ML092540310
| ML092540310 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/08/2009 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Jensen J Indiana Michigan Power Co |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC MD9837, TAC MD9838 | |
| Download: ML092540310 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 8, 2009 Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO MODIFY ALLOWABLE STORAGE PATTERNS IN SPENT FUEL STORAGE RACKS (TAC NOS. MD9837 AND MD9838)
Dear Mr. Jensen:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 311 and 293 to Renewed Facility Operating License Nos. DPR-58 and DPR-74 for the Donald C. Cook Nuclear Plant, Units 1 and 2, respectively. The amendments are in response to your application dated September 25, 2008 (Agencywide Documents Access and Management System Accession No. ML082820400).
The amendment modifies Figures 4.3-1 and 4.3-2 in the Technical Specifications (TS). These figures display allowable locations for nuclear fuel in the spent fuel pool storc:lge racks. The figures show two different allowable storage patterns for four of the storage rack modules. The amendment modifies these two figures such that fuel may be located in any of the four individual modules in accordance with either figure, and thus allow continued placement of new and intermediate burnup fuel in the spent fuel pool as the storage racks approach a full condition.
A copy of the associated safety evaluation is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
~----
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 311 to DPR-58
- 2. Amendment No. 293 to DPR-74
- 3. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 311 License No. DPR-58
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 25, 2008, 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
- 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 Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 311, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 45 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION C?;tv~t=,
Peter S. Tam, Acting Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications Date of Issuance: October 8, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 311 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Renewed Facility Operating License No. DPR-58 with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT -3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The change areas are identified by marginal lines.
REMOVE INSERT 4.0-4 4.0-4 4.0-5 4.0-5
- 3 and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix S, as revised through Amendment No. 311 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4) Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22,1983, December 23,1983, March 16, 1984, August 27,1985, Renewed License No. DPR-58 Amendment No. 311
Design Features 4.0
- MODULE A1
- MODULE C1~
- MODULE E1
- MODULE AS ~
~'.:.-; '..
>. /.".
REGION 1 CELLS o REGION 2 CELLS o REGION 3 CELLS
- The storage pattern for any of these individual modules may be as shown in this figure or Figure 4.3-2.
Figure 4.3-1 (page 1 of 1)
Normal Storage Pattern (Mixed Three Zone)
Cook Nuclear Plant Unit 1 4.0-4 Amendment No.~, 311
4.0 Design Features
- MODULE A1
~
- MODULE C1
- MODULE E1
- MODULE A5
~
181 EMPTY LOCATIONS REGION 1 CELLS o REGION 2 CELLS D
REGION 3 CELLS
- The storage pattern for any of these individual modules may be as shown in this figure or Figure 4.3-1.
Figure 4.3-2 (page 1 of 1)
Interim Storage Pattern (Checkerboard)
Cook Nuclear Plant Unit 1 4.0-5 Amendment No. 237, 311
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 293 License No. DPR-74
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 25, 2008, 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
- 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 Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Speci'f1cations contained in Appendix A and Appendix B, as revised through Amendment No. 293, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 45 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION q~~
Peter S. Tam, Acting Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications Date of Issuance: October 8, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following page of Renewed Facility Operating License No. DPR-74 with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT - 3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The change areas are identified by marginal lines.
REMOVE INSERT 4.0-4 4.0-4 4.0-5 4.0-5
- 3 radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to the renewed operating license The preoperational tests, startup tests and other items identified in Attachment 1 to this renewed operating license shall be completed. Attachment 1 is an integral part of this renewed operating license.
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix S, as revised through Amendment No. 293 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Additional Conditions (a) Deleted by Amendment No. 76 (b) Deleted by Amendment No.2 (c) Leak Testing of Emergency Core Cooling System Valves Indiana Michigan Power Company shall prior to completion of the first inservice testing interval leak test each of the two valves in series in the Renewed License No. DPR-74 Amendment No. 293
Design Features 4.0
- MODULE A1
- MODULE 1
C ~ 1""H'*5¥*
- MODULE E1
- MODULE A5~
REGION 1 CELLS o REGION 2 CELLS
[J REGION 3 CELLS
- The storage pattern for any of these individual modules may be as shown in this figure or Figure 4.3-2.
