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| | number = ML14157A082 | | | number = ML14157A082 |
| | issue date = 07/01/2014 | | | issue date = 07/01/2014 |
| | title = Wolf Creek - Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process (TAC MF3243) | | | title = Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Heflin A C | | | addressee name = Heflin A |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
| | docket = 05000482 | | | docket = 05000482 |
| | license number = NPF-042 | | | license number = NPF-042 |
| | contact person = Lyon C F | | | contact person = Lyon C |
| | case reference number = TAC MF3243 | | | case reference number = TAC MF3243 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Adam C. Heflin UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1, 2014 President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WOLF CREEK GENERATING STATION-ISSUANCE OF AMENDMENT RE: ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-522, REVISION 0, "REVISE VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS TO OPERATE FOR 10 HOURS PER MONTH" (TAC NO. MF3243) | | WOLF CREEK GENERATING STATION- ISSUANCE OF AMENDMENT RE: |
| | ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-522, REVISION 0, "REVISE VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS TO OPERATE FOR 10 HOURS PER MONTH" (TAC NO. |
| | MF3243) |
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| ==Dear Mr. Heflin:== | | ==Dear Mr. Heflin:== |
| The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 208 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 17, 2013. The amendment revises TS Surveillance Requirement (SR) 3. 7.1 0.1 and SR 3. 7 .13.1 to reduce the required run time for periodic operation of the control room pressurization system filter trains and emergency exhaust system filter trains, with heaters on, from 10 hours to 15 minutes. The amendment is consistent with plant-specific options provided in the NRC's model safety evaluation in Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month," as part of the consolidated line item improvement process. | | |
| A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-482 | | The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 208 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 17, 2013. |
| | The amendment revises TS Surveillance Requirement (SR) 3. 7.1 0.1 and SR 3. 7 .13.1 to reduce the required run time for periodic operation of the control room pressurization system filter trains and emergency exhaust system filter trains, with heaters on, from 10 hours to 15 minutes. The amendment is consistent with plant-specific options provided in the NRC's model safety evaluation in Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month," as part of the consolidated line item improvement process. |
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| | A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 |
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| ==Enclosures:== | | ==Enclosures:== |
| 1. Amendment No. 208 to NPF-42 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 License No. NPF-42 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Wolf Creek Generating Station (the facility) Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated December 17, 2013, 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, as amended, 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. Enclosure 1 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-42 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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance. | | : 1. Amendment No. 208 to NPF-42 |
| | : 2. Safety Evaluation cc w/encls: Distribution via Listserv |
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| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 License No. NPF-42 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment to the Wolf Creek Generating Station (the facility) |
| | Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated December 17, 2013, 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, as amended, 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. |
| | Enclosure 1 |
| | : 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-42 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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
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| | Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 1 , 2014 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 208 RENEWED FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Renewed Facility Operating License No. NPF-42 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. Renewed Facility Operating License REMOVE INSERT 4 4 Technical Specifications REMOVE 3.7-28 3.7-35 INSERT 3.7-28 3.7-35 4 (5) The Operating Corporation, 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; and (6) The Operating Corporation, 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. C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations 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 The Operating Corporation is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% 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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license. (4) Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER #5)* Deleted per Amendment No. 141. *The parenthetical notation following the title of many license conditions denotes the section of the supporting Safety Evaluation Report and/or its supplements wherein the license condition is