ML092710609
ML092710609 | |
Person / Time | |
---|---|
Site: | Palo Verde |
Issue date: | 09/30/2009 |
From: | Hall J Plant Licensing Branch IV |
To: | Edington R Arizona Public Service Co |
Hall, J R, NRR/DORL/LPL4, 301-415-4032 | |
References | |
TAC ME1552, TAC ME1553, TAC ME1554 | |
Download: ML092710609 (19) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C.
September 30, 2009 Mr. Randall K.
Executive Vice President Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND ISSUANCE OF AMENDMENTS RE: ADOPTION OF TSTF-511, REVISION 0, "ELIMINATE WORKING HOUR RESTRICTIONS FROM TS 5.2.2 TO SUPPORT COMPLIANCE WITH 10 CFR PART 26" (TAC NOS. ME1552, ME1553, AND ME1554)
Dear Mr. Edington:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 175 to Facility Operating License No. NPF-41, Amendment No. 175 to Facility Operating License No. NPF-51, and Amendment No. 175 to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively.
The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 28, 2009, as supplemented by letter dated August 3, 2009. The amendments revise TS 5.2.2, "Unit Staff," to eliminate working hour restrictions in paragraph d to support compliance with the revisions to Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs," that became effective on March 31, 2008. The changes are consistent with guidance contained in the NRC-approved Revision 0 to Technical Specifications Task Force (TSTF) change traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The availability of this improvement was announced in the Federal Register on December 30, 2008 (73 FR 79923), as part of the consolidated line item improvement process.
R. Edington -2 A copy of the related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely,?'tL'-;(. ))A James R. Hall, Senior Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket Nos. STN 50-528, STN and STN
Enclosures:
- 1. Amendment No. 175 to 2. Amendment No. 175 to 3. Amendment No. 175 to 4. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL. DOCKET NO. STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 175 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated May 28,2009, as supplemented by letter dated August 3,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
Enclosure 1
-2Accordingly, 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-41 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-41 and Technical Specifications Date of Issuance:
September 30, 2009 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL. DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 175 License No. NPF-51 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated May 28,2009, as supplemented by letter dated August 3,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
Enclosure 2
-2Accordingly, 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 1\10. NPF-51 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-51 and Technical Specifications Date of Issuance:
September 30, 2009 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET DOCKET NO. STN PALO VERDE NUCLEAR GENERATING STATION, UNIT AMENDMENT TO FACILITY OPERATING Amendment No. 175 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated May 28, 2009, as supplemented by letter dated August 3, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
Enclosure 3
-2Accordingly, 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-74 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-74 and Technical Specifications Date of Issuance:
September 30, 2009 ATTACHMENT TO LICENSE AMENDMENT NOS. 175. 175. AND FACILITY OPERATING LICENSE NOS. NPF-41. NPF-51, AND DOCKET NOS. STN 50-528, STN 50-529, AND STN Replace the following pages of the Facility Operating Licenses Nos. NPF-41, NPF-51, and NPF-74, and 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. Operating REMOVE Replace Page 5 of Facility Operating License No. NPF-41 with the attached Page Replace Page 6 of Facility Operating License No. NPF-51 with the attached Page Replace Page 4 of Facility Operating License No. NPF-74 with the attached Page Technical REMOVE INSERT 5.2-2 5.2-2 5.2-3 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Operating Staff Experience Requirements Deleted Post-Fuel-Loading Initial Test Program (Section 14, SER and SSER 2)* Deleted Environmental Qualification Deleted Fire Protection Program APS 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, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Emergency Preparedness Deleted "The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 175 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Operating Staff Experience Requirements (Section 13.1.2, SSER 9)* Deleted Initial Test Program (Section 14, SER and SSER 2) Deleted Fire Protection Program APS 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, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Inservice Inspection Program (Sections 5.2.4 and 6.6, SER and SSER 9) Deleted Supplement NO.1 to NUREG-0737 Requirements Deleted *The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 175 Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3876 megawatts thermal (100% power) through operating cycle 13, and 3990 megawatts thermal (100% power) after operating cycle 13, in accordance with the conditions specified herein. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Initial Test Program (Section 14, SER and SSER 2) Deleted Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 171, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions. Mitigation Strategy License Condition APS shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas: Fire fighting response strategy with the following elements: Pre-defined coordinated fire response strategy and guidance. Assessment of mutual aid fire fighting assets. Designated staging areas for equipment and materials. Command and control. Training of response personnel.