Figure 4.3-1 (page 1 of 1)
Normal Storage Pattern (Mixed Three Zone)
Cook Nuclear Plant Unit 2 4.0-4 Amendment No. 299, 293
4.0 Design Features
- MODULE A1 ~
- MODULE C1
- MODULE E1
- MODULE A5
~
'. :/",;<'~ /'.,/:
181 EMPTY LOCATIONS REGION 1 CELLS D
REGION 2 CELLS
[J REGION 3 CELLS
- The storage pattern for any of these individual modules may be as shown in this figure or Figure 4.3-1.
Figure 4.3-2 (page 1 of 1)
Interim Storage Pattern (Checkerboard)
Cook Nuclear Plant Unit 2 4.0-5 Amendment No. 2W, 293
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 311 AND 293 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-58 AND DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
By application dated September 25, 2008 (Reference 1), Indiana Michigan Power Company (the licensee) requested changes to the Technical Specifications (TSs) for the spent fuel pool (SFP) storage patterns at the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. The licensee's request was supported by an analysis performed for the licensee by Holtec International, which was included as Enclosure 3 to the licensee's September 25, 2008, request.
The licensee proposes to change the CNP TSs by modifying Figures 4.3-1 and 4.3-2. Currently, the figures describe two different allowable storage patterns for four of the storage rack modules. The proposed amendment would modify the two figures such that fuel may be located in any of these four individual storage rack modules in accordance with either figure. This will allow continued placement of new and intermediate burnup fuel in the SFP as the storage racks approach a full condition.
This change will allow increased flexibility in SFP storage. The proposed license amendment only changes the loading configuration in the SFP, and does not change the construction of the storage rack modules or expand the SFP storage capacity.
2.0 REGULATORY EVALUATION
2.1 Technical Specifications Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications,"
requires design features to be included that are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety, and are not covered by Safety Limits, Limiting Safety System Settings, Limiting Control Settings, Limiting Conditions for Operation, or Surveillance Requirements.
- 2 Irradiated fuel from both CNP units is stored in the spent fuel storage racks located in the common SFP. New fuel is also stored in the SFP prior to being placed in the reactor vessel during refueling operations. In the current CNP TSs, control of the storage of fresh and depleted fuel in the SFP is governed by a combination of TS 3.7.16, "Spent Fuel Pool Storage," and TS 4.3.1, "Fuel Storage - Criticality." The limits on depleted fuel are provided in TS 3.7.16.
Depleted fuel is divided into two categories, a highly burned category called Region 2 and a moderately burned category called Region 3. The description of how these two regions are intermixed in the SFP with the fresh fuel in Region 1 is described in TS 4.3.1.1.
Currently, TS 4.3.1.1 allows for one of two storage patterns in the SFP. One is called the "Normal Storage Pattern." In this configuration, all 23 storage modules have a mixed zone three region (MZTR) storage pattern. The MZTR storage pattern is where the Region 1 fuel is alternated with Region 2 fuel in the outer most row/column of each storage module. The second row/column of each storage module is filled with Region 2 fuel only. The remaining interior row/columns are filled with Region 3 fuel.
The other storage pattern is called the "Interim Storage Pattern." In this configuration, 19 storage modules have the MZTR storage pattern while the remaining 4 storage modules have the first and second row/column filled just like the MZTR storage pattern, but the interior area is filled with a "checkerboard" of Region 1 fuel and empty storage cells.
The proposed amendment would allow those 4 storage modules to have either the MZTR or the checkerboard storage pattern in any combination of those 4 modules while the remaining 19 would have to meet the MZTR requirements.
2.2 Criticality Accident Requirements Title 10 of the Code of Federal Regulations, Section 70.24, "Criticality accident requirements,"
requires that licensees authorized to possess specified quantities and forms of special nuclear material maintain provisions for monitoring criticality and mitigating the consequences of criticality accidents.
