ML091470163
| ML091470163 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/24/2009 |
| 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 ME1012, TAC ME1013 | |
| Download: ML091470163 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 24, 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 AMENDMENT TO ELIMINATE WORKING HOUR RESTRICTIONS FROM TECHNICAL SPECIFICATIONS TO SUPPORT COMPLIANCE WITH 10 CFR PART 26 (TAC NOS. ME1012 AND ME1013)
Dear Mr. Jensen:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 310 and 292 to Renewed Facility Operating License Nos. DPR-58 and DPR-74 for the Donald C.
Cook Nuclear Plant, Units 1 and 2, respectively.
The amendment deletes those portions of the Technical Specifications (TS) superseded by Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs,"
Subpart I, "Managing Fatigue." The change is consistent with NRC-approved Technical Specification Task Force (TSTF) Improved Standard TS Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26,"
Revision O.
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, Ter 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. 310 to DPR-58
- 2. Amendment No. 292 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. 310 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 March 19, 2009, as supplemented by letter dated April 17, 2009, 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 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. 310 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 2
- 3.
The license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION y!()/J~~
Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Appendix A Date of Issuance: July 24, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 310 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 page of Appendix A, Technical Specifications, with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT 5.2-2 5.2-2
- 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 B, as revised through Amendment No. 310 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. 310
5.2 Organization 5.2 Organization 5.2.2 Unit Staff (continued)
- b.
Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements;
- c.
A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;
- d.
DELETED
- e.
The operations manager must hold or have held a Senior Operator license at Cook Nuclear Plant or a similar reactor, or have been certified for equivalent Senior Operator knowledge. If the operations manager does not hold an Senior Operator license, then a line operations middle manager shall hold a Senior Operator license for the purposes of directing operational activities; and
- f.
In MODE 1,2,3, or 4, an individual (shared with Unit 2) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Cook Nuclear Plant Unit 1 5.2-2 Amendment No.~, 310
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. 292 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 March 19,2009, as supplemented by letter dated April 17, 2009, 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 Renewed Facility Operating License No. DPR-74 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. 292 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 2
- 3.
The license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION
-, t
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Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Appendix A Date of Issuance: July 24, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 292 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 page of Appendix A, Technical Specifications, with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT 5.2-2 5.2-2
- 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. 292 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. 292
5.2 Organization 5.2 Organization 5.2.2 Unit Staff (continued)
- b.
Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements;
- c.
A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;
- d.
DELETED
- e.
The operations manager must hold or have held a Senior Operator license at Cook Nuclear Plant or a similar reactor, or have been certified for equivalent Senior Operator knowledge. If the operations manager does not hold an Senior Operator license, then a line operations middle manager shall hold a Senior Operator license for the purposes of directing operational activities; and
- f.
In MODE 1,2,3, or 4, an individual (shared with Unit 1) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Cook Nuclear Plant Unit 2 5.2-2 Amendment No. ~, 292
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 310 AND 292 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 March 19, 2009 (Reference 1), as supplemented by letter dated April 17, 2009 (Reference 2), Indiana Michigan Power Company (I&M, the licensee) requested changes to the Technical Specifications (TS) for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2.
The proposed changes would delete Paragraph d of TS 5.2.2, "Unit Staff."
The April 17, 2009, supplement was issued to provide the State of Michigan the enclosure and attachments associated with the original March 19, 2009, application, as required pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50.91(b). Therefore, this supplement did not expand the scope of the application as originally noticed, and did not change the staff's proposed no significant hazards consideration published in the Federal Register on May 5, 2009 (74 FR 20750).
The licensee stated that its application is consistent with NRC-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26," (Reference 3). Both CNP-1 and CNP-2 have improved TSs with text similar to that discussed in TSTF-511, although TS 5.2.2, Paragraph d, is not an exact duplicate to STS 5.2.2, Paragraph d. The availability of this TS improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923) as part of the consolidated line item improvement process (CLlIP).
2.0 REGULATORY EVALUATION
The history of NRC regulations pertaining to prevention of worker impairment is summarized in a March 31, 2008, Federal Register notice containing the final rule that amended 10 CFR Part 26 (73 FR 16966). Title 10 of the Code of Federal Regulations Part 26, Subpart I, provides the regulatory requirements for managing worker fatigue at nuclear power plants.
- 2 The NRC regulatory requirements related to the content of the TSs are contained in 10 CFR Part 50.36. Title 10 CFR 50.36 requires that the TSs include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) Surveillance Requirements (SR); (4) design features; and (5) administrative controls. The administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
The NRC guidance for the format and content of licensee TSs can be found in NUREG-1430, Revision 3.0, "Standard Technical Specifications Babcock and Wilcox Plants," NUREG-1431, Revision 3.0, "Standard Technical Specifications Westinghouse Plants," NUREG-1432, Revision 3.0, "Standard Technical Specifications Combustion Engineering Plants," NUREG 1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4," and NUREG-1434, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/6," referred to as Standard Technical Specifications (STS). Section 5 of STS contains administrative controls. Paragraph d of Section 5.2.2 of STS contains requirements for administrative procedures to limit the working hours of personnel who perform safety-related functions. This paragraph represents NRC guidance on how licensee TS requirements should address work hour controls. Licensees adhere to the guidance to varying degrees due to minor administrative differences and differences in each licensee's current licensing basis. The inconsistent level of adherence to NRC guidance has lead to inconsistent TS interpretation and implementation. This has also made it difficult for NRC to enforce the requirements.