discussed. Renewed License No. NPF-42 Amendment No. 208 ACTIONS .. (continued)_ CONDITION REQUIRED ACTION F. Two CREVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B. F.1 Enter LCO 3.0.3. SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SR 3.7.10.2 SR 3.7.10.3 SR 3.7.10.4 SURVEILLANCE Operate each CREVS train pressurization filter unit for 2: 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for 2: 15 continuous minutes. Perform required CREVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP). Verify each CREVS train actuates on an actual or simulated actuation signal. Perform required unfiltered air in leakage testing of the CRE and CBE boundaries in accordance with the Control Room Envelope Habitability Program. CREVS 3.7.10 COMPLETION TIME Immediately FREQUENCY 31 days In accordance with the VFTP 18 months In accordance with the Control Room Habitability Program Wolf Creek-Unit 1 3.7-28 Amendment No. 123, 134, 171, 177, 179,184,208 ACTIONS (continued) EES 3.7.13 CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time of Condition E not met. QB Two EES trains inoperable during movement of irradiated fuel assemblies in the fuel building for reasons other than Condition E. SURVEILLANCE REQUIREMENTS F.1 Suspend movement of Immediately irradiated fuel assemblies in the fuel building. SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each EES train 15 continuous minutes 31 days with the heaters operating. SR 3.7.13.2 Perform required EES filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.13.3 Verify each EES train actuates on an actual or 18 months simulated actuation signal. (continued) Wolf Creek
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| * Unit 1 3.7-35 Amendment No. 134, 171, 177, 484,208 UNITED STATES '1)-o11 NUCLEAR REGULATORY COMMISSION ! WASHINGTON, D.C. 20555-0001 <( 0 \ii '</. .,I) ..,.o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
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| ==1.0 INTRODUCTION==
| | Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 1 , 2014 |
| By letter dated December 17, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13358A238), Wolf Creek Nuclear Operating Corporation (the licensee), submitted a request to revise the Technical Specifications (TSs) for the Wolf Creek Generating Station (WCGS). Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month" (ADAMS Accession No. ML 100890316), dated March 30, 2010. The proposed change would revise TS Surveillance Requirements (SRs), which currently require operating each of the pressurization filter units of the Control Room Emergency Ventilation System (CREVS) trains and each Emergency Exhaust System (EES) train for at least 10 continuous hours, with the heaters operating at a frequency of 31 days. The SRs would be changed to require at least 15 continuous minutes of system operation, with the heaters operating at a frequency of 31 days. Specifically, the licensee proposes to change TS 3.7.1 0, "Control Room Emergency Ventilation System (CREVS)," and TS 3.7.13, "Emergency Exhaust System (EES)." In particular, SR 3. 7.1 0.1 and SR 3. 7 .13.1, which currently require operating the respective systems for at least 10 continuous hours with heaters operating at a frequency of 31 days, would be changed to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days. The licensee stated that the license amendment request is consistent with NRC-approved TSTF-522. The availability of this TS improvement was announced in the Federal Register on September 20, 2012 (77 FR 58421 ), as part of the consolidated line item improvement process. Enclosure 2
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 208 RENEWED FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Renewed Facility Operating License No. NPF-42 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. |
| | Renewed Facility Operating License REMOVE INSERT 4 4 Technical Specifications REMOVE INSERT 3.7-28 3.7-28 3.7-35 3.7-35 |
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| | 4 (5) The Operating Corporation, 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; and (6) The Operating Corporation, 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. |
| | C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations 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 The Operating Corporation is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% |
| | 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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license. |
| | (4) Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER #5)* |
| | Deleted per Amendment No. 141. |
| | *The parenthetical notation following the title of many license conditions denotes the section of the supporting Safety Evaluation Report and/or its supplements wherein the license condition is discussed. |
| | Renewed License No. NPF-42 Amendment No. 208 |
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| | CREVS 3.7.10 ACTIONS . (continued)_ |
| | CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B. |
| | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train pressurization filter unit 31 days for 2: 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for 2: 15 continuous minutes. |
| | SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or 18 months simulated actuation signal. |
| | SR 3.7.10.4 Perform required unfiltered air in leakage testing of the In accordance with CRE and CBE boundaries in accordance with the the Control Room Control Room Envelope Habitability Program. Habitability Program Wolf Creek- Unit 1 3.7-28 Amendment No. 123, 134, 171, 177, 179,184,208 |
