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| issue date = 05/21/2010
| issue date = 05/21/2010
| title = IR 0720006-10-002, on 04/12/2010 Through 04/15/2010, Brunswick Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection
| title = IR 0720006-10-002, on 04/12/2010 Through 04/15/2010, Brunswick Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection
| author name = Franke M E
| author name = Franke M
| author affiliation = NRC/RGN-II/DRS/EB3
| author affiliation = NRC/RGN-II/DRS/EB3
| addressee name = Annacone M J
| addressee name = Annacone M
| addressee affiliation = Carolina Power & Light Co
| addressee affiliation = Carolina Power & Light Co
| docket = 05000324, 05000325, 07200006
| docket = 05000324, 05000325, 07200006
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:May 21, 2010
[[Issue date::May 21, 2010]]


Mr. Michael Vice President Carolina Power and Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461
==SUBJECT:==
 
BRUNSWICK STEAM ELECTRIC PLANT - UNIT 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) CRANE INSPECTION REPORT 07200006/2010002
SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - UNIT 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) CRANE INSPECTION REPORT 07200006/2010002


==Dear Mr. Annacone:==
==Dear Mr. Annacone:==
Line 30: Line 28:
The inspection 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 represents the results of that inspection. Based on results of this inspection; no violations or findings of significance were identified.
The inspection 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 represents the results of that inspection. 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 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 NRC's Agencywide Documents Access Management System (ADAMS). ADAMS is accessible CP&L 2 from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
In accordance with 10 CFR 2.390 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 Management System (ADAMS). ADAMS is accessible
 
CP&L  
 
from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,/RA/
Sincerely,
Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos.: 50-325, 50-324, and 72-006 License Nos.: DPR-71, DPR-62  
/RA/  
 
Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety  
 
Docket Nos.: 50-325, 50-324, and 72-006 License Nos.: DPR-71, DPR-62  


===Enclosure:===
===Enclosure:===
Unit 2 Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection Report 07200006/2010002  
Unit 2 Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection Report 07200006/2010002 w/Attachment: Supplemental Information
 
REGION II==
Docket Nos.:
50-325, 50-324, 72-006
 
License Nos.:
DPR-71, DPR-62


===w/Attachment:===
Report No.:  
Supplemental Information cc w/encl: (See page 3)


_________________________
07200006/2010002
G SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DFFI RII:DRP RII:DRS SIGNATURE RA RA RA RA NAME FLETCHER PRINCE MUSSER FRANKE DATE 5/ /2010 5/ /2010 5/21/2010 5/21/2010 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO CP&L 3 cc w/encl: R. J. Duncan, II Vice President Nuclear Operations Carolina Power & Light Company Electronic Mail Distribution Director Site Operations Brunswick Steam Electric Plant Electronic Mail Distribution Edward L. Wills, Jr. Plant General Manager Brunswick Steam Electric Plant Progress Energy Carolinas, Inc. Electronic Mail Distribution


Christos Kamilaris Director Fleet Support Services Carolina Power & Light Company Electronic Mail Distribution Joseph W. Donahue Vice President Nuclear Oversight Carolina Power and Light Company Electronic Mail Distribution Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy Carolinas, Inc. Electronic Mail Distribution Phyllis N. Mentel Manager, Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc. Electronic Mail Distribution Michael S. Williams Manager, Training Brunswick Steam Electric Plant Progress Energy Carolinas, Inc. Electronic Mail Distribution
Licensee:


(Vacant) Manager License Renewal Progress Energy Electronic Mail Distribution Annette H. Pope Supervisor, Licensing/Regulatory Programs Brunswick Steam Electric Plant Progress Energy Carolinas, Inc. Electronic Mail Distribution Senior Resident Inspector U.S. Nuclear Regulatory Commission Brunswick Steam Electric Plant U.S. NRC 8470 River Road, SE Southport, NC 28461 John H. O'Neill, Jr. Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Washington, DC 20037-1128 Peggy Force Assistant Attorney General State of North Carolina P.O. Box 629 Raleigh, NC 27602 Chairman North Carolina Utilities Commission Electronic Mail Distribution Robert P. Gruber Executive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, NC 27699-4326 Brunswick County Board of Commissioners P.O. Box 249 Bolivia, NC 28422
Carolina Power and Light (CP&L)  


