ML051800048

License Amendment, Amendment Revises the TSs Related to Fuel Handling and Storage

ML051800048
Person / Time
Site:	Davis Besse
Issue date:	08/16/2005
From:	Macon W NRC/NRR/DLPM/LPD3
To:	Bezilla M FirstEnergy Nuclear Operating Co
Macon W, NRR/DLPM,415-3965
Shared Package
ML051800079	List: ML051800048 ML052290254
References
TAC MC6812
Download: ML051800048 (15)

Text

August 16, 2005 Mr. Mark B. Bezilla Vice President-Nuclear, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: FUEL HANDLING AND STORAGE (TAC NO. MC6812)

Dear Mr. Bezilla:

The Commission has issued the enclosed Amendment No. to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit 1. The amendment revises the Technical Specifications (TSs) in response to your application dated April 22, 2005.

This amendment revises the TSs related to fuel handling and storage. Specifically, the changes reflect that spent fuel storage racks are no longer installed in the cask pit or transfer pit and that there are no longer any low density fuel storage racks in the spent fuel pool.

Additionally, the changes relocate the requirements of TS 3/4.9.7, "Crane Travel - Fuel Handling Building," to the Technical Requirements Manual.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosures:

1. Amendment No. 266 to NPF-3

2. Safety Evaluation cc w/encls: See next page

August 16, 2005 Mr. Mark B. Bezilla Vice President-Nuclear, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: FUEL HANDLING AND STORAGE (TAC NO. MC6812)

Dear Mr. Bezilla:

The Commission has issued the enclosed Amendment No. to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit 1. The amendment revises the Technical Specifications (TSs) in response to your application dated April 22, 2005.

This amendment revises the TSs related to fuel handling and storage. Specifically, the changes reflect that spent fuel storage racks are no longer installed in the cask pit or transfer pit and that there are no longer any low density fuel storage racks in the spent fuel pool.

Additionally, the changes relocate the requirements of TS 3/4.9.7, "Crane Travel - Fuel Handling Building," to the Technical Requirements Manual.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosures:

1. Amendment No. 266 to NPF-3

2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC PDIII/2 R/F WMacon TBoyce, O-12H2 OGC GGrant, RIII ACRS GHill (2)

DClarke GSuh DLPMDPR HNieh (A) PD Package Accession Number: ML051800079 Amendment Accession Number: ML051800048 TS Accession Number: ML052290254 OFFICE PM:PD3-2 LA:PD3-2 SC:IROB-A OGC SC:PD3-2 NAME WMacon DClarke TBoyce SUttal GSuh DATE 8/1/05 7/29/05 8/2/05 8/11/05 8/12/05 OFFICIAL RECORD COPY

Davis-Besse Nuclear Power Station, Unit 1 cc:

Mary E. O'Reilly FirstEnergy Corporation 76 South Main St.

Akron, OH 44308 Manager - Regulatory Affairs FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State - Route 2 Oak Harbor, OH 43449-9760 Director, Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009 Regional Administrator U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60523-4351 Michael A. Schoppman Framatome ANP 24 Calabash Court Rockville, MD 20850 Resident Inspector U.S. Nuclear Regulatory Commission 5503 North State Route 2 Oak Harbor, OH 43449-9760 Barry Allen, Plant Manager FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State - Route 2 Oak Harbor, OH 43449-9760 Dennis Clum Radiological Assistance Section Supervisor Bureau of Radiation Protection Ohio Department of Health P.O. Box 118 Columbus, OH 43266-0118 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-2206 Zack A. Clayton DERR Ohio Environmental Protection Agency P.O. Box 1049 Columbus, OH 43266-0149 State of Ohio Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573 Attorney General Office of Attorney General 30 East Broad Street Columbus, OH 43216 President, Board of County Commissioners of Ottawa County Port Clinton, OH 43252 President, Board of County Commissioners of Lucas County One Government Center, Suite 800 Toledo, OH 43604-6506 The Honorable Dennis J. Kucinich United States House of Representatives Washington, D.C. 20515 The Honorable Dennis J. Kucinich United States House of Representatives 14400 Detroit Avenue Lakewood, OH 44107 Mr. Joseph J. Hagan Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760

FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 266 License No. NPF-3 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee) dated April 22, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 266, are hereby incorporated in the license.

