ML091770664
| ML091770664 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle, Farley  |
| Issue date: | 09/04/2009 |
| From: | Martin R Plant Licensing Branch II |
| To: | Ajuni M Southern Nuclear Operating Co |
| Martin R, NRR/DORL, 415-1493 | |
| References | |
| TAC ME1351, TAC ME1352, TAC ME1353, TAC ME1354, TAC ME1355, TAC ME1356 | |
| Download: ML091770664 (39) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 4, 2009 Mr. Mark J. Ajluni Manager, Nuclear Licensing Southern Nuclear Operating Company, Inc 40 Inverness Center Parkway P.O. Box 1295 Birmingham, Alabama 35201
SUBJECT:
SOUTHERN NUCLEAR OPERATING COMPANY, INC., PLANTS (FARLEY, HATCH, VOGTLE) ISSUANCE OF AMENDMENTS REGARDING ELIMINATION OF WORKING HOUR RESTRICTIONS FROM TECHNICAL SPECIFICATIONS, TSTF-511 (TAC NOS. ME1351, ME1352, ME1353, ME1354, ME1355 AND ME1356)
Dear Mr. Ajluni:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 182 to Renewed Facility Operating License NPF-2 and Amendment No. 175 to Renewed Facility Operating License t\\lPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP);
Amendment No. 262 to Renewed Facility Operating License DPR-57 and Amendment No. 206 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (HNP); and Amendment No. 156 to Renewed Operating License NPF-68 and Amendment 1\\10. 137 to Renewed Operating License NPF-81 for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP), respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 19, 2009.
The amendments delete those portions of the TS superseded by Title 10 of the Code of Federal Regulations (10 CFR ), Part 26, Subpart I. This change is consistent with the Nuclear Regulatory Commission (NRC)-approved Revision 0 to Technical Specification Task Force (TSTF) Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." 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.
M. Ajluni
- 2 A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, j11~1 Robe E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348,50-364,50-321, 50-366, 50-424, and 50-425
Enclosures:
- 1. Amendment No. 182 to NPF-2
- 2. Amendment No. 175 to NPF-8
- 3. Amendment No. 262 to DPR-57
- 4. Amendment 1\\10. 206 to NPF-5
- 5. Amendment No. 156 to NPF-68
- 6. Amendment No. 137 to NPF-81
- 7. Safety Evaluation cc w/encl: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 182 Renewed License No. NPF-2
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated May 19, 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 license 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. NPF-2 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 182, are hereby incorporated in the license. Southern Nuclear 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 by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION f{'
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Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-2 and the Technical Specifications Date of Issuance: September 4, 2009
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 175 Renewed License No. NPF-8
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated May 19, 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 license 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. NPF-8 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.175, are hereby incorporated in the license. Southern Nuclear 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 by October 1,2009.
FOR THE NUCLEAR REGULATORY COMMISSIOI\\I I
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Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-8 and the Technical Specifications Date of Issuance:
September 4, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 182 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND TO LICENSE AMENDMENT NO. 175 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License License No. NPF-2, page 4 License No. NPF-2, page 4 License No. NPF-8, page 3 License No. NPF-8, page 3 TSs TSs 5.2-2 5.2-2 5.2-3 5.2-3
-4 (2)
Technical Specificalions The Technical SDPau:.,ations contained in Appendix A, 18 revised thr~)Ljgh Amendment No. 182are hereby IncorPorated In the renewed Ilcinse.
Southern Nuclear snail ope.rete the facility In accordance with the Technical Specifications.
(3)
Additional Condhions The ma~rB specified In the following conditi.ons shall be completed to the satisfaction of the Commlalon within the slated time I'QrJods following the Issuance lJf the renewed license or within "1M opera~al restrictions indicated. The removal of these col)ditions Ilha!l be made by.
an amendment to the renewed license supported by a"f8vorable " ""
evaluation by the Commissloli.
. a.
. Southern NuClear stlall not operate ttie reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation: "
- b.
Deleted per Amendment 13
- c.
Deleted per Amenc;fment 2
- d.