(cc w/encl - See page 4)
Facility:
CP&L 4 (cc w/encl cont'd) James Ross Nuclear Energy Institute Electronic Mail Distribution


Public Service Commission State of South Carolina P.O. Box 11649 Columbia, SC 29211
Brunswick Steam Electric Plant, Unit 2


W. Lee Cox, III Section Chief Radiation Protection Section N.C. Department of Environmental Commerce & Natural Resources Electronic Mail Distribution
Location:


Warren Lee Emergency Management Director New Hanover County Department of Emergency Management 230 Government Center Drive Suite 115 Wilmington, NC 28403
8470 River Road, SE Southport, NC 28461


Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos.: 50-325, 50-324, 72-006
Dates:  


License Nos.: DPR-71, DPR-62 Report No.: 07200006/2010002
April 12, 2010 through April 15, 2010


Licensee: Carolina Power and Light (CP&L)
Inspectors:  
Facility: Brunswick Steam Electric Plant, Unit 2 Location: 8470 River Road, SE Southport, NC 28461


Dates: April 12, 2010 through April 15, 2010 Inspectors: C. Fletcher, Reactor Inspector, RII/DRS/EB3 R. Prince, Fuel Facility Inspector, RII/DFFI  
C. Fletcher, Reactor Inspector, RII/DRS/EB3 R. Prince, Fuel Facility Inspector, RII/DFFI  


Approved by: Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety  
Approved by:
Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety  


Enclosure  
Enclosure  


=EXECUTIVE SUMMARY=
=EXECUTIVE SUMMARY=
Progress Energy selected the Transnuclear NUHOMS-61BT Horizontal Modular dry cask storage system for spent fuel storage at the Brunswick Steam Electric Plant. The Transnuclear NUHOMS-61BT Dry Cask Storage System (DCSS) is licensed by the Nuclear Regulatory  
Progress Energy selected the Transnuclear NUHOMS-61BT Horizontal Modular dry cask storage system for spent fuel storage at the Brunswick Steam Electric Plant. The Transnuclear NUHOMS-61BT Dry Cask Storage System (DCSS) is licensed by the Nuclear Regulatory Commission as Certificate of Compliance (CoC) No. 1004, Amendment 10. The Brunswick Independent Spent Fuel Storage Installation (ISFSI) consists of a series of reinforced concrete horizontal storage modules (HSMs). The NUHOMS DCSS consists of a dry shielded canister (DSC) which holds 61 fuel assemblies. The DSC is placed into a transfer cask (TC) to provide shielding for protection of workers during transfer operations and during the drying, helium backfilling, and welding of the DSC. The DSC is loaded with spent fuel, drained of water, vacuum dried, filled with helium gas, and sealed by welding. The TC (loaded with the DSC) is then moved from the cask preparation area within the Reactor Building and is placed onto a transfer trailer (TT) located in the railroad bay of the Reactor Building. The transfer trailer, with the loaded TC, is transported from the plant to the ISFSI. The DSC is inserted into a shielded HSM for storage. Each HSM holds a single, loaded DSC.


Commission as Certificate of Compliance (CoC) No. 1004, Amendment 10. The Brunswick Independent Spent Fuel Storage Installation (ISFSI) consists of a series of reinforced concrete horizontal storage modules (HSMs). The NUHOMS DCSS consists of a dry shielded canister (DSC) which holds 61 fuel assemblies. The DSC is placed into a transfer cask (TC) to provide shielding for protection of workers during transfer operations and during the drying, helium backfilling, and welding of the DSC. The DSC is loaded with spent fuel, drained of water, vacuum dried, filled with helium gas, and sealed by welding. The TC (loaded with the DSC) is then moved from the cask preparation area within the Reactor Building and is placed onto a transfer trailer (TT) located in the railroad bay of the Reactor Building. The transfer trailer, with the loaded TC, is transported from the plant to the ISFSI. The DSC is inserted into a shielded HSM for storage. Each HSM holds a single, loaded DSC.
The licensee has developed a cask loading plan in accordance with approved procedures.