FirstEnergy Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 16, 2005

ATTACHMENT TO LICENSE AMENDMENT NO. 266 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert VIII VIII 3/4 9-7 3/4 9-7 3/4 9-11 3/4 9-11 3/4 9-12 3/4 9-12 3/4 9-13 3/4 9-13 3/4 9-14 3/4 9-15 3/4 9-16 3/4 9-14 5-1 5-1 5-2 5-2 5-3 5-3

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 266 TO FACILITY OPERATING LICENSE NO. NPF-3 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-346

1.0 INTRODUCTION

By application to the U.S. Nuclear Regulatory Commission (NRC, Commission) dated April 22, 2005 (Reference 1), FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested changes to the Technical Specifications (TSs) for the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS).

The proposed changes would revise the TSs related to fuel handling and storage. Specifically, the proposed changes would revise TS 3/4.9.11, "Storage Pool Water Level," TS 3/4.9.12, "Storage Pool Ventilation," TS 3/4.9.13, "Spent Fuel Assembly Storage," and TS 5.6, "Fuel Storage," to reflect that spent fuel storage racks are no longer installed in the cask pit or transfer pit. Fuel storage racks were permitted to be temporarily installed in the cask pit and transfer pit during a project to increase spent fuel pool (SFP) storage capacity. All temporarily installed fuel storage racks have now been moved into the SFP. Additionally, the proposed changes would relocate the requirements of TS 3/4.9.7, "Crane Travel - Fuel Handling Building," to the DBNPS Technical Requirements Manual (TRM). The proposed changes to TS 3/4.9.13 and TS 5.6 would also reflect that there are no longer low density fuel storage racks in the SFP. The proposed changes would make TS requirements consistent with the current fuel storage design.

DBNPS has pursued a SFP rerack project to increase the SFP capacity from 735 fuel assemblies to a new capacity of 1,624 fuel assemblies. As part of this project, spent fuel racks were allowed to be temporarily installed in the cask pit and transfer pit. License Amendment No. 237 was issued on February 29, 2000 (Reference 2), providing approval for use of up to 289 cask pit rack storage locations. License Amendment No. 247 was issued October 19, 2001 (Reference 3), providing approval for the increase in SFP storage capacity and for use of up to 90 transfer pit rack storage locations. Currently, there are no storage racks in the cask pit or transfer pit. All of the storage racks are currently located in the SFP.

The proposed changes are desired by the licensee to support removal of restrictions on movement of crane loads over the transfer and cask pits. These restrictions are no longer required since there are no fuel racks in the transfer and cask pits. The proposed changes also simplify the TSs by removing allowances and requirements that are no longer needed. These changes are desired to enhance operations during the 14th refueling outage, which is currently scheduled to commence in March 2006.

Associated changes to the TS Bases are also being made in support of this application. These Bases changes are being processed under the DBNPS TS Bases Control Program and were provided by the licensee for information only.

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR), Part 50.36, "Technical specifications,"

contains requirements for the content of operating license TSs. 10 CFR 50.36(c)(2)(ii) specifies the following criteria for determining which items require a TS limiting condition for operation (LCO):

Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

Criterion 2. A process variable, design feature,, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The requirements of TS 3/4.9.7, which are proposed for relocation to the DBNPS TRM, were evaluated by the NRC staff against the criteria of 10 CFR 50.36(c)(2)(ii) for deletion from TSs.

This evaluation is documented below. The relocation of TS 3/4.9.7 requirements to the TRM is also consistent with NUREG-1430, "Standard Technical Specifications - Babcock and Wilcox Plants," Revision 3, dated June 2004. Therefore, relocation of the requirements of TS 3/4.9.7 does not affect the conformance of the DBNPS Operating License TSs to the requirements of 10 CFR 50.36.