The current storage patterns were approved on January 14, 1993 (Reference 2), by license amendments 169 and 152 for Units 1 and 2, respectively. From that licensing activity, the regulatory requirement is that the CNP SFP must have a maximum calculated reactivity (kef!) of no greater than 0.95, including all biases and uncertainties at the 95/95 probability/confidence level without credit for soluble boron for normal conditions.
Inadvertent accidental criticality will be precluded through compliance with the TSs, the geometric spacing of fuel assemblies in the new fuel storage facility and SFP, and administrative controls imposed on fuel handling procedures.
The CNP Plant Specific Design Criteria is described in Section 1.4 of the Updated Final Safety Analysis Report. Criterion 66, "Prevention of Fuel Storage Criticality," discusses that the new and spent fuel storage racks are designed so it is impossible to insert assemblies other than in the storage cells, thereby maintaining separation. The spent fuel storage racks are designed with multiple regions that accept assemblies based on their reactivity values. Borated water is used to fill the spent fuel storage pool at a concentration to match that used in the reactor cavity
- 3 and refueling canal during refueling operations. Minimum boron requirements for the SFP and the reactor cavity during refueling operations are described in the TSs.
The fuel is stored vertically in an array with sufficient center-to-center distance between assemblies to assure keff is less than or equal to 0.95 even if unborated water were used to fill the pool. During reactor vessel head removal, and while loading and unloading fuel from the reactor, the boron concentration is maintained at not less than that required to shut down the core to a keff of 0.95.
Finally, a minimum of 2400 parts per million (ppm) of soluble boron is required in the SFP when fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool. This limit is specified in TS Section 3.7.15.
3.0 TECHNICAL EVALUATION
3.1 Methodology Currently, there is not a generically-approved methodology for performing SFP criticality analyses. Therefore, licensees must submit a plant-specific SFP criticality analysis that includes technically supported margins. The purpose of this amendment request is to change the allowed apportionment of the two patterns - the MZTR or the "checkerboard" without changing the patterns themselves. The approach taken in this amendment request relies on the analysis that was performed when the racks were approved on January 14, 1993 (Reference 2). The original analysis was performed on a per pattern basis. Each storage pattern was modeled as an infinite array of either one of the two patterns. The analysis (Reference 2) determined that the normal condition keff for each storage pattern to be approximately 0.940. During the course of preparing this amendment request, the licensee determined that a misloading event in the "checkerboard" storage pattern had not been considered as part of the original analysis; therefore, this request contains an analysis of a misloading event in the checkerboard storage pattern. The misloading event is analyzed as a 5x5 array of "checkerboarded" fresh fuel with a misloaded fresh fuel assembly in the center of the array with periodic boundary conditions. This model does not consider the possibility that a misloading closer to the Region 1 and Region 2 fuel assemblies may actually be more reactive. However, the periodic boundary conditions make it an infinite array of misloaded fuel assemblies rather than a single misloaded fuel assembly, and the empty cells between the misloaded fuel assemblies will tend to decouple one misloading from another. These effects are considered in Section 3.3 below.
3.2 Original Analysis The proposed amendment request is heavily reliant on the original SFP criticality analysis. In the original analysis, the normal condition keff for both storage patterns had very similar nominal keffand rack-up of the biases and uncertainties. The normal condition keff for both storage patterns was concluded to be approximately 0.940 without credit for soluble boron. Although the vintage of the original analysis indicates there may be aspects that would not meet today's standards, the original analysis has approximately 1 percent b.keff margin to the requirement for keff to be less than 0.95. Because of this substantial margin, staff did not revisit the original analysis. The explicit conditions of the SFP modules being all 23 MZTR or 19 MZTR and four
- 4 "checkerboard" storage patterns were not analyzed. Instead, each storage pattern was analyzed as an infinite array of itself. The interaction between the modules is what would come into play when the storage patterns are placed next to each other. Since the storage patterns had very similar normal condition keff and rack-up of the biases and uncertainties, coupled with the first two rows/columns of each pattern being identical, indicates the interaction between the different storage patterns will be very similar to the interaction between the same storage patterns.
Therefore, the quantity of one storage pattern or another is not particularly important.
