ML051880106
| ML051880106 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 07/05/2005 |
| From: | Lyon C NRC/NRR/DLPM/LPD3 |
| To: | Gaffney M Dominion Energy Kewaunee |
| Lyon C, NRR/DLPM, 415-2296 | |
| Shared Package | |
| ML051870040 | List: |
| References | |
| TAC MC7238 | |
| Download: ML051880106 (15) | |
Text
DOMINION ENERGY KEWAUNEE, INC.
DOCKET NO. 50-305 KEWAUNEE POWER STATION FACILITY OPERATING LICENSE AS AMENDED License No. DPR-43 The Atomic Energy Commission (the Commission) having found that:
A. The application for license filed by the applicant 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 and all required notifications to other agencies or bodies have been duty made; B. Construction of the Kewaunee Power Station (facility) has been substantially completed in conformity with Provisional Construction Permit No CPPR-50, as amended, and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii)that such activities will be conducted in compliance with the rules and regulations of the Commission; E. Dominion Energy Kewaunee, Inc. (the licensee) is technically and financially qualified to engage In the activities authorized by this operating license in accordance with the rules and regulations of the Commission; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this operating license will not be Inimical to the common defense and security or to the health and safety of the public; Amendment No. 185 1
H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License No. DPR-43, subject to the condition for protection of the environment set forth herein, Is In accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and
- 1. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be Inaccordance with the Commission's regulations in 10 CFR Part 30 and 70, including 10 CFR Section 30.33,70.23 and 70.31.
- 2. Facility Operating License No. DPR43 is hereby issued to Dominion Energy Kewaunee, Inc. to read as follows:
A. This license applies to the Kewaunee Power Station, a pressurized water nuclear reactor and associated equipment (the facility), owned by Dominion Energy Kewaunee, Inc. The facility is located in Kewaunee County, Wisconsin, and is described in the 'Final Safety Analysis Report' as supplemented and amended (Amendments 7 through 31) and the Environmental Report as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Dominion Energy Kewaunee, Inc.:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, 1Licensing of Production and Utilization Facilities," to possess, use and operate the facility at the designated location in Kewaunee County, Wisconsin, in accordance with the procedures and limitations set forth Inthis license; (2) 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; (3) 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 inamounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use Inamounts 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; (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.
Amendment No. 185 2
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter 1: (1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, (2) 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 (3) 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 In excess of 1772 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 185 , are hereby incorporated in the license. The licensee shall operate the facility in accordance'with the Technical Specifications.
(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) subject to the following provision:
The licensee 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.
(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10CFR 73.21, is entitled: 'Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004.
(5) Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until completion of an NRC environmental assessment supporting an increased limit.
Amendment No. 185 3
(6) Steam Generator Upper Lateral Supports The design of the steam generator upper lateral supports may be modified by reducing the number of snubbers from four (4) to one (1) per steam generator.
(7) Deleted (8) Operator Actions The auxiliary feedwater system local manual operator actions as described in the License Amendment Request submitted May 5, 2005, and supplemented on June 9, 2005, shall be eliminated no later than completion of Kewaunee refueling outage R-29.
D. The licensee shall comply with applicable effluent limitations and other limitations and monitoring requirements, if any, specified pursuant to Section 401 (d) of the Federal Water Pollution Control Act Amendments of 1972.
E. This license is effective as of the date of issuance, and shall expire at midnight on December 21, 2013.
FOR THE ATOMIC ENERGY COMMISSION Original Signed by A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing
Attachment:
Appendices A and B - Technical Specifications Date of Issuance: December 21, 1973 Amendment No. 185 4
APPENDIX A TECHNICAL SPECIFICATIONS FOR KEWAUNEE POWER STATION I
KEWAUNEE, WISCONSIN DOMINION ENERGY KEWAUNEE, INC. I DOCKET NUMBER 50-305
5.0 DESIGN FEATURES 5.1 SITE APPLICABILITY Applies to the location and extent of the reactor site.
OBJECTIVE To define those aspects of the site which affect the overall safety of the installation.
SPECIFICATION The Kewaunee Power Station is located on property owned by Dominion Energy l Kewaunee, Inc. at a site on the west shore of Lake Michigan, approximately 30 miles east-southeast of the city of Green Bay, Wisconsin.
The minimum distance from the center line of the reactor containment to the site exclusion radius as defined in 10 CFR 100.3 Is 1200 meters.
Amendment No. 185 TS 5.1-1
APPENDIX B ENVIRONMENTAL TECHNICAL SPECIFICA11ONS FOR KEWAUNEE POWER STATION I KEWAUNEE, WISCONSIN DOMINION ENERGY KEWAUNEE, INC. I DOCKET NUMBER 50-305
BASIS Kewaunee Power Station (KPS) design was not designed to Section Xl of the ASME Code; therefore, 100% compliance may not be practically achievable. However, the design process did consider access for in-service inspection, and made modifications within design limitations to provide maximum access. To the extent practical, Dominion Energy Kewaunee, Inc.
performs inspection of ASME Code Class 1, Class 2, Class 3, and Class MC components in accordance wit Section Xl of the ASME Code. If an inspection required by the Code is impractical, Dominion Energy Kewaunee, Inc. requests Commission approval for deviation from the requirement.