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| ==2.0 REGULATORY EVALUATION==
| | EES 3.7.13 ACTIONS (continued) |
| One of the reasons air filtration and adsorption systems are required at nuclear power plants is to lower the concentration of airborne radioactive material that may be released from the site to the environment due to a design basis event. Lowering the concentration of airborne radioactive materials can mitigate doses to plant operators and members of the public in the event of a design basis event. A typical system consists of ventilation ductwork, fans, dampers, valves, instrumentation, prefilters or demisters, high-efficiency particulate air (HEPA) filters, heaters, and activated charcoal adsorbers. These systems are tested by operating the systems and monitoring the response of the overall system as well as individual components. Laboratory tests of charcoal adsorbers are also performed to ensure the charcoal adsorbs an acceptable amount of radioactive gasses. Current testing requirements for the air filtration and adsorption systems state that the systems should be operated for at least 10 continuous hours with heaters operating at a frequency of 31 days. These requirements are based on original NRC staff guidance for testing air filtration and adsorption systems that has been superseded. The current NRC staff guidance states that at least 15 continuous minutes of ventilation system operation with heaters operating every 31 days is acceptable for those plants that test ventilation system adsorption at a relative humidity of less than 95 percent. The licensee proposed revising its SRs, which currently require operating the ventilation systems for at least 10 continuous hours with the heaters operating at a frequency of 31 days, to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days. The regulatory requirements for the design and testing of these systems are contained in Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.67, "Accident source term," and Part 100, "Reactor Site Criteria," as well as 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criteria 19, 41, 42, 43, and 61. NRC Regulatory Guide (RG) 1.52, Revision 2, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" (ADAMS Accession No. ML0037 40139) was published in March 1978. RG 1.52, Revision 2 provided guidance and criteria acceptable to the NRC staff for licensees to implement the regulations in 10 CFR related to air filtration and adsorption systems. Regulatory Position 4.d of RG 1.52, Revision 2 states that Each ESF [engineered safety feature] atmosphere cleanup train should be operated at least 10 hours per month, with the heaters on (if so equipped), in order to reduce the buildup of moisture on the adsorbers and HEPA filters. The purpose of this position is to minimize the moisture content in the system and thereby enhance efficiency in the event the system is called upon to perform its design basis function. Testing requirements for air filtration and adsorption systems currently require operating the heaters in the respective ventilation and filtering systems for at least 10 continuous hours every 31 days. The current Standard TS (STS) Bases explain that operation of heaters for 10 hours would eliminate moisture on the charcoal adsorbers and HEPA filters. Following subsequent industry experience and testing, the NRC staff learned that 10 continuous hours of system operation would dry out the charcoal adsorber for a brief period of time but, following heater de-energization, the level of moisture accumulation in adsorbers would rapidly return to the pre-test level. The NRC staff found this information persuasive and subsequently issued NRC Generic Letter (GL) 99-02: "Laboratory Testing of Nuclear-Grade Activated Charcoal," dated June 3, 1999 (ADAMS Accession No. ML082350935 and errata sheet dated August 23, 1999, at ADAMS Accession No. ML03111 0094). GL 99-02 requested licensees to confirm that their charcoal testing protocols accurately reflected the adsorber gaseous activity capture capability. GL 99-02 also requested licensees to account for the effects of moisture accumulation in adsorbers. As a result, the NRC staff updated RG 1.52 in June 2001 to include the new information (ADAMS Accession No. ML01171 0176). RG 1.52, Revision 3, Regulatory Position 6.1 states, that Each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes each month, with the heaters on (if so equipped), to justify the operability of the system and all its components. One of the reasons for the previous 1 0-hour requirement for ventilation system operation with heaters operating was to minimize the effects of moisture on the adsorber's ability to capture gaseous activity. However, these effects are already accounted for in the Ventilation Filter Testing Program (VFTP). WCGS TS 5.5.11, "Ventilation Filter Testing Program (VFTP)," requires testing charcoal adsorbers in a manner to account for the effects of moisture on the adsorber's ability to capture gaseous activity. Therefore, the licensee proposed to remove the 1 0-hour requirement for ventilation system operation with heaters operating from SR 3. 7.1 0.1 and SR 3.7.13.1. The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. The regulations at 10 CFR 50.36 require that the TS include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. The NRC's guidance for the format and content of the STS applicable to WCGS can be found in NUREG-1431, "Standard Technical Specifications-Westinghouse Plants."
| | CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies Time of Condition E not in the fuel building. |
| | met. |
| | QB Two EES trains inoperable during movement of irradiated fuel assemblies in the fuel building for reasons other than Condition E. |
| | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each EES train for~ 15 continuous minutes 31 days with the heaters operating. |
| | SR 3.7.13.2 Perform required EES filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.13.3 Verify each EES train actuates on an actual or 18 months simulated actuation signal. |
| | (continued) |
| | Wolf Creek |
| | * Unit 1 3.7-35 Amendment No. ~23,132, 134, 171, 177, 484,208 |
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| ==3.0 TECHNICAL EVALUATION==
| | ~"'~REG(/{ UNITED STATES |
| 3.1 Proposed TS Changes Current SR 3.7.10.1 states: Operate each CREVS train pressurization filter unit for 10 continuous hours with the heaters operating and each CREVS train filtration filter unit for 15 minutes. Revised SR 3.7.10.1 would state: Operate each CREVS train pressurization filter unit for 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for 15 continuous minutes. Current SR 3. 7 .13.1 states: Operate each EES train 10 continuous hours with the heaters operating. Revised SR 3. 7 .13.1 would state: Operate each EES train 15 continuous minutes with the heaters operating. 3.2 NRC Staff Evaluation The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, guidance in the STS as modified by TSTF-522, and the regulatory requirements of 10 CFR 50.36. The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, which states that each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes with heaters on. The proposed change would require at least 15 minutes of CREVS and EES operation with the heaters operating. Therefore, the NRC staff concludes that the proposed changes are consistent with the guidance in RG 1.52, Revision 3. The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in the STS, as modified by TSTF-522. The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431, "Standard Technical Specifications-Westinghouse Plants" by TSTF-522. Therefore, the NRC staff concludes that the proposed changes are consistent with guidance in the STS, as modified by TSTF-522. The NRC staff compared the proposed changes to the existing SRs, as well as the regulatory requirements of 10 CFR 50.36. The existing SRs provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. The proposed changes reduce the amount of required system operational time from 10 hours to 15 minutes. The 1 0-hour operational requirement for heaters was based on using the SRs to eliminate moisture in the adsorbers and thus ensure that the adsorbers would capture gaseous activity. As discussed in Section 2.0 of this safety evaluation, the effects of moisture on the adsorber's ability to capture gaseous activity are now accounted for in the licensee's VFTP. Since the SRs are no longer relied upon to ensure that the effects of moisture on the adsorber's ability to capture gaseous activity are accounted for, the 1 0-hour heater operational requirement is unnecessary. The NRC staff found that reducing the required minimum system operation time to 15 minutes, consistent with RG 1. 52, Revision 3, in conjunction with the VFTP, is sufficient to justify operability of the system and all its components. The NRC staff concludes that the proposed SRs meet the regulatory requirements of 10 CFR 50.36 because they provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. Therefore, the NRC staff concludes that the proposed changes are acceptable. The regulation at 10 CFR 50.36 states: "A summary statement of the bases or reasons for such specifications ... shall also be included in the application, but shall not become part of the technical specifications." The licensee may make changes to the TS Bases without prior NRC staff review and approval in accordance with TS 5.5.14, "Technical Specifications (TS) Bases Control Program." Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff determined that these TS Bases changes are consistent with the proposed TS changes and provide the purpose for each requirement in the specification consistent with the Commission's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors," dated July 22, 1993 (58 FR 39132).
| | ~~"\,; '1)-o 11 NUCLEAR REGULATORY COMMISSION |
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| | 0 WASHINGTON, D.C. 20555-0001 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 |
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| ==4.0 STATE CONSULTATION== | | ==1.0 INTRODUCTION== |
| In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had o comments.