Deleted per Amendment 2
- e.
Deleted per Amet:ldment 152 Deleted per Amendment 2
- f.
Deleted per Amendment 158
- g.
Southern Nuclear shall maintain a secondary ~er chem~ry.
monitoring progrem to Inhibit steam generator tube de9~~on. ".
ThIs program shaD Include:
- 1) lden~flcatlonof a sampling schedule for the critical parameten; and control points fa these paramelen;;
- 2)
Identillcation 01 the procedures used to qua"ntify parameters that are critical to control poin~;
- 3)
Identification of process sampling points:
- 4)
A procedure for the recording and manageme~t of.data:
Farley - Unit 1 Renewed Ucense No:NPF-2 Amendment N~.: 182
~3*
(2)
Alabama Power 90mpany, pursuant to Section 1O~ or lhe Act and 10 CFR Part 50, "Ucenslng of Production and UtIlization FacA"ies.* to possess but not operate Ihe'facility at the designated location in Houston County, Alabama In accordance with Ie procedures and limitations set forth In this renewed Ucen~.
(3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70. to receive, p0S8888 and use at any time speCIal n.iclear material a8 reactor tuGr; In accordance with the Umltations for storage and.amounts required for reactor operation, as described In the Final Safety Analysis Report. as supplemented and amended; (4)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70.
to receive, pOssess, and use at any lime any byproduct. source and special nuclear material as sealed neutron Sources for reactor startup*
. ~ealed sources' for reactor Ins.trumentatlon and-ra'diatior'fmonitoring ".
equIpment calibration, and~as fission detectors In amounts as required; (5)
Southern Nuclear, pursuant to the Ad 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 calibration or associated with radfoactlve apparatus or components; and (6)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 3D, 40 and 70,
..to possess, but*not separate, such byproduct and special nuclear materials a~ may be'produced by the operation of the facility.
C.
This renewed license shall be deemed 10 contain and Is subjeCt to the conditions specified in the Commissions's regulations sel forth in 10 CFR Chapter I and is subject to aU applicable.provisions of the Act and the rules. regUlations, and orders 01 the CommissIon now or hereafter In eHeCl; and Is subject to*the additional conditions specified or Incorporated below:
(1)
Maximum. power Level Southern Nuclear is authorized to operate Ihe facility at reactor core power levels not in excess of 2775 megawatts thenna!.
(2)
Technical S'pecifiCations
'The' Technical SpACification~ contained in Appendix A, as revised through Amendment No. 175*.* are hereby Incorporated In the renewed Iic~nse.
Southern N'uclear snail. operate the facility in accordance with the Teet!nical Specifications.
Farley'
- Unit 2 Renewed UcensE' No. NPF-8'
. Amendment No:175
5.2.2 Organization 5.2 5.2 Organization Unit Staff (continued)
- b.
At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2,3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. A single SRO may fill this position for both units.
- c.
Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g 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.
- d.
A Health Physics 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.
- e.
Deleted.
(continued)
Farley Units 1 and 2 5.2-2 Amendment No.. 182 (Unit 1)
Amendment No. 175 (Unit 2)
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- f.
The Operations Manager or at least one Operations Superintendent shall hold an SRO license.
- g.
The Shift Technical Advisor (STA) shall provide advisory technical support to the responsible SRO in the areas of thermal hydraulics. reactor engineering. and plant analysis with 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 Shift. The same individual may fill this position for both units.
Farley Units 1 and 2 5.2-3 Amendment No. 182 (Unit 1)
Amendment No. 175 (Unit 2)
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 262 Renewed License No. DPR-57
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated May 19,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 262, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION
{lei G L,--7/5 {( (0 '['\\ J Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-57 and the Technical Specifications Date of Issuance:
September 4, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 262 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License Page 4 Page 4 TSs TSs 5.0-3 5.0-3 5.0-4 5.0-4
for sample analysis or Instrument calibration, or associated with radioactive apparatus or components; (6)
. Southern Nuclear, pursuanll0 the Act and 10 CFR Parts 30 and 70, to possess, but not saparale,such byproducl and special nuclear malerlals as may be produced by lhe operation of the facility.