Design requirements for the fuel handling and storage systems are specified in the DBNPS Updated Safety Analysis Report (USAR) Section 3D.1.52, "Criterion 61 - Fuel Storage and Handling and Radioactivity Control," and Section 3D.1.53, "Criterion 62 - Prevention of Criticality in Fuel Storage and Handling." USAR Section 3D.1.52 states, in part:

The fuel storage and handling, radioactive waste, and other systems which may contain radioactivity are designed to assure adequate safety under normal and postulated accident conditions. These systems are designed (1) with a capability to permit appropriate periodic inspection and testing of components important to safety, (2) with suitable shielding for radiation protection, (3) with appropriate containment, confinement, and filtering systems, (4) with a residual heat removal capability having reliability and testability that reflects the importance to safety of decay heat and other residual heat removal, and (5) to prevent significant reduction in fuel storage coolant inventory under accident conditions.

USAR Section 3D.1.53 states, in part:

Criticality in the fuel storage and handling system is prevented by physical systems or processes by using geometrically safe configurations.

3.0 TECHNICAL EVALUATION

The NRC staff's previous safety evaluations (SEs) for License Amendment Nos. 237 and 247 related to the licensee's SFP rerack project covered the following applicable technical areas:

thermal-hydraulic analysis of the SFP, cask pit and transfer pit; fuel-handling area ventilation; control and handling of heavy loads; criticality analysis of the high density fuel storage racks; structural materials analysis; structural mechanics analysis; and occupational radiation protection and radioactive waste.

The NRC staff has reviewed the licensee's regulatory and technical analyses in support of its proposed license amendment. The licensee's proposed changes do not involve any new technical requirements or expansion of the existing SFP as currently licensed; therefore, the applicability of the previously approved SEs is not changed. The proposed changes reflect only that spent fuel storage racks are no longer installed in the cask pit or transfer pit and that there are no longer any low density fuel storage racks in the SFP. Additionally, the changes relocate the requirements of TS 3/4.9.7 to the TRM. These proposed changes are administrative in nature and the detailed evaluation below will support the conclusion that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

The NRC staff has also reviewed the associated changes to the TS Bases made in support of the proposed license amendment and finds them to be consistent with the proposed revisions to the TSs reflecting the current DBNPS fuel storage design.

3.1 TS 3/4.9.7, "Crane Travel - Fuel Handling Building" The licensee provides the following basis for the proposed TS change:

The proposed amendment would delete TS 3/4.9.7 from the Technical Specifications and relocate it to the TRM. TS Limiting Condition for Operation (LCO) 3.9.7 requires:

Loads in excess of 2430 pounds shall be prohibited from travel over fuel assemblies in the spent fuel pool, cask pit*, or transfer pit.

The TS is applicable with fuel assemblies and water in the spent fuel pool, cask pit, or transfer pit. TS Surveillance Requirement (SR) 4.9.7 states:

The weight of each load, other than a fuel assembly, shall be verified to be < 2430 pounds prior to moving it over fuel assemblies in the spent fuel pool, cask pit*, or transfer pit.

The asterisked note affecting this LCO and SR states:

An impact cover weighing in excess of 2430 pounds may be moved over fuel assemblies in the cask pit provided that administrative controls are established. Other loads in excess of 2430 pounds may be moved over fuel assemblies in the cask pit provided: 1) an impact cover is installed, and 2) administrative controls are established to limit the load to 17,530 pounds and to limit the height that the load may travel over the impact cover.

The requirements of TS 3/4.9.7 will be relocated to the TRM upon implementation of the amendment. A change to page VIII of the TS Index is also proposed, reflecting the deletion of TS 3/4.9.7.