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| ==5.0 ENVIRONMENTAL CONSIDERATION==
| | By letter dated December 17, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A238), Wolf Creek Nuclear Operating Corporation (the licensee), submitted a request to revise the Technical Specifications (TSs) for the Wolf Creek Generating Station (WCGS). Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month" (ADAMS Accession No. ML100890316), dated March 30, 2010. |
| The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or changes to surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on March 18, 2014 (79 FR 15151). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. | | The proposed change would revise TS Surveillance Requirements (SRs), which currently require operating each of the pressurization filter units of the Control Room Emergency Ventilation System (CREVS) trains and each Emergency Exhaust System (EES) train for at least 10 continuous hours, with the heaters operating at a frequency of 31 days. The SRs would be changed to require at least 15 continuous minutes of system operation, with the heaters operating at a frequency of 31 days. |
| | Specifically, the licensee proposes to change TS 3.7.1 0, "Control Room Emergency Ventilation System (CREVS)," and TS 3.7.13, "Emergency Exhaust System (EES)." In particular, SR |
| | : 3. 7.1 0.1 and SR 3. 7 .13.1, which currently require operating the respective systems for at least 10 continuous hours with heaters operating at a frequency of 31 days, would be changed to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days. |
| | The licensee stated that the license amendment request is consistent with NRC-approved TSTF-522. The availability of this TS improvement was announced in the Federal Register on September 20, 2012 (77 FR 58421 ), as part of the consolidated line item improvement process. |
| | Enclosure 2 |
|
| |
|
| ==6.0 CONCLUSION== | | ==2.0 REGULATORY EVALUATION== |
| 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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: M. Hamm, NRR/DSS/STSB Date: July 1, 2014 A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Docket No. 50-482 | | |
| | One of the reasons air filtration and adsorption systems are required at nuclear power plants is to lower the concentration of airborne radioactive material that may be released from the site to the environment due to a design basis event. Lowering the concentration of airborne radioactive materials can mitigate doses to plant operators and members of the public in the event of a design basis event. A typical system consists of ventilation ductwork, fans, dampers, valves, instrumentation, prefilters or demisters, high-efficiency particulate air (HEPA) filters, heaters, and activated charcoal adsorbers. These systems are tested by operating the systems and monitoring the response of the overall system as well as individual components. |
| | Laboratory tests of charcoal adsorbers are also performed to ensure the charcoal adsorbs an acceptable amount of radioactive gasses. |
| | Current testing requirements for the air filtration and adsorption systems state that the systems should be operated for at least 10 continuous hours with heaters operating at a frequency of 31 days. These requirements are based on original NRC staff guidance for testing air filtration and adsorption systems that has been superseded. The current NRC staff guidance states that at least 15 continuous minutes of ventilation system operation with heaters operating every 31 days is acceptable for those plants that test ventilation system adsorption at a relative humidity of less than 95 percent. |
| | The licensee proposed revising its SRs, which currently require operating the ventilation systems for at least 10 continuous hours with the heaters operating at a frequency of 31 days, to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days. |
| | The regulatory requirements for the design and testing of these systems are contained in Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.67, "Accident source term," and Part 100, "Reactor Site Criteria," as well as 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criteria 19, 41, 42, 43, and 61. |
| | NRC Regulatory Guide (RG) 1.52, Revision 2, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" (ADAMS Accession No. ML003740139) was published in March 1978. RG 1.52, Revision 2 provided guidance and criteria acceptable to the NRC staff for licensees to implement the regulations in 10 CFR related to air filtration and adsorption systems. |
| | Regulatory Position 4.d of RG 1.52, Revision 2 states that Each ESF [engineered safety feature] atmosphere cleanup train should be operated at least 10 hours per month, with the heaters on (if so equipped), in order to reduce the buildup of moisture on the adsorbers and HEPA filters. |
| | The purpose of this position is to minimize the moisture content in the system and thereby enhance efficiency in the event the system is called upon to perform its design basis function. |