C.
This renewed license shall be deemed 10 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, Sectlon 40.41 of Part 40, Section 50.54 of Part 50, end Section 70.32 of Part 70; all applicable provisions.of the Acland the rules, regulations, and orders of the CommissIon no~ or hereafter In effect; and the addltlonal conditions specified orIncorporated below:
(1)
Maximum Power level Southern Nuclear Is authorized 10 operate 'he faclllly at steady stale reactor core power levels not In excess of 2B04megawatis thermal.
(2)
, Technlcal Specifications The TechnlcaJ Specifications (Appendix A) and the Environmental' Prolection Plan (Appendix B), as revised through Amendment Ho.
are hereby Incorporated In.the renewed license. Southern Nuclear shall operate the facility In accordance with the TechnIcal Specifications and the Environmental Protection Plan.
The SUlVenJance RequIrement (SR) contelned In the Techni.cal Speclflcatlons and Bated below,ls not required to be pfllrformed Immed1ately upon ImplementaUon of Amendment No. 262. The SR nsted below shaD be successfully demorislratedprJor to the lime and conditIon specltled:
SR 3.8.1.18 shin be successfully demonstrated at Its neld regulal1y scheduled performance (3)
. fire ProtectloD Southern Nuclear shall lmplemenl and maintain In effect all prcMslons of the fire prolecUon program, whIch Is referenced In the Updated final Safety Analysis Report for the facility, as conlalned In the upda1ed Fire Hazards Analysis Bnd Are ProtecUon Program for Edwtn I. Hateh Nuclear Plant Units 1 and 2, which was originally submitted by letter dated July 22~ 1986. Southem Nuclear may make changes to the fire protecUon program without prior Commission approval only Hthe changes Renewed Ucense No. DPR*57 Amendment NO 262 l
5.2.2 Organization 5.2 5.2 Organization Unit Staff (continued)
- b.
At least one licensed Reactor Operator (RO) shall be present in the control room for each unit that contains fuel in the reactor. In addition, while the unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- c.
The minimum shift crew composition shall be in accordance with 10 CFR 50.54{m){2){i). Shift crew composition may be less than the minimum requirement of 10 CFR 50.54{m){2)(i) and 5.2.2.a 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.
- d.
An individual qualified to implement radiation protection procedures 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.
- e.
Deleted.
(continued)
HATCH UNIT 1 5.0-3 Amendment No. 262
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- f.
The Operations Manager or at least one Operations Superintendent shall hold an SRO license.
- g.
The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervisor in the areas of thermal hydraulics. reactor engineering, and plant analysis with 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 Shift.
HATCH UNIT 1 5.0-4 Amendment No. 262
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 206 Renewed License No. NPF-5
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated May 19, 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-5 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 206, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION I
(
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Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-5 and the Technical Specifications Date of Issuance:
September 4, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 206 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License Page 4 Page 4 TSs TSs 5.0-3 5.0-3 5.0-4 5.0-4
- 4 (6)
Southern Nuclear, 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 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions2 specified or incorporated below:
(1)
Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 206, are hereby incorporated in the renewed license. Southern Nuclear snail operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.
(a)
Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the the Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.
Renewed License No. NPF-5 Amendment No, 2D6
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- b.
At least one licensed Reactor Operator (RO) shall be present in the control room for each unit that contains fuel in the reactor. In addition, while the unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- c.
The minimum shift crew composition shall be in accordance with 10 CFR 50.54(m)(2)(i). Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a 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.
- d.
An individual qualified to implement radiation protection procedures 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.
- e.
Deleted.
(continued)
HATCH UNIT 2 5.0-3 Amendment No. 206
5.2.2 Organization 5.2 5.2 Organization Unit Staff (continued)
- f.
The Operations Manager or at least one Operations Superintendent shall hold an SRO license.
- g.
The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with 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 Shift.