The basis for surveillance testing of the Reactor Coolant System pressure isolation valves identified in Table TS 3.1-2 Is contained within 'Order for Modification of License' dated April
- 20. 1981.
Technical Specification 4.2.b These Technical Specifications provide inspection and plugging requirements for KPS steam generator tubes. Fulfilling these requirements assures that KPS steam generator tubes are inspected and maintained in a manner consistent with current NRC regulations and guidelines including the General Design Criteria of 10 CFR Part 50, Appendix A.
Generic Design Criterion (GDC) 14, 'Reactor Coolant Pressure Boundary," and GDC 31,
'Fracture Prevention of Reactor Coolant Pressure Boundary,' require the reactor coolant pressure boundary to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. Also, GDC 15, OReactor Coolant System Design,"
requires the Reactor Coolant System and associated auxiliary, control, and protection systems to be designed with sufficient margin to ensure that design limits of the reactor coolant pressure boundary are not exceeded during normal operation, Including during anticipated operational transients. Furthermore, GDC 32, 'Inspection of Reactor Coolant System Pressure Boundary,' requires components that are part of the reactor coolant pressure boundary to be designed to permit periodic Inspection and testing of critical areas In order to assess their structural and leak tight integrity.
The NRC has developed guidance for steam generator tube inspection and maintenance including Regulatory Guides 1.83 and 1.121. Regulatory Guide 1.83, 'In-service Inspection of Pressurized Water Reactor Steam Generator Tubes," forms the basis for many of the requirements In this section and should be consulted before revising them. Regulatory Guide 1.121, 'Bases for Plugging Degraded PWR Steam Generator Tubes,' defines steam generator tube minimum wall thickness.
Amendment No. 185 TS B4.2-1
Technical Specification 4.2.b.1 If the steam generators are performing in an adequately similar manner, it is appropriate to limit the inspection to one steam generator per Inspection Interval on an alternating basis. This offers economic savings as well as reduction of radiation exposure and outage duration.
Technical Specification 4.2.b.2 Inspection of the steam generator tubes provides evaluation of their service condition.
Operational experience has shown that certain types of steam generators are susceptible to generic degradation mechanisms. It has also revealed site-specific steam generator tube degradation mechanisms. The Kewaunee Inspection program assesses both generic and site-specific tube degradations.
Kewaunee uses various eddy current (EC) testing methodologies to inspect steam generator tubes. EC technology has Improved considerably since Kewaunee began commercial operation in 1974, and Dominion Energy Kewaunee, Inc. Is committed to use advanced EC methods and technology, as appropriate, to assure accurate assessment of steam generator tube service condition.
Technical Specification 4.2.b.3 Kewaunee Power Station steam generator tube Inspections are typically conducted during refueling outages. Criteria used to select tubes for inspection are based, in part, on tube service condition deterrmined during previous inspections, and on operational experience from other plants with similar steam generators and water chemistry. Identification of degraded steam generator tubes results in expansion of the current inspection as well as increased frequency of subsequent Inspections. In this manner, steam generator tube surveillance remains consistent with tube service condition.
Several operational events or transients require consequent steam generator tube Inspections.
These Inspections must be performed after occurrence of excessive primary-to-secondary leakage or after transients that Impose large mechanical and thermal stresses on the tubes.
Amendment No. 185 TS B4.2-2
BASIS System Tests (TS 4.5.a)
The Safety Injection System and the Containment Vessel Internal Spray System are principal plant safety systems that are normally in standby during reactor operation. Complete systems tests cannot be performed when the reactor Is OPERATING because a safety Injection signal causes containment Isolation, and a Containment Vessel Internal Spray System test requires the system to be temporarily disabled. The method of assuring OPERABILITY of these systems is therefore to combine system tests to be performed during periodic shutdowns with more frequent component tests, which can be performed during reactor operation.
The systems tests demonstrate proper automatic operation of the Safety Injection and Containment Vessel Internal Spray Systems. A test signal is applied to initiate automatic action, resulting in verification that the components received the safety injection signal in the proper sequence. The test demonstrates the operation of the valves, pump circuit breakers, and automatic circuitry. (1)
The Internal Containment Spray (ICS) System is designed to provide containment cooling in the event of a loss-of-coolant accident or steam line break, thereby ensuring the containment pressure does not exceed its design value of 45 psig at 2680 F (100% R.H.). t2) To ensure adequate cooling is available, calculations were performed to determine the ICS flow rate necessary to provide post-accident cooling. These calculations showed that a flow rate of 1300 gpm provides the required cooling capabilities for one train. With the Kewaunee Power Station system design, 76 properly functioning spray nozzles per train will adequately provide the required flow rate of 1300 gpm per train.
Component Tests - Containment Fancoii Units (TS 4.5.a.3)
Testing of the containment fancoil unit emergency discharge and backdraft dampers is performed to assure the integrity of the duct work post-LOCA.