Amendment No. 175 Revised by letter dated August 2, 2007 Organization 5.2 Organization 5.2.2 Unit Staff (continued) shall be assigned for each control room from which a reactor is operating in MODES 1. 2. 3. or 4. b. Shift crew composition shall meet the requirements stipulated herein and in 10 CFR 50.54(m).
Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and and 5.2.2.e 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. 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. The Operations Department Leader or Operations Supervisor*
shall hold an SRO license. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics.
reactor engineering.
and plant analysis regard to the safe operation of the unit. In addition.
the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on . PALO VERDE UNITS 5.2-2 AMENDMENT NO. 175 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 175 TO FACILITY OPERATING LICENSE NO. NPF-41, AMENDMENT NO. 175 TO FACILITY OPERATING LICENSE NO. NPF-51, AND AMENDMENT NO. 175 TO FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY, ET AL. PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530
1.0 INTRODUCTION
By letter dated May 28, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091560229), as supplemented by letter dated August 3,2009 (ADAMS Accession No. ML092250361), Arizona Public Service Company (APS, the licensee), requested changes to the Technical Specifications (TSs) for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. The proposed amendment would revise TS 5.2.2, "Unit Staff," to eliminate working hour restrictions in paragraph d of TS 5.2.2 to support compliance with Title 10 of the Code of Federal Regulations (10 CFR), Part 26. The supplemental letter dated August 3, 2009, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 28,2009 (74 FR 37247). APS stated that the application is consistent with NRC-approved Technical Specification Task Force (TSTF) change traveler, TSTF-511, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." The PVNGS TS have minor differences when compared to the Standard Technical Specifications (STS) addressed by TSTF-511.
Section 3.0 of this safety evaluation discusses the differences between the STS addressed by TSTF-511 and the PVNGS TSs. 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. EnclosureA
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2.0 REGULATORY EVALUATION
The history of the NRC regulations pertaining to prevention of worker impairment is summarized in the Federal Register notice containing the final rule that amended 10 CFR Part 26 (73 FR 16966, March 31,2008).
Subpart I, "Managing Fatigue," of 10 CFR Part 26 provides the regulatory requirements for managing worker fatigue at nuclear power plants. The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR Section 50.36, "Technical specifications." The regulations in 10 CFR 50.36 require that the TS include items in the following categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (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's guidance for the format and content of the licensee's TSs can be found in NUREG-1432, Revision 3, "Standard Technical Specifications Combustion Engineering Plants," referred to as the STS. TS 5.0 of the STS contains administrative controls.
Paragraph d of TS 5.2.2 of the STS contains requirements for administrative procedures to limit the working hours of personnel who perform safety-related functions.
This paragraph represents NRC's guidance on how licensees' 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 TS 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 affect 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, Revision 0, proposed a change to the STS that would delete paragraph d of STS 5.2.2. This change was approved in a Federal Register notice on December 30,2008 (73 FR 79923). 2.1 Adoption of TSTF-511, Revision 0, by APS Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by APS will provide reasonable assurance that APS will maintain limits on the working hours of personnel who perform safety-related functions at the PVNGS. APS has committed to remove the specific TS requirements concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements; or to meet both sets of requirements until the amendment request is approved by NRC and subsequently implemented by the licensee.