HATCH UNIT 2 5.0-4 Amendment No. 206
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 156 Renewed License No. NPF-68
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Renewed Facility Operating License No. NPF-68 filed by the Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated May 19, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules alld regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.156, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-68 and the Technical Specifications Date of Issuance: September 4, 2009
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 137 Renewed License No. NPF-81
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Renewed Facility Operating License No. NPF-81 filed by the Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated May 19, 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-81 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.137, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009.
FOR THE NUCLEAR REGULATORY COMMISSION J ~. "
[teL Lc,_~ /~/l L [1:'7/
Undine Shoop, Acting Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility License No. NPF-81 and the Technical Specifications Date of Issuance:
September 4, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 156 RENEWED FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 137 RENEWED FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License License License No. NPF-68, page 4 License No. NPF-68, page 4 License No. NPF-81, page 3 License No. NPF-81, page 3 TSs TSs 5.2-2 5.2-2 5.2-3 5.2-3
-4 (1 ) Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Soecifications contained in Appendix A, as revised through Amendment No. 156; and the Environmental Protection Plan contained in Appendix B. both or which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.
(4) Deleted (5) Deleted (6) Deleted (7) Deleted (8) Deleted (9) Deleted (10) Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2.
Assessment of mutual aid fire fighting assets
- 3.
Designated staging areas for eqUipment and materials
- 4.
Command and control
- 5.
Training of response personnel (b) Operations to mitigate fuel damage considering the following:
- 1.
Protection and use of personnel assets
- 2.
Communications
- 3.
Minimizing fire spread
- 4.
Procedures for implementing integrated fire response strategy
- 5.
Identification of readily-available pre-staged eqUipment
- 6.
Training on integrated fire response strategy Renewed Operating License No. NPF-68 Amendment No. 156
-3 (2)
Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, pursuant to the Act and 10 CFR Part 50, to possess but not operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license; (3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Southern Nuclear, 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 calibration or associated with radioactive apparatus or components; (6)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.
C. This license shall be deemed to contain and Is sUbject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 137 and the EnVironmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be Renewed Operatina License NPF-81 Amendment No. 137
5.2 5.2.2 Organization 5.2 Organization Unit Staff (continued) 2, 3, or 4. With both units in MODES 5 or 6 or defueled, a total of three non-licensed operators are required for the two units.
- b.
At least one licensed RO shall be present in the control room when fuel is in the reactor.
NOTE-------------------------------
A single SRO licensed on both units may fulfill this function for both units.
In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed SRO shall be present in the control room.
- c.
The shift crew composition may be less than the minimum requirement of 10 CFR 50.54 (m)(2)(i) and 5.2.2.a and g 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.
- d.
NOTE------------------------
A single Health Physics Technician may fulfill this position for both units.
A Health Physics 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.
- e.
Deleted.
(continued)
Vogtle Units 1 and 2 5.2-2 Amendment No.1 56 (Unit 1)
Amendment No.1 37 (Unit 2)
5.2 Organization 5.2 Organization 5.2.2 Unit Staff (continued)
- f.
The Operations Manager or at least one Operations Superintendent shall hold an SRO license.
- g.
An individual shall be assigned who provides technical support in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall be available for duty when the plant is in modes 1-4. At other times, this individual is not required. In addition, this individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
This position may also be filled by the Shift Superintendent or the individual with an SRO license provided that person meets the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Vogtle Units 1 and 2 5.2-3 Amendment NO.156 (Unit 1)
Amendment NO.1 37 (Unit 2)
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 'h.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 182 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 AMENDMENT NO. 175 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 AMENDMENT NO. 262 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AMENDMENT NO. 206 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 AMENDMENT NO. 156 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-68 AMENDMENT NO. 137 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-81 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 DOCKET NOS. 50-321 AND 50-366 DOCKET NOS. 50-424 AND 50-425
1.0 INTRODUCTION
By application dated May 19, 2009, to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents and Management System (ADAMS), Accession No. ML091400381),
Southern Nuclear Operating Company, Inc. (SNC, the licensee), requested changes to the Technical Specifications (TSs) for the Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP), the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (HNP), and the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP). The proposed changes would delete the TS section titled "Unit Staff' as listed in Table 1 below.