The licensee has developed a cask loading plan in accordance with approved procedures. Procedures governing the lifting of heavy loads contained the appropriate requirements specified in national standards. Controls governing the lifting, handling, and movement of heavy loads are adequately addressed in approved procedures. Maintenance and testing activities to ensure the ability of the Reactor Building crane to safely handle anticipated loads were properly performed and documented in accordance with approved procedures.
Procedures governing the lifting of heavy loads contained the appropriate requirements specified in national standards. Controls governing the lifting, handling, and movement of heavy loads are adequately addressed in approved procedures. Maintenance and testing activities to ensure the ability of the Reactor Building crane to safely handle anticipated loads were properly performed and documented in accordance with approved procedures.


No findings of significance were identified.
No findings of significance were identified.


=REPORT DETAILS=
=REPORT DETAILS=
Report Details
Report Details


===.1 Inspection of Unit 2 Reactor Building Crane===
===.1 Inspection of Unit 2 Reactor Building Crane===
====a. Inspection Scope====
(Inspection Procedure (IP) 60854)


====a. Inspection Scope====
(Inspection Procedure (IP) 60854)
The objective of this inspection was to determine if the licensee had developed, implemented, and evaluated preoperational testing activities with regard to the Unit 2 Reactor Building bridge crane, to safely load spent fuel from the spent fuel pool (SFP) into a dry cask storage system, and to transfer the loaded dry cask storage system to the ISFSI.
The objective of this inspection was to determine if the licensee had developed, implemented, and evaluated preoperational testing activities with regard to the Unit 2 Reactor Building bridge crane, to safely load spent fuel from the spent fuel pool (SFP) into a dry cask storage system, and to transfer the loaded dry cask storage system to the ISFSI.


Specifically, the inspectors reviewed the licensee's recent modifications to the Unit 2 Reactor Building bridge crane, which will be utilized for handling the Transnuclear Transfer Cask (TC), and the licensee's programs associated with the handling of heavy loads, maintenance, inspection, and periodic testing of the crane. The inspection consisted of field observations, interviews with cognizant personnel, and a review of documentation associated with the Heavy Loads Program.
Specifically, the inspectors reviewed the licensees recent modifications to the Unit 2 Reactor Building bridge crane, which will be utilized for handling the Transnuclear Transfer Cask (TC), and the licensees programs associated with the handling of heavy loads, maintenance, inspection, and periodic testing of the crane. The inspection consisted of field observations, interviews with cognizant personnel, and a review of documentation associated with the Heavy Loads Program.


====b. Observations and Findings====
====b. Observations and Findings====
The Brunswick Unit 2 Reactor Building crane is a single-trolley Seismic Category 1 overhead crane with a 125-ton capacity main hoist. The crane was previously reviewed by the NRC and found to meet the single-failure proof criteria specified in NUREG-0612 and NUREG-0554. The licensee implemented Engineering Change 71206, Reactor Building (RB) Crane Wire Rope Upgrade, in 2009. The design modification replaced the existing wire rope with a rope of sufficient load capacity to handle the fully-loaded 110-ton transfer cask to be utilized for dry cask storage activities.
The Brunswick Unit 2 Reactor Building crane is a single-trolley Seismic Category 1 overhead crane with a 125-ton capacity main hoist. The crane was previously reviewed by the NRC and found to meet the single-failure proof criteria specified in NUREG-0612 and NUREG-0554. The licensee implemented Engineering Change 71206, Reactor Building (RB) Crane Wire Rope Upgrade, in 2009. The design modification replaced the existing wire rope with a rope of sufficient load capacity to handle the fully-loaded 110-ton transfer cask to be utilized for dry cask storage activities.


To ensure that the crane cannot travel over areas of the SFP where spent fuel is stored, the licensee has designated safe load paths on the 117' elevation of the Reactor Building. These restrictions are specified in Procedure OMMM15, Operation and Inspection of Cranes and Material Handling Equipment.
To ensure that the crane cannot travel over areas of the SFP where spent fuel is stored, the licensee has designated safe load paths on the 117 elevation of the Reactor Building. These restrictions are specified in Procedure OMMM15, Operation and Inspection of Cranes and Material Handling Equipment.


Procedure OMST-CR51R, Operating and Visual Inspection of Reactor Building Crane, provides instructions for verifying the operability of the crane interlocks, which prevent travel over stored spent fuel assemblies.
Procedure OMST-CR51R, Operating and Visual Inspection of Reactor Building Crane, provides instructions for verifying the operability of the crane interlocks, which prevent travel over stored spent fuel assemblies.