-3.0 TECHNICAL 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 PVNGS are currently located in paragraph d of TS 5.2.2. When the amendment is implemented, the regulatory requirements of 10 CFR 26, Subpart I will effectively replace the plant-specific TS requirements found in paragraph d of the PVNGS 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 are best provided by the licensee's administrative processes, including its commitment management program (see NRC Regulatory Issue Summary 2000-017, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," dated September 21,2000).
The above regulatory commitment does not warrant the creation of regulatory requirements (items requiring prior NRC approval of subsequent changes).
The verbiage of PVNGS TS 5.2.2, paragraph d, is similar, but not identical, to the verbiage of STS 5.2.2, paragraph
- d. The differences are as follows:
- STS 5.2.2, paragraph d, states that the plant manager or plant manager's designee must authorize deviations from the guideline on working hours. PVNGS TS 5.2.2, paragraph d, allows such deviations to be approved by the director level or their designees.
- STS 5.2.2, paragraph d, requires the conduct of a periodic, independent review to ensure that excessive hours have not been assigned.
PVNGS TS 5.2.2, paragraph d, does not require that this review be independent, but rather requires that the review be conducted monthly by authorized individuals or designees.
These differences are insignificant, as the intent of TSTF-511, Revision 0, is to delete those TS requirements that are superseded by the revised regulations in 10 CFR Part 26, Subpart I. APS proposed a deviation to the model safety evaluation commitment.
This deviation changes the commitment to include TS implementation after October 1, 2009, the required 10 CFR Part 26 final rule implementation date. The licensee's stated commitment is as follows: Removal of the plant-specific Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements.
In the event NRC approval for the requested amendment is not obtained before October 1, 2009, the amendment shall be implemented within 30 days of NRC approval and APS shall comply with the new 10 CFR 26, Subpart I, requirements and current Technical Specifications until the approved TS changes are implemented.
-This difference is acceptable to the NRC staff. After October 1, 2009, PVNGS must comply with both its TSs and the regulations stated in 10 CFR Part 26. The NRC staff evaluated the licensee's proposed change against the applicable regulatory requirements listed in Section 2.0 of this safety evaluation.
The staff also compared the proposed change to the change made to the STS by TSTF-511, Revision O. The staff considered the licensee's commitment to implement 10 CFR Part 26, Subpart I concurrently with the deletion of TS work hour control requirements in its evaluation of the proposed change. Given the licensee's commitment, there is reasonable assurance that the licensee will comply with the regulations for work hour controls, either through TS requirements or through the requirements of 10 CFR Part 26, Subpart I, at all times at PVNGS. Therefore, the licensee will continue to prevent worker fatigue from adversely affecting public health and safety and the common defense and security.
Therefore, the NRC staff concludes the proposed change is acceptable.
4.0 REGULATORY COMMITMENT In its May 28, 2009, letter, the licensee made the following regulatory commitment:
Removal of the plant-specific Technical Specification requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements.
In the event NRC approval for the requested amendment is not obtained before October 1, 2009, the amendment shall be implemented within 30 days of NRC approval and APS shall comply with the new 10 CFR 26, Subpart I, requirements and current Technical Specifications until the approved TS changes are implemented.
The NRC staff considers this to be a regulatory commitment and concludes that it is acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendments.
The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION The amendments change recordkeeping, reporting, or administrative procedures.
Accordingly, the amendments meet 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 amendments.
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7.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
K. Bucholtz Date: September 30, 2009 R. Edington -2 A copy of the related Safety Evaluation is also enclosed.
The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, IRA! James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 175 to NPF-41 2. Amendment No. 175 to NPF-51 3. Amendment No. 175 to NPF-74 4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrPMPaloVerde Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource KBucholtz, NRRIDIRS/ITSB ALewin. NRRlDIRS/ITSB ADAMS Accession No ML092710609
- SE memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA DIRSIITSB/BC OGC NRR/LPL4/BC NRR/LPL4/PM NAME JRHalt JBurkhardt REltiott*
Not Required MMarkley JRHalt DATE 9/29/09 9/29/09 7/28/09 9/30109 9/30109 OFFICIAL AGENCY RECORD