The NRC staff has evaluated the proposed change and finds it consistent with the criteria of 10 CFR 50.36(c)(2)(ii) for establishing an LCO. Limitations on transport loads in the fuel storage area are not installed instrumentation used to detect degradation of the reactor coolant pressure boundary; they are not considered an initial condition of a design basis accident or transient; they are not a structure, system, or component that mitigates any design basis accident or transient; and, they are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. Therefore, the TS 3/4.9.7 requirements do not meet any of the criteria for inclusion in the TSs and may be relocated to the TRM.

NUREG-1430, Revision 3, does not contain a LCO for crane travel in the fuel storage area.

Crane travel requirements previously reviewed and approved in NRC staff SEs (References 2 and 3) will continue to be in effect under the proposed change to relocate these requirements to the TRM. The TRM is incorporated by reference into the DBNPS USAR and any subsequent changes to the crane travel requirements by the licensee would require evaluation under the appropriate regulatory processes (e.g., 10 CFR 50.59). Given that current crane travel requirements will remain unchanged upon implementation of this amendment, the proposed change would have no adverse effect on nuclear safety and is, therefore, acceptable.

3.2 TS 3/4.9.11, "Storage Pool Water Level" The licensee provides the following basis for the proposed TS change:

The proposed amendment would revise TS 3/4.9.11 to reflect the removal of the allowance for temporary location of storage racks in the cask and transfer pits.

TS LCO 3.9.11 currently states:

As a minimum, 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks in the spent fuel pool, cask pit, or transfer pit.

The proposed change to TS LCO 3.9.11 would remove the reference to storage racks in the cask and transfer pits. The revised TS LCO 3.9.11 would state:

As a minimum, 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks in the spent fuel pool.

A similar change would be made to remove the reference to storage racks in the cask and transfer pits from the Applicability statement of TS 3.9.11. The revised applicability statement would state:

Whenever irradiated fuel assemblies are in the spent fuel pool.

TS SR 4.9.11 would also be revised to remove the reference to storage racks in the cask and transfer pits. The revised TS SR 4.9.11 would state:

The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the spent fuel pool.

The NRC staff has evaluated the proposed change and finds that it is appropriate to remove the requirements related to storage of fuel in the cask and transfer pits. The storage racks that were temporarily installed in the cask pit during the rerack project have been moved into the SFP. No storage rack was actually installed in the transfer pit during the rerack project. The licensee states that there is no foreseeable future need for fuel storage racks in either the cask or transfer pits. Given that current LCO and SR requirements for SFP water level will remain unchanged upon implementation of this amendment, the proposed change would have no adverse effect on nuclear safety and is, therefore, acceptable.

3.3 TS 3/4.9.12, "Storage Pool Ventilation" The licensee provides the following basis for the proposed TS change:

TS LCO 3.9.12 specifies requirements for the emergency ventilation systems servicing the storage pool area. The Applicability statement for TS LCO 3.9.12 states:

Whenever irradiated fuel is in the spent fuel pool, cask pit, or transfer pit, or during CORE ALTERATIONS or movement of irradiated fuel within the containment with the containment equipment hatch open.

The proposed change would remove the reference to storage racks in the cask and transfer pits. The revised Applicability statement would state:

Whenever irradiated fuel is in the spent fuel pool, or during CORE ALTERATIONS or movement of irradiated fuel within the containment with the containment equipment hatch open.

Similar changes would also be made to TS LCO 3.9.12 Action a and Action c.

The proposed change would revise Action a to state:

With one emergency ventilation system servicing the storage pool area inoperable, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the OPERABLE emergency ventilation system servicing the storage pool area is in operation and discharging through at least one train of HEPA

[high-efficiency particulate air] filters and charcoal adsorbers.

The proposed change would revise Action c to state:

With no emergency ventilation system servicing the storage pool area OPERABLE, suspend CORE ALTERATIONS and all operations involving movement of fuel within the containment or spent fuel pool, or crane operation with loads over the spent fuel pool, until at least one system is restored to OPERABLE status. CORE ALTERATIONS and fuel movement within containment may proceed provided the containment equipment hatch cover is closed and held in place by a minimum of four bolts.