The licensee stated that the application is consistent with the NRC's approved Revision 0 to Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26." Section 3.0 of the technical evaluation contains the differences between TSTF-511 and the TSs for the SNC nuclear plants listed in Table 1 below. 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 Table 1 Nuclear Power Plant TS Section Paragraph Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP)
TS 5.2.2 e
Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP)
TS 5.2.2 e
VOQtle Electric GeneratinQ Plant, Units 1 and 2 (VEGP)
TS 5.2.2 e
2.0 REGULATORY EVALUATION
The history of NRC regulations pertaining to prevention of worker impairment is summarized in the Federal Register notice containing the final rule that amended Title 10 of the Code of Federal Regulations (10 CFR) Part 26 (73 FR 16966, March 31, 2008). Part 26 of 10 CFR, Subpart I provides the regulatory requirements for managing worker fatigue at nuclear power plants.
The NRC's regulatory requirements related to the content of the TSs are contained in 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 (SRs); (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 facilities in a safe manner.
The NRC's 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," I\\lUREG-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 the STSs contains administrative controls. Paragraph d of Section 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 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 the 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.
- 3 This change was approved in Federal Register notice published on December 30,2008 (73 FR 79923).
2.1 Adoption of TSTF-511, Revision 0, by the SNC nuclear plants listed in Table 1 Proper adoption of TSTF-511 and implementation of 10 CFR Part 26, Subpart I by SNC will provide reasonable assurance that SNC will maintain limits on the working hours of personnel who perform safety-related functions. SI\\IC 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 SNC nuclear plants are currently located in the TS section and paragraph referenced in Table 1. When implemented, the regulatory requirements of 10 CFR 26, Subpart I will replace the plant-specific TS requirements found in Table 1 for the SNC nuclear plants.
The licensee proposed deleting paragraph e of TS 5.2.2, as referenced in Table 1, for FNP, HNP, and VEGP. 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 commitments 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).
3.1 SNC Nuclear plant-specific TS changes A.
Edwin I. Hatch Nuclear Plant. Unit Nos. 1 and 2 (HNP)
There are minor differences between HI\\IP TSs and TSTF-511. First, the equivalent HNP TS where work hour restrictions are located is TS 5.2.2, Paragraph e. This differs from TSTF-511, where work hour restrictions are located in STS 5.2.2, Paragraph d.
Second, while the text of HNP, TS 5.2.2, Paragraph e, is similar to the text of TSTF-511, STS 5.2.2, paragraph d, it is not identical. The most significant differences are as follows:
TSTF-511, STS 5.2.2, paragraph d states, "The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime." HI\\IP, TS 5.2.2, Paragraph e states, "Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the unit is operating.
However..." and incorporates the guidelines to be followed in TS 5.2.2 Paragraph e.
-4 TSTF-511, 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. HNP, TS 5.2.2, Paragraph e allows such deviations to be approved by the plant manager, or by higher levels of management.
TSTF-511, STS 5.2.2, Paragraph d requires the conduct of a periodic, independent review to ensure that excessive hours have not been assigned.
HI'JP, TS 5.2.2, Paragraph e does not require that this review be independent but rather requires that the review be conducted monthly by the plant manager or a designee.
These differences are insignificant as the intent of TSTF-511 is to delete TSs superseded by the revised regulations in 10 CFR Part 26, Subpart I.
B.
Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP)
There are minor differences between the FNP TSs and TSTF-511. First, the equivalent FI'JP TS where work hour restrictions are located is TS 5.2.2, Paragraph e. This differs from TSTF-511, where work hour restrictions are located in STS 5.2.2, Paragraph d.
Second, while the text of FNP, TS 5.2.2, Paragraph e, is similar to the text of TSTF-511, STS 5.2.2, Paragraph d, it is not identical. The most significant differences are as follows:
TSTF-511, STS 5.2.2, Paragraph d states, "The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime." FNP, TS 5.2.2, Paragraph e states, "Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the unit is operating.
