- B. Thompson, Manager, Nuclear Licensing
- S. Zarandi, General Manager, Nuclear Support Services
NRC
- J. Reece, V. C. Summer Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, DISCUSSED AND UPDATED
Opened
None
Closed
None
Discussed
None