The NRC staff has evaluated the proposed change and finds that it is appropriate to remove the requirements related to storage of fuel in the cask and transfer pits. The storage racks that were temporarily installed in the cask pit during the rerack project have been moved into the SFP. No storage rack was actually installed in the transfer pit during the rerack project. The licensee states that there is no foreseeable future need for fuel storage racks in either the cask or transfer pits. Given that current LCO and Action statement requirements for SFP ventilation will remain unchanged upon implementation of this amendment, the proposed change would have no adverse effect on nuclear safety and is, therefore, acceptable.

3.4 TS 3/4.9.13, "Spent Fuel Assembly Storage" The licensee provides the following basis for the proposed TS change:

TS LCO 3.9.13 specifies requirements for the placement of fuel assemblies in the spent fuel storage racks. TS LCO 3.9.13 currently states:

Fuel assemblies shall be placed in the spent fuel storage racks in accordance with the following criteria:

a.

Fuel assemblies stored in the spent fuel pool shall meet the criteria shown in Figure 3.9-1, when located in the low density spent fuel storage racks.

b.

Fuel assemblies stored in the cask pit shall meet the criteria shown in Figure 3.9-2, when located in the high density spent fuel storage racks.

c.

Fuel assemblies stored in the spent fuel pool or transfer pit shall meet the criteria shown in Figure 3.9-3, when located in the high density spent fuel storage racks.

The proposed change would revise TS LCO 3.9.13 to state:

Fuel assemblies stored in the spent fuel pool shall be placed in the spent fuel storage racks in accordance with the criteria shown in Figure 3.9-1.

The proposed change would delete TS Figure 3.9-1, "Burnup vs. Enrichment Curves for the Davis-Besse Low Density Spent Fuel Pool Storage Racks," and TS Figure 3.9-2, "Burnup vs. Enrichment Curve for the Davis-Besse High Density Cask Pit Storage Racks." Existing TS Figure 3.9-3, "Burnup vs.

Enrichment Curves for the Davis-Besse High Density Spent Fuel Pool and Transfer Pit Storage Racks," would be renumbered and renamed Figure 3.9-1, "Burnup vs. Enrichment Curves for the Davis-Besse High Density Spent Fuel Pool Storage Racks."

The proposed change would revise the applicability statement for TS LCO 3.9.13 to state:

Whenever fuel assemblies are in the spent fuel pool.

The proposed change would also revise the Action statement for TS LCO 3.9.13 to remove references to the cask pit, transfer pit, and the deleted figures. The revised TS LCO 3.9.13 Action statement would state:

With the requirement of the above specification not satisfied, suspend all other fuel movement within the spent fuel pool and move the non-complying fuel assemblies to allowable locations in accordance with Figure 3.9-1. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

TS SR 4.9.13.1 would also be revised to remove references to the cask pit, transfer pit, and the deleted figures. The revised SR 4.9.13.1 would state:

Prior to storing a fuel assembly in the spent fuel pool, verify by administrative means that the initial enrichment and burnup of the fuel assembly are in accordance with Figure 3.9-1.

The NRC staff has evaluated the proposed change and finds that it is appropriate to remove the requirements related to storage of fuel in the cask and transfer pits, and to revise the requirements related to low density fuel storage racks in the SFP. The storage racks that were temporarily installed in the cask pit during the rerack project have been moved into the SFP and there are no longer any low density fuel storage racks in the SFP. No storage rack was actually installed in the transfer pit during the rerack project. The rerack project replaced all low density fuel storage racks with high density fuel storage racks, which have been previously reviewed and approved for use in NRC staff SEs (References 2 and 3). The licensee states that there is no foreseeable future need for fuel storage racks in either the cask or transfer pits. Given that current LCO and SR requirements for the spent fuel storage racks will remain unchanged upon implementation of this amendment, and that the current TS Figures 3.9-1 and 3.9-2 are no longer applicable or required, the proposed change would have no adverse effect on nuclear safety and is, therefore, acceptable.