The new requirements of 10 CFR Part 26, Subpart I supersede the guidance for requirements found in Paragraph d of Section 5.2.2 of all STS. Subpart I distinguishes between work hour controls and fatigue management and strengthens the requirements for both. Subpart I requires nuclear power plant licensees to ensure against worker fatigue adversely affecting public health and safety and the common defense and security by establishing clear and enforceable requirements for the management of worker fatigue. Licensees are required to implement Subpart I by October 1, 2009 as announced in the Final rule that revised 10 CFR Part 26 (73 FR 16966, March 31, 2008). TSTF-511 proposed a change to STS that would delete Paragraph d of STS 5.2.2. This change was approved in Federal Register notice on December 30,2008 (73 FR 79923).
2.1 Adoption of TSTF-511, Revision 0, by CNP Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by I&M will provide reasonable assurance that I&M will maintain limits on the working hours of personnel who perform safety-related functions. I&M has committed to remove the plant-specific TS requirements concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
3.0 TECHNICAL EVALUATION
Controls on work hours for personnel at nuclear power plants are necessary to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Work hour controls for CNP are currently located in Paragraph d of TS 5,2,2, When
- 3 implemented, the regulatory requirements of 10 CFR Part 26, Subpart I replace the plant specific TS requirements found in section 5.2.2 Paragraph d of CNP TSs.
The licensee proposed deleting Paragraph d of TS 5.2.2. The licensee committed to implement the new requirements of 10 CFR Part 26, Subpart I concurrently with the deletion of the TS requirements on work hour controls. The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitment(s) are best provided by the licensee's administrative processes, including its commitment management program (see Regulatory Issue Summary 2000-017, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff'). The above regulatory commitments do not warrant the creation of regulatory requirements (items requiring prior NRC approval of subsequent changes).
Both CNP-1 and CNP-2 have improved TSs with text similar to the text of TSTF-511. The CNP TS 5.2.2, Paragraph d, is not an exact duplicate to STS 5.2.2, Paragraph d.
TSTF-511, STS 5.2.2, Paragraph d states the following:
"Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., [licensed Senior Reactor Operators (SROs), licensed Reactor Operators (ROs), health physicists, auxiliary operators, and key maintenance personnel]).
The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.
Any deviation from the above guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.
Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned."
CNP, TS 5.2.2, Paragraph d states, "The amount of overtime worked by unit staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12)."
Generic Letter 82-12 has the same requirements as STS 5.2.2, Paragraph d. This difference is insignificant as the intent of TSTF-511 is to delete TSs superseded by the revised regulations in 10 CFR Part 26, Subpart I.
The staff evaluated the licensee's proposed change against the applicable regulatory requirements listed in Section 2.0. The staff also compared the proposed change to the change made to STS by TSTF-511. In its evaluation of the proposed change, the staff considered the licensee's commitment to implement 10 CFR Part 26, Subpart I, concurrent with the deletion of TS work hour control requirements. Given the licensee's commitment, there is reasonable
-4 assurance that the licensee will comply with the regulations for work hour controls at all times either through TS requirements or through the requirements of 10 CFR Part 26, Subpart I, and will continue to prevent worker fatigue from adversely affecting public health and safety and the common defense and security. Therefore, the staff finds the proposed change acceptable.
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 recordkeeping, reporting, or administrative procedures. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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 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 Lawrence J. Weber, Indiana Michigan Power Company, to USNRC Document Control Desk, re: "License Amendment Request for Adoption of TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26" (ADAMS Accession No. ML090920411 ).
- 2. Letter from Lawrence J. Weber, Indiana Michigan Power Company, to USNRC Document Control Desk, re: "Supplement to License Amendment Request for Adoption of TSTF-511, Revision a, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26" (ADAMS Accession No. ML091190309).
- 3. Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, Revision a, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26."
- 4. Federal Register Notice, Notice of Availability published on December 30, 2008 (73 FR 79923).
Principal Contributor: Kristy Bucholtz, NRR Date: July 24, 2009
July 24, 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 ELIMINATE WORKING HOUR RESTRICTIONS FROM TECHNICAL SPECIFICATIONS TO SUPPORT COMPLIANCE WITH 10 CFR PART 26 (TAC NOS. ME1012 AND ME1013)
Dear Mr. Jensen:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 310 and 292 to Renewed Facility Operating License Nos. DPR-58 and DPR-74 for the Donald C.
Cook Nuclear Plant, Units 1 and 2, respectively.
The amendment deletes those portions of the Technical Specifications (TS) superseded by Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs,"
Subpart I, "Managing Fatigue." The change is consistent with NRC-approved Technical Specification Task Force (TSTF) Improved Standard TS Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26,"
Revision O.
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. 310 to DPR-58
- 2. Amendment No. 292 to DPR-74
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:
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- b ML 9 470163 LPL3-1/PM OFFICE NAME DATE ITSB/BC LPL3-'I/LA RElliott TBeltz BTuily 06/30/09 06/26/09 05/19/09 19 2009 memo d t aed M a LPL3-1/BC OGC/NLO LSubin LJames 07/24/09 07/13/09 OFFICIAL RECORD COPY