The crane will be used to move the TC containing the DSC from the cask loading area located in the southeast corner of the SFP to the cask preparation area, located on the 117' elevation of the RB, and back again. The crane is also used to lift the TC from the transport trailer from the 20' elevation to the 117' elevation refuel floor.
The crane will be used to move the TC containing the DSC from the cask loading area located in the southeast corner of the SFP to the cask preparation area, located on the 117 elevation of the RB, and back again. The crane is also used to lift the TC from the transport trailer from the 20 elevation to the 117 elevation refuel floor.


The inspectors reviewed the preventative maintenance and inspection programs for the Unit 2 RB crane. The inspectors found that procedures adequately addressed test requirements, frequent and periodic inspections, pre-operational checks, and inspections prior to use. The inspectors reviewed recently performed quarterly and annual inspection work packages for completeness and accuracy.
The inspectors reviewed the preventative maintenance and inspection programs for the Unit 2 RB crane. The inspectors found that procedures adequately addressed test requirements, frequent and periodic inspections, pre-operational checks, and inspections prior to use. The inspectors reviewed recently performed quarterly and annual inspection work packages for completeness and accuracy.
Line 107: Line 118:
The inspectors toured the ISFSI facility to observe ongoing construction activities. The ISFSI presently contains 20 horizontal storage modules (HSM).
The inspectors toured the ISFSI facility to observe ongoing construction activities. The ISFSI presently contains 20 horizontal storage modules (HSM).


Ongoing construction activities include final grading of the ISFSI apron and activities to prepare the ISFSI pad and the heavy haul path for incorporation into the existing plant Protected Area. The inspectors reviewed receipt inspection documents for the HSM components and the work package for installation of HSMs on the ISFSI pad. Material discrepancies noted during receipt inspections were properly dispositioned and issues were entered into the licensee's corrective action program as necessary.
Ongoing construction activities include final grading of the ISFSI apron and activities to prepare the ISFSI pad and the heavy haul path for incorporation into the existing plant Protected Area. The inspectors reviewed receipt inspection documents for the HSM components and the work package for installation of HSMs on the ISFSI pad. Material discrepancies noted during receipt inspections were properly dispositioned and issues were entered into the licensees corrective action program as necessary.


At the time of the inspection, the licensee had not decided if Progress Energy personnel would perform the entire ISFSI operation or if certain aspects of the ISFSI operation would be contracted to a vendor. Therefore, a review of qualifications and training of personnel involved in ISFSI operations was not performed.
At the time of the inspection, the licensee had not decided if Progress Energy personnel would perform the entire ISFSI operation or if certain aspects of the ISFSI operation would be contracted to a vendor. Therefore, a review of qualifications and training of personnel involved in ISFSI operations was not performed.
Line 113: Line 124:
No findings of significance were identified.
No findings of significance were identified.


===.2 Exit Meeting Summary===
===.2===
 
===Exit Meeting Summary===
The inspectors presented the inspection results to M. Annacone and other Brunswick personnel at the conclusion of the inspection on April 15, 2010. The licensee acknowledged the results presented.
The inspectors presented the inspection results to M. Annacone and other Brunswick personnel at the conclusion of the inspection on April 15, 2010. The licensee acknowledged the results presented.


ATTACHMENT:
ATTACHMENT:  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
===Licensee Personnel===
===Licensee Personnel===
: [[contact::M. Annacone]], Site Vice President
: [[contact::M. Annacone]], Site Vice President  
: [[contact::E. Willis]], Plant General Manager  
: [[contact::E. Willis]], Plant General Manager  
: [[contact::S. Gordy]], Operations Manager  
: [[contact::S. Gordy]], Operations Manager  
: [[contact::W. Brewer]], Maintenance Manager  
: [[contact::W. Brewer]], Maintenance Manager  
: [[contact::B. Davis]], Engineering Manager  
: [[contact::B. Davis]], Engineering Manager  
: [[contact::P. Mentel]], Environmental & Radiological Controls Manager
: [[contact::P. Mentel]], Environmental & Radiological Controls Manager  
: [[contact::K. Ward]], Major Projects  
: [[contact::K. Ward]], Major Projects  
: [[contact::C. Rajendra]], Major Projects  
: [[contact::C. Rajendra]], Major Projects  
Line 135: Line 145:
: [[contact::R. Tripp]], Major Projects  
: [[contact::R. Tripp]], Major Projects  
: [[contact::W. Worthington]], NFM & SA  
: [[contact::W. Worthington]], NFM & SA  
: [[contact::B. Murray]], Licensing
: [[contact::B. Murray]], Licensing  
: [[contact::T. Sherrill]], Licensing  
: [[contact::T. Sherrill]], Licensing  
: [[contact::B. Howath]], Whiting Corporation  
: [[contact::B. Howath]], Whiting Corporation  