| | Testing requirements for air filtration and adsorption systems currently require operating the heaters in the respective ventilation and filtering systems for at least 10 continuous hours every |
| | |
| | 31 days. The current Standard TS (STS) Bases explain that operation of heaters for 10 hours would eliminate moisture on the charcoal adsorbers and HEPA filters. |
| | Following subsequent industry experience and testing, the NRC staff learned that 10 continuous hours of system operation would dry out the charcoal adsorber for a brief period of time but, following heater de-energization, the level of moisture accumulation in adsorbers would rapidly return to the pre-test level. The NRC staff found this information persuasive and subsequently issued NRC Generic Letter (GL) 99-02: "Laboratory Testing of Nuclear-Grade Activated Charcoal," dated June 3, 1999 (ADAMS Accession No. ML082350935 and errata sheet dated August 23, 1999, at ADAMS Accession No. ML031110094). GL 99-02 requested licensees to confirm that their charcoal testing protocols accurately reflected the adsorber gaseous activity capture capability. GL 99-02 also requested licensees to account for the effects of moisture accumulation in adsorbers. |
| | As a result, the NRC staff updated RG 1.52 in June 2001 to include the new information (ADAMS Accession No. ML011710176). RG 1.52, Revision 3, Regulatory Position 6.1 states, that Each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes each month, with the heaters on (if so equipped), to justify the operability of the system and all its components. |
| | One of the reasons for the previous 10-hour requirement for ventilation system operation with heaters operating was to minimize the effects of moisture on the adsorber's ability to capture gaseous activity. However, these effects are already accounted for in the Ventilation Filter Testing Program (VFTP). WCGS TS 5.5.11, "Ventilation Filter Testing Program (VFTP)," |
| | requires testing charcoal adsorbers in a manner to account for the effects of moisture on the adsorber's ability to capture gaseous activity. Therefore, the licensee proposed to remove the 10-hour requirement for ventilation system operation with heaters operating from SR 3. 7.1 0.1 and SR 3.7.13.1. |
| | The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. The regulations at 10 CFR 50.36 require that the TS include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. |
| | The NRC's guidance for the format and content of the STS applicable to WCGS can be found in NUREG-1431, "Standard Technical Specifications- Westinghouse Plants." |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | 3.1 Proposed TS Changes Current SR 3.7.10.1 states: |
| | Operate each CREVS train pressurization filter unit for ~ 10 continuous hours with the heaters operating and each CREVS train filtration filter unit for |
| | ~ 15 minutes. |
| | Revised SR 3.7.10.1 would state: |
| | Operate each CREVS train pressurization filter unit for ~ 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for |
| | ~ 15 continuous minutes. |
| | Current SR 3. 7 .13.1 states: |
| | Operate each EES train for~ 10 continuous hours with the heaters operating. |
| | Revised SR 3. 7 .13.1 would state: |
| | Operate each EES train for~ 15 continuous minutes with the heaters operating. |
| | 3.2 NRC Staff Evaluation The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, guidance in the STS as modified by TSTF-522, and the regulatory requirements of 10 CFR 50.36. |
| | The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, which states that each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes with heaters on. The proposed change would require at least 15 minutes of CREVS and EES operation with the heaters operating. Therefore, the NRC staff concludes that the proposed changes are consistent with the guidance in RG 1.52, Revision 3. |
| | The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in the STS, as modified by TSTF-522. The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431, "Standard Technical Specifications- Westinghouse Plants" by TSTF-522. Therefore, the NRC staff concludes that the proposed changes are consistent with guidance in the STS, as modified by TSTF-522. |
| | The NRC staff compared the proposed changes to the existing SRs, as well as the regulatory requirements of 10 CFR 50.36. The existing SRs provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. The proposed changes reduce the amount of required system operational time from 10 hours to |
| | |
| | 15 minutes. The 10-hour operational requirement for heaters was based on using the SRs to eliminate moisture in the adsorbers and thus ensure that the adsorbers would capture gaseous activity. As discussed in Section 2.0 of this safety evaluation, the effects of moisture on the adsorber's ability to capture gaseous activity are now accounted for in the licensee's VFTP. |