Component Tests - Pumps (TS 4.5.b.1)
During reactor operation, the instrumentation which is depended upon to initiate safety injection and containment spray is checked daily and the initiating logic circuits are tested monthly (in accordance with TS 4.1). In addition, the active components (pumps and valves) are to be tested quarterly to check the operation of the starting circuits and to verify that the pumps are In satisfactory running order. The quarterly test Interval is based on the judgment that more frequent testing would not significantly Increase the reliability (i.e., the probability that the component would operate when required), yet more frequent testing would result in increased wear over a long period of time.
{"USAR Section 6.2 (2)USAR Section 6.4 Amendment No. 185 TS B4.5-1
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 50-305 AMENDMENT TO INDEMNITY AGREEMENT NO. B-53 AMENDMENT NO.10 Effective July 5 ,2005, Indemnity Agreement No. B-53, between Wisconsin Public Service Corporation, Wisconsin Power and Light Company, Nuclear Management Company, LLC, and the Atomic Energy Commission, dated July 13, 1972, as amended, is hereby further amended by deleting the above named licensees from the indemnity agreement and replacing these licensees with the following named licensee 'Dominion Energy Kewaunee, Inc."
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Cathy Haney, Program Director Policy and Rulemaking Program Division of Regulatory Improvement Programs, NRR Accepted_ .2005 Accepted ,2005 By By Wisconsin Public Service Corporation Wisconsin Power and Light Company Accepted .2005 Accepted_ -
.2005 By By Nuclear Management Company, LLC Dominion Energy Kewaunee, Inc.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 50-305 AMENDMENT TO INDEMNITY AGREEMENT NO. B-53 AMENDMENT NO.10 Effective July 5 , 2005, Indemnity Agreement No. B-53, between Wisconsin Public Service Corporation, Wisconsin Power and Light Company, Nuclear Management Company, LLC, and the Atomic Energy Commission, dated July 13, 1972, as amended, is hereby further amended by deleting the above named licensees from the indemnity agreement and replacing these licensees with the following named licensee "Dominion Energy Kewaunee, Inc."
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Ceil~
Cathy Haney, Program Director Policy and Rulemaking Program Division of Regulatory Improvement Programs, NRR Accepted_ .2005- - -
Accepted ,2005 By By Wisconsin Public Service Corporation Wisconsin Power and Light Company Accepted .
.2005 Accepted_ ,2005 By By_
Nuclear Management Company, LLC Doi minion Energy Kewaunee, Inc.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 50-305 AMENDMENT TO INDEMNITY AGREEMENT NO. B-53 AMENDMENT NO.10 Effective July 5 , 2005, Indemnity Agreement No. B-53, between Wisconsin Public Service Corporation, Wisconsin Power and Light Company, Nuclear Management Company, LLC, and the Atomic Energy Commission, dated July 13, 1972, as amended, is hereby further amended by deleting the above named licensees from the indemnity agreement and replacing these licensees with the following named licensee 'Dominion Energy Kewaunee, Inc."
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Cathy Haney, Program Director Policy and Rulemaking Program Division of Regulatory Improvement Programs, NRR Accepted ,2005 Accepted .2005 By By Wisconsin Public Service Corporation Wisconsin Power and Light Company Accepted. ,2005 Accepted_ .2005 By By Nuclear Management Company, LLC Dominion Energy Kewaunee, Inc.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 50-305 AMENDMENT TO INDEMNITY AGREEMENT NO. B-53 AMENDMENT NO.10 Effective July 5 , 2005, Indemnity Agreement No. B-53, between Wisconsin Public Service Corporation, Wisconsin Power and Light Company, Nuclear Management Company, LLC, and the Atomic Energy Commission, dated July 13, 1972, as amended, is hereby further amended by deleting the above named licensees from the indemnity agreement and replacing these licensees with the following named licensee "Dominion Energy Kewaunee, Inc."
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Cathy H y, Pogram Director Policy and Rulemaking Program Division of Regulatory Improvement Programs, NRR Accepted_ .2005
,_ Accepted . ,.2005 By By Wisconsin Public Service Corporation Wisconsin Power and Light Company A evdanfta 9nn-1 9-1 Accepted ,2005 By By Nuclear Management Company, LLC Dominion Energy Kewaunee, Inc.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 50-305 AMENDMENT TO INDEMNITY AGREEMENT NO. B-53 AMENDMENT NO.10 Effective July 5 , 2005, Indemnity Agreement No. B-53, between Wisconsin Public Service Corporation, Wisconsin Power and Light Company, Nuclear Management Company, LLC, and the Atomic Energy Commission, dated July 13, 1972, as amended, is hereby further amended by deleting the above named licensees from the indemnity agreement and replacing these licensees with the following named licensee 'Dominion Energy Kewaunee, Inc."
FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Cathy Ha y, Program Director Policy and Rulemaking Program Division of Regulatory Improvement Programs, NRR Accepted ,2005 Ar-r-ntorl A)nnaJ By By Wisconsin Public Service Corporation Wisconsin Power and Light Company Accepted ,2005 Ar:tantatr . -- t-- 2005 By By Nuclear Management Company, LLC Dominion Energy Kewaunee, Inc.