However... n and incorporates the guidelines to be followed in TS 5.2.2 Paragraph e.
TSTF-511, 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. FNP, TS 5.2.2, Paragraph e states, "Any deviation from the above guidelines for the minimum shift compliment defined in Specifications 5.2.2.a and b and health physics technicians shall be reviewed and approved by the Plant Manager, his designee, or by higher levels of management. Any deviation from the above guidelines for key maintenance personnel shall be reviewed and approved by the Maintenance Manger or his designee."
TSTF-511, STS 5.2.2, Paragraph d requires the conduct of a periodic, independent review to ensure that excessive hours have not been assigned.
FNP, TS 5.2.2, Paragraph e does not have this requirement.
- 5 These differences are insignificant as the intent of TSTF-511 is to delete TSs superseded by the revised regulations in 10 CFR Part 26, Subpart I.
C.
Vogtle Electric Generating Plant. Units 1 and 2 (VEGP)
There are minor differences between the VEGP TSs and TSTF-511. First, the equivalent VEGP TS where work hour restrictions are located is TS 5.2.2, Paragraph e. This differs from TSTF-511, where work hour restrictions are located in STS 5.2.2, Paragraph d.
Second, while the text of VEGP, TS 5.2.2, Paragraph e, is similar to the text of TSTF-511, STS 5.2.2, Paragraph d, it is not identical. The most significant differences are as follows:
TSTF-511, STS 5.2.2, Paragraph d states, "The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime." VEGP, TS 5.2.2, Paragraph e states, "Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work an 8 or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the unit is operating. However..." and incorporates the guidelines to be followed in TS 5.2.2 Paragraph e.
TSTF-511, 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. VEGP, TS 5.2.2, Paragraph e allows such deviations to be approved by the department manager, or by higher levels of management.
TSTF-511, STS 5.2.2, Paragraph d requires the conduct of a periodic, independent review to ensure that excessive hours have not been assigned.
VEGP, TS 5.2.2, Paragraph e does not require that this review be independent but rather requires that the review be conducted monthly by the plant manager or a designee.
These differences are insignificant as the intent of TSTF-511 is to delete TSs superseded by the revised regulations in 10 CFR Part 26, Subpart I.
The NRC staff evaluated the licensee's proposed changes against the applicable regulatory requirements listed in Section 2. The NRC staff also compared the proposed changes to the change made to the STSs by TSTF-511. The NRC 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 changes. 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 FNP, HNP, and VEGP. 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 finds the proposed changes acceptable.
-6
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Alabama and Georgia State officials were notified of the proposed issuance of the respective amendments. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments changes 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.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: K. Buckhotz A. Lewin Date: September 4, 2009
M. Ajluni
-2 A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348,50-364,50-321, 50-366, 50-424, and 50-425
Enclosures:
- 1. Amendment No. 182 to I\\JPF-2
- 2. Amendment No. 175 to NPF-8
- 3. Amendment No. 262 to DPR-57
- 4. Amendment No. 206 to NPF-5
- 5. Amendment No. 156 to NPF-68
- 6. Amendment No. 137 to NPF-81
- 7. Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION:
Public RidsOgcRp Resource LPL2-1 RlF RidsNrrDorlLpl2-1 Resource RidsAcrsAcnwMailCTR Resource RidsNrrPMVogtle Resource RidsRgn2MailCenter Resource RidsNrrLASRohrer Resource RidsNrrltsb Resource RidsNrrPMFarley Resource RidsNrrPMNorthAnna Resource K. Buckhotz, NRR A. Lewin, NRR
. db ADAMSAccesslon No. ML091770664
- SE transmltte
>Y memo dated OFFICE NRRlLPL2-1/PM NRRlLPL2-1/PM NRRlLPL2-1/LA ITSB/BC OGC/NLO w/ comments NRRlLPL2-1/(A)BC NAME RMartin DWright SRohrer/ MOBrien REllliot*
BHarris UShoop DATE 09/03/09 09/02/09 07/14/09 07/15/09 06/15/09 07/16/09 09/04/09 OFFICIAL RECORD COpy