3.5 TS 5.6, "Fuel Storage" The licensee provides the following basis for the proposed TS change:

The proposed change would delete current TS 5.6.1.1 to reflect that there are no longer low density spent fuel storage racks at the DBNPS. TS 5.6.1.1 currently states:

5.6.1.1 The low density spent fuel pool storage racks are designed and shall be maintained with:

a.

A Keff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 1%

delta k/k for calculation uncertainty.

b.

A rectangular array of stainless steel cells spaced 12 31/32 inches on centers in one direction and 13 3/16 inches on centers in the other direction. Fuel assemblies stored in the spent fuel pool shall be placed in a stainless steel cell of 0.125 inches nominal thickness or in a failed fuel container.

c.

Fuel assemblies stored in the spent fuel pool in accordance with Technical Specification 3.9.13.

Existing TS 5.6.1.2 would be renumbered to TS 5.6.1.1. Existing TS 5.6.1.3 would be renumbered to TS 5.6.1.2 and revised to reflect the removal of storage racks from the cask and transfer pits. The new TS 5.6.1.2 would state:

The high density spent fuel pool storage racks are designed and shall be maintained with:

a.

A Keff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance for manufacturing tolerances and calculation uncertainty.

b.

A rectangular array of stainless steel cells with walls of 0.075 inches nominal thickness, spaced a nominal 9.22 inches on center in both directions. Boral neutron absorber material is utilized between each cell for criticality considerations.

c.

Fuel assemblies stored in the spent fuel pool in accordance with Technical Specification 3.9.13.

TS 5.6.3 would be revised to reflect that fuel is no longer stored in the transfer and cask pits. The revised TS 5.6.3 would state:

The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1624 fuel assemblies.

Although TS 5.6.2, "Drainage," contains references to the cask pit and transfer pit, the requirements for the cask and transfer pit remain appropriate to prevent inadvertent draining of the spent fuel pool. Therefore, TS 5.6.2 is considered acceptable as-is, and no change to TS 5.6.2 is proposed.

The NRC staff has evaluated the proposed change and finds that it is appropriate to remove the requirements related to storage of fuel in the cask and transfer pits, and to revise the requirements related to low density fuel storage racks in the SFP. The storage racks that were temporarily installed in the cask pit during the rerack project have been moved into the SFP and there are no longer any low density fuel storage racks in the SFP. No storage rack was actually installed in the transfer pit during the rerack project. The rerack project replaced all low density fuel storage racks with high density fuel storage racks, which have been previously reviewed and approved for use in NRC staff SEs (References 2 and 3). The licensee states that there is no foreseeable future need for fuel storage racks in either the cask or transfer pits. Given that current TS requirements for fuel storage will remain unchanged upon implementation of this amendment, and that the current TS 5.6.1.1 is no longer applicable or required, the proposed change would have no adverse effect on nuclear safety and is, therefore, acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (70 FR 29795). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1.

Bezilla, M.B. (FENOC) to U.S. NRC, "Davis-Besse Nuclear Power Station License Amendment Application to Revise Technical Specification Requirements for Refueling Operations and Design Features to Reflect the Status of the Spent Fuel Pool Rerack Project (License Amendment Request No. 02-0003)," dated April 22, 2005 (ADAMS Accession No. ML051160321) 2.

Pickett, D.V. (NRC) to Campbell, G.G. (FENOC), "Issuance of Amendment - Davis-Besse Nuclear Power Station, Unit 1 (TAC No. MA5477)," dated February 29, 2000 (ADAMS Accession No. ML003687008) 3.

Pickett, D.V. (NRC) to Campbell, G.G. (FENOC), "Issuance of Amendment - Davis-Besse Nuclear Power Station, Unit 1 (TAC No. MB0688)," dated October 19, 2001 (ADAMS Accession No. ML012910442)

Principal Contributor: W. Macon Date: August 16, 2005