3.3 Misloading in the "Checkerboard" Storage Pattern The misloading event is analyzed as a 5x5 array of checkerboarded fresh fuel with a misloaded fresh fuel assembly in the center of the array with periodic boundary conditions. Since CNP normally has a soluble boron in the SFP and the double contingency principle only requires one independent accident/abnormal condition to be considered at a time, the CNP credits soluble boron in an accident/abnormal condition. The analysis was performed with 800 ppm of soluble boron in the SFP and determined the keff under these conditions was approximately 0.930.
Except for the bias and uncertainties resulting from the criticality analysis using the MCt\\lP4a three-dimensional Monte Carlo code, the misloading event analysis uses the bias and uncertainty values determined in the original analysis. This brings the potential vintage concerns of the original analysis into the current analysis. The current analysis has potential areas of interest (e.g., whether or not a misloading essentially in the center of the "checkerboard" is the limiting condition). However, the resultant keff of 0.930 provides approximately a 2 percent Likeff margin to the requirement for keff to be less than 0.95. Since this value is determined using a concentration of 800 ppm soluble boron in the SFP, and the CNP TS 3.7.15 requires a minimum concentration of 2400 ppm soluble boron in the SFP, the staff concludes there is ample margin to draw a reasonable assurance conclusion that a misloading event in the checkerboard storage pattern will continue to meet the regulatory requirements regarding SFP criticality with the requested change.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts of any effluents 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 considerations, and there has been no public comment on such finding (73 FR 76411). 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.
- 5
6.0 CONCLUSION
The Commission 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. Letter from Mr. Lawrence J. Weber, Site Vice President, Indian Michigan Power Company, to the U.S. NRC Document Control Desk, RE: "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos. 50-315 and 50-316, License Amendment Request to Modify Allowable Storage Patterns in Spent Fuel StorClge Racks," dated September 25, 2008 (ADAMS Accession No. ML082820400).
- 2. Letter from U.S. NRC to Mr. E. E. Fitzpatrick, Vice President, Indiana Michigan Power Company, RE: "Donald C. Cook Nuclear Plant, Units 1 and 2 - Amendment Nos. 169 and 152 to Facility Operating License Nos. DPR-58 and DPR-74 (TAC Nos. M80615 and M80616)," dated January 14, 1993 (ADAMS Accession No. ML021060153).
Principal Contributor: Kent A. L. Wood, NRRlDSS/SRXB Date: October 8, 2009
Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUB~IECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT TO MODIFY ALLOWABLE STORAGE PATTERNS IN SPENT FUEL STORAGE RACKS (TAC NOS. MD9837 AND MD9838)
Dear Mr. Jensen:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 311 and 293 to Renewed Facility Operating License Nos. DPR-58 and DPR-74 for the Donald C. Cook Nuclear Plant, Units 1 and 2, respectively. The amendments are in response to your application dated September 25,2008 (Agencywide Documents Access and Management System Accession No. ML082820400).
The amendment modifies Figures 4.3-1 and 4.3-2 in the Technical Specifications (TS). These figures display allowable locations for nuclear fuel in the spent fuel pool storage racks. The figures show two different allowable storage patterns for four of the storage rack modules. The amendment modifies these two figures such that fuel may be located in any of the four individual modules in accordance with either figure, and thus allow continued placement of new and intermediate burnup fuel in the spent fuel pool as the storage racks approach a full condition.
A copy of the associated safety evaluation is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 311 to DPR-58
- 2. Amendment No. 293 to DPR-74
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC RidsNrrPMDCCook Resource RidsNrrDssSrxb Resource LPL3-1 RlF RidsNrrDorlDpr Resource RidsNrrDirsltsb Resource RidsNrrDorlLpl3-1 Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrLATHarris Resource RidsAcrsAcnw_MailCTR Resource KWood, NRRlDSS ADAMS Accesslon N0: ML092540310
LPL3-1/(A)BC NAME TBeltz THarris GCranston
- RElliott AJones PTam DATE 10/05/09 09/18/09 08/24/09 10/07/09 09/30/09 10/08/09 OFFICIAL RECORD COpy