| | Since the SRs are no longer relied upon to ensure that the effects of moisture on the adsorber's ability to capture gaseous activity are accounted for, the 10-hour heater operational requirement is unnecessary. The NRC staff found that reducing the required minimum system operation time to 15 minutes, consistent with RG 1. 52, Revision 3, in conjunction with the VFTP, is sufficient to justify operability of the system and all its components. The NRC staff concludes that the proposed SRs meet the regulatory requirements of 10 CFR 50.36 because they provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. Therefore, the NRC staff concludes that the proposed changes are acceptable. |
| | The regulation at 10 CFR 50.36 states: "A summary statement of the bases or reasons for such specifications ... shall also be included in the application, but shall not become part of the technical specifications." The licensee may make changes to the TS Bases without prior NRC staff review and approval in accordance with TS 5.5.14, "Technical Specifications (TS) Bases Control Program." Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff determined that these TS Bases changes are consistent with the proposed TS changes and provide the purpose for each requirement in the specification consistent with the Commission's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors," |
| | dated July 22, 1993 (58 FR 39132). |
| | |
| | ==4.0 STATE CONSULTATION== |
| | |
| | In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had o comments. |
| | |
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| | |
| | The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or changes to surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on March 18, 2014 (79 FR 15151). |
| | Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. |
| | |
| | ==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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: M. Hamm, NRR/DSS/STSB Date: July 1, 2014 |
| | |
| | A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, IRA/ |
| | Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
| 1. Amendment No. 208 to NPF-42 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllpl4-1 Resource Sincerely, IRA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMWolfCreek Resource RidsRgn4MaiiCenter Resource MHamm, NRR/DSS/STSB ADAMS A ccess1on N o.: ML 14157A082 * . d d M 2 20 4 v1a memo ate ay 8, 1 OFFICE N RR/DORLILPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DSS/STSB/BC* NAME FLyon JBurkhardt REIIiott DATE 7/1/14 6/17/14 5/28/14 OFFICE OGC NRR/DORLILPL4-1 /BC NRR/DORLILPL4-1 /PM NAME JWachutka MMarkley Flyon DATE 6/25/14 7/1/14 7/1/14 OFFICIAL RECORD COPY | | : 1. Amendment No. 208 to NPF-42 |
| }} | | : 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrDssStsb Resource LPL4-1 r/f RidsNrrLAJBurkhardt Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrPMWolfCreek Resource RidsNrrDoriDpr Resource RidsRgn4MaiiCenter Resource RidsNrrDorllpl4-1 Resource MHamm, NRR/DSS/STSB ADAMS Access1on N o.: ML14157A082 *v1a |
| | . memo d ate d May 2 8, 20 14 OFFICE N RR/DORLILPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DSS/STSB/BC* |
| | NAME FLyon JBurkhardt REIIiott DATE 7/1/14 6/17/14 5/28/14 OFFICE OGC NRR/DORLILPL4-1 /BC NRR/DORLILPL4-1 /PM NAME JWachutka MMarkley Flyon DATE 6/25/14 7/1/14 7/1/14 OFFICIAL RECORD COPY}} |
Letter Sequence Approval |
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TAC:MF3243, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours PER Month (Approved, Closed) |
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MONTHYEARWO 13-0089, Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-12-17017 December 2013 Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process Project stage: Other ML14050A1342014-02-19019 February 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process Project stage: Approval 2014-02-19
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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 2024-09-06
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24212A0372024-08-0707 August 2024 Summary of July 23, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Wolf Creek Generating Station, Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22252A1512022-11-0404 November 2022 Issuance of Amendment No. 234 Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22199A2942022-08-16016 August 2022 Issuance of Amendment No. 233 Removal of Table of Contents from the Technical Specifications ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing ML22021B5982022-02-23023 February 2022 Issuance of Amendment No. 231 Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21210A2472021-09-0303 September 2021 Issuance of Amendment No. 230 Revision of Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML21238A3862021-09-0202 September 2021 Correction to Issuance of Amendment No. 229 Change to Owner Licensee Names ML21095A1922021-07-20020 July 2021 Issuance of Amendment No. 229 Change to Owner Licensee Names ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ML20276A1492020-12-0707 December 2020 Issuance of Amendment No. 226 Extension of Type a and Type C Leak Rate Test Frequencies ML19353C5002020-02-27027 February 2020 Issuance of Amendment No. 224 Revision to Technical Specification 3.3.5, - Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, - ML19182A3452019-08-19019 