===NRC Personnel===
===NRC Personnel===
: [[contact::P. O'Bryan]], NRC Senior Resident Inspector  
: [[contact::P. OBryan]], NRC Senior Resident Inspector  


==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
None


None 
==LIST OF DOCUMENTS REVIEWED==


==LIST OF DOCUMENTS REVIEWED==
1. Procedure
: OMMM-015, Operation and Inspection of Cranes and Material Handling Equipment
: 2. Procedure
: OPM-CRN501, Preventative Maintenance for the Fixed Gantry and Track Cranes 3. Procedure
: OPM-CRN002, Overhead Crane Checklist 4. Procedure
: OMST-CR51R, Operating and Visual Inspection of Reactor Building Crane 5. Procedure
: OSMP-M002, Meggering and Bridging of Electric Motors 6. Procedure
: IFS-NGGC-0011, Horizontal Storage Module Assembly, Rev 1 7. Transnuclear Certificate of Conformance for
: HSM-H Array
: 8. Franklin Research Center, Technical Evaluation Report, Control of Heavy Loads, CP&L Company Brunswick Units 1 and 2, April 23, 1984, NRC Contract Number NRC-03-81-
: 130 9. Work Order
: 01379387 02, 2-BC-RB-Bridge-Crane Upgrade, 10/06/08
: Attachment
: 10. Work Order
: 01457346 01, Perform Inspection of Unit 2 Reactor Building Crane, 09/8/09, 2-BC-RB-Bridge Crane 11. Work Order
: 01493628 02, 2-BC-RB-Bridge Crane Wire Rope Change-Out 12. Work Order
: 01493628 04, 2-BC-RB-Bridge Crane Wire Rope Change-Out and Crane Operability Check (Rope Break-In) 13. Work Order
: 01524720 01, Quarterly Unit 2 Crane Lube and Inspect, 11/30/09, and Before Use or Daily Crane Inspection, 2-BC-RB-Bridge Crane, 02/2/10 14. Work Order
: 01589025 02, Install
: HSM 15. Work Order
: 01596780 05, Test Tornado Latch Controls, Unit 2
: 16. FSAR, Rev 21A, Section 9.1.4, Control of Heavy Loads 17.
: EGR-NGGC-0006, Whiting Corporation Operation and Maintenance Manual dated 1/73 for 125/5 Ton reactor Building Cranes (FP-1445) 18. Engineering Change 67587R2, Spent Fuel Dry Storage Unit 2 Reactor Building Bridge Crane Upgrade 19. Engineering Change 71206R1, Reactor Building Crane Wire Rope Upgrade 20. Engineering Change 71207R7, Reactor Building Crane Tornado Latch Control Modification (Units 1 & 2) 21. Engineering Change 71907R0, Evaluate OBE, Design, and Licensing Basis Requirements for Reactor Building Cranes Unit 1 & 2 22. Whiting Corporation, Project No: C10388.41, 02/17/10, Crane Natural Frequencies, Vertical Seismic Loads (Gz), and Horizontal Seismic Loads (Gy) with the Crane in Parked Position (Parking Locks Engaged) (Including Pendulum Swing) 23. Whiting Corporation Calculation, C10388.42, C10388.43, C10388.45, Design Report (Static) 24. Nuclear Generation Group, Calculation 05E15-0036, Reactor Building Crane Static, Seismic, Tornado Loading Qualification, 02/12/10 25. A/R
: 00282917, Unit 1 & 2 Reactor Building Crane Seismic Qualification 26. Licensee Event Report
: 1-2008-003, Brunswick Steam Electric Plant, Unit No's 1 & 2, Aug 11, 2008
}}
}}

Latest revision as of 04:48, 14 January 2025

IR 0720006-10-002, on 04/12/2010 Through 04/15/2010, Brunswick Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection
ML101450293
Person / Time
Site: Brunswick, 07200006  Duke Energy icon.png
Issue date: 05/21/2010
From: Mark Franke
NRC/RGN-II/DRS/EB3
To: Annacone M
Carolina Power & Light Co
References
IR-10-002
Download: ML101450293 (11)
v • d • e


Text

May 21, 2010

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT - UNIT 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) CRANE INSPECTION REPORT 07200006/2010002

Dear Mr. Annacone:

On April 15, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed a portion of the Independent Spent Fuel Storage Installation (ISFSI) Dry Run inspection at your Brunswick Unit 2 facility. The enclosed inspection report documents the inspection findings between April 12-15, 2010, for the Unit 2 Reactor Building crane and Heavy Loads Program, which was performed in accordance with Inspection Procedure 60854, Pre-operational Testing of an Independent Spent Fuel Storage Installation.

The inspection 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 represents the results of that inspection. Based on results of this inspection; no violations or findings of significance were identified.

In accordance with 10 CFR 2.390 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 Management System (ADAMS). ADAMS is accessible

CP&L

from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety

Docket Nos.: 50-325, 50-324, and 72-006 License Nos.: DPR-71, DPR-62

Enclosure:

Unit 2 Independent Spent Fuel Storage Installation (ISFSI) Crane Inspection Report 07200006/2010002 w/Attachment: Supplemental Information

REGION II==

Docket Nos.:

50-325, 50-324,72-006

License Nos.:

DPR-71, DPR-62

Report No.:

07200006/2010002

Licensee:

Carolina Power and Light (CP&L)

Facility:

Brunswick Steam Electric Plant, Unit 2

Location:

8470 River Road, SE Southport, NC 28461

Dates:

April 12, 2010 through April 15, 2010

Inspectors:

C. Fletcher, Reactor Inspector, RII/DRS/EB3 R. Prince, Fuel Facility Inspector, RII/DFFI

Approved by:

Mark E. Franke, Chief Engineering Branch 3 Division of Reactor Safety

Enclosure

EXECUTIVE SUMMARY

Progress Energy selected the Transnuclear NUHOMS-61BT Horizontal Modular dry cask storage system for spent fuel storage at the Brunswick Steam Electric Plant. The Transnuclear NUHOMS-61BT Dry Cask Storage System (DCSS) is licensed by the Nuclear Regulatory Commission as Certificate of Compliance (CoC) No. 1004, Amendment 10. The Brunswick Independent Spent Fuel Storage Installation (ISFSI) consists of a series of reinforced concrete horizontal storage modules (HSMs). The NUHOMS DCSS consists of a dry shielded canister (DSC) which holds 61 fuel assemblies. The DSC is placed into a transfer cask (TC) to provide shielding for protection of workers during transfer operations and during the drying, helium backfilling, and welding of the DSC. The DSC is loaded with spent fuel, drained of water, vacuum dried, filled with helium gas, and sealed by welding. The TC (loaded with the DSC) is then moved from the cask preparation area within the Reactor Building and is placed onto a transfer trailer (TT) located in the railroad bay of the Reactor Building. The transfer trailer, with the loaded TC, is transported from the plant to the ISFSI. The DSC is inserted into a shielded HSM for storage. Each HSM holds a single, loaded DSC.

The licensee has developed a cask loading plan in accordance with approved procedures.

Procedures governing the lifting of heavy loads contained the appropriate requirements specified in national standards. Controls governing the lifting, handling, and movement of heavy loads are adequately addressed in approved procedures. Maintenance and testing activities to ensure the ability of the Reactor Building crane to safely handle anticipated loads were properly performed and documented in accordance with approved procedures.

No findings of significance were identified.

REPORT DETAILS

Report Details

.1 Inspection of Unit 2 Reactor Building Crane

a. Inspection Scope

(Inspection Procedure (IP) 60854)

The objective of this inspection was to determine if the licensee had developed, implemented, and evaluated preoperational testing activities with regard to the Unit 2 Reactor Building bridge crane, to safely load spent fuel from the spent fuel pool (SFP) into a dry cask storage system, and to transfer the loaded dry cask storage system to the ISFSI.

Specifically, the inspectors reviewed the licensees recent modifications to the Unit 2 Reactor Building bridge crane, which will be utilized for handling the Transnuclear Transfer Cask (TC), and the licensees programs associated with the handling of heavy loads, maintenance, inspection, and periodic testing of the crane. The inspection consisted of field observations, interviews with cognizant personnel, and a review of documentation associated with the Heavy Loads Program.

b. Observations and Findings

The Brunswick Unit 2 Reactor Building crane is a single-trolley Seismic Category 1 overhead crane with a 125-ton capacity main hoist. The crane was previously reviewed by the NRC and found to meet the single-failure proof criteria specified in NUREG-0612 and NUREG-0554. The licensee implemented Engineering Change 71206, Reactor Building (RB) Crane Wire Rope Upgrade, in 2009. The design modification replaced the existing wire rope with a rope of sufficient load capacity to handle the fully-loaded 110-ton transfer cask to be utilized for dry cask storage activities.

To ensure that the crane cannot travel over areas of the SFP where spent fuel is stored, the licensee has designated safe load paths on the 117 elevation of the Reactor Building. These restrictions are specified in Procedure OMMM15, Operation and Inspection of Cranes and Material Handling Equipment.

Procedure OMST-CR51R, Operating and Visual Inspection of Reactor Building Crane, provides instructions for verifying the operability of the crane interlocks, which prevent travel over stored spent fuel assemblies.

The crane will be used to move the TC containing the DSC from the cask loading area located in the southeast corner of the SFP to the cask preparation area, located on the 117 elevation of the RB, and back again. The crane is also used to lift the TC from the transport trailer from the 20 elevation to the 117 elevation refuel floor.

The inspectors reviewed the preventative maintenance and inspection programs for the Unit 2 RB crane. The inspectors found that procedures adequately addressed test requirements, frequent and periodic inspections, pre-operational checks, and inspections prior to use. The inspectors reviewed recently performed quarterly and annual inspection work packages for completeness and accuracy.

The inspectors were accompanied by licensee personnel as they performed an inspection of the Unit 2 RB crane. The inspectors observed the overall material condition of the crane components. The new rope on the main hoist was inspected for the presence of defects or indications of damage. At the request of the NRC inspectors, licensee personnel described the procedure to manually lower a load in the event of a loss-of-power incident. Personnel were knowledgeable of the procedural steps and the location of the components required to be accessed in the event that manual operation had to be performed.

The inspectors reviewed the work packages and design analysis associated with the seismic and tornado qualification modifications installed on the Unit 2 RB crane. The review also included a walkdown of the newly installed tornado latches on the bridge and trolley of the Unit 2 RB crane.

The inspectors toured the ISFSI facility to observe ongoing construction activities. The ISFSI presently contains 20 horizontal storage modules (HSM).

Ongoing construction activities include final grading of the ISFSI apron and activities to prepare the ISFSI pad and the heavy haul path for incorporation into the existing plant Protected Area. The inspectors reviewed receipt inspection documents for the HSM components and the work package for installation of HSMs on the ISFSI pad. Material discrepancies noted during receipt inspections were properly dispositioned and issues were entered into the licensees corrective action program as necessary.

At the time of the inspection, the licensee had not decided if Progress Energy personnel would perform the entire ISFSI operation or if certain aspects of the ISFSI operation would be contracted to a vendor. Therefore, a review of qualifications and training of personnel involved in ISFSI operations was not performed.

No findings of significance were identified.

.2

Exit Meeting Summary

The inspectors presented the inspection results to M. Annacone and other Brunswick personnel at the conclusion of the inspection on April 15, 2010. The licensee acknowledged the results presented.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

M. Annacone, Site Vice President
E. Willis, Plant General Manager
S. Gordy, Operations Manager
W. Brewer, Maintenance Manager
B. Davis, Engineering Manager
P. Mentel, Environmental & Radiological Controls Manager
K. Ward, Major Projects
C. Rajendra, Major Projects
B. Bellamy, Major Projects
R. Tripp, Major Projects
W. Worthington, NFM & SA
B. Murray, Licensing
T. Sherrill, Licensing
B. Howath, Whiting Corporation

NRC Personnel

P. OBryan, NRC Senior Resident Inspector

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

None

LIST OF DOCUMENTS REVIEWED

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