August 2019 Issuance of Amendment No 222 Revise Technical Specifications to Adopt TSTF Traveler TSTF-529, Clarify Use and Application Rules ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16179A2932016-08-0303 August 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14209A0232014-08-14014 August 2014 Issuance of Amendment No. 210, Modify License Condition Related to Approval of Revised Cyber Security Plan Implementation Milestone 8 Completion Date ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML13282A5342013-12-0606 December 2013 Issuance of Amendment No. 207, Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to Reflect Mass Input Transient Analysis ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ML12334A3122012-12-21021 December 2012 Issuance of Amendment No. 203, Revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, to Replace Surveillance Requirement 3.6.6.8 with an Event-Based Frequency ML12279A2502012-12-12012 December 2012 Issuance of Amendment No. 202, Revise Physical Security License Condition and Change to Scope of Milestone 6 for the Cyber Security Plan Implementation Schedule ML12300A3092012-12-11011 December 2012 Issuance of Amendment No. 201, Revise TS 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report for a Permanent Alternate Repair Criteria ML12318A1452012-12-0505 December 2012 Issuance of Amendment No. 200, Revision to Technical Specifications (TS) 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems ML12289A8962012-11-19019 November 2012 Issuance of Amendment No. 199, Request to Adopt Technical Specification Task Force Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies Using Consolidated Line Item Improvement Process ML1104804612011-04-19019 April 2011 Issuance of Amendment No. 196, Correction of Typographical Error in Technical Specification 5.7.2, Administrative Controls Related to High Radiation Area ML1108405902011-04-0606 April 2011 Issuance of Amendment No. 195, Revise Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criterion ML1105508462011-03-30030 March 2011 Issuance of Amendment No. 194, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 to Identify Functions and Modes for Reactor Trip P-4 Interlock Function ML1021703352010-11-0303 November 2010 Issuance of Amendment No. 190, Revise Technical Specification 3.6.3, Containment Isolation Valves, Limiting Condition for Operation ML1025604982010-09-30030 September 2010 Issuance of Amendment No. 189, Revise Updated Safety Analysis Report to Modify Fire Protection Program for Use of Fire-Resistive Electrical Cable ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ML1006300132010-03-0505 March 2010 Issuance of Amendment No. 187, Revise TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps (Emergency Circumstances) ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ML0917301912009-08-0707 August 2009 License Amendment, Issuance of Amendment No. 185, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0917002962009-07-30030 July 2009 Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months ML0909607342009-05-15015 May 2009 Issuance of Amendment No. 182, Revise Technical Specification 3.5.2, ECCS - Operating, in Accordance with TSTF-325A, ECCS Conditions and Required Actions with <100% Equivalent ECCS Flow ML0906103172009-03-31031 March 2009 Issuance of Amendment No. 181, Revise Licensing Basis, Modification of the Main Steam and Feedwater Isolation System Controls 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23256A2882023-09-20020 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-08 ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22252A1512022-11-0404 November 2022 Issuance of Amendment No. 234 Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ML22199A2942022-08-16016 August 2022 Issuance of Amendment No. 233 Removal of Table of Contents from the Technical Specifications ML22069A0562022-05-18018 May 2022 Issuance of Amendment No. 232 Regarding Revision to the Emergency Plan Related to On-Shift Staffing ML22021B5982022-02-23023 February 2022 Issuance of Amendment No. 231 Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21210A2472021-09-0303 September 2021 Issuance of Amendment No. 230 Revision of Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML21095A1922021-07-20020 July 2021 Issuance of Amendment No. 229 Change to Owner Licensee Names ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ML20276A1492020-12-0707 December 2020 Issuance of Amendment No. 226 Extension of Type a and Type C Leak Rate Test Frequencies ML20302A0802020-10-30030 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20111A3372020-04-27027 April 2020 Request from Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-666-1 ML19353C5002020-02-27027 February 2020 Issuance of Amendment No. 224 Revision to Technical Specification 3.3.5, - Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, - ML19291A0182019-11-12012 November 2019 Request for Relief I4R-07, Utilize Code Case N-513-4 - Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping of American Society of Mechanical Engineers Boiler and Pressure Code Section XI ML19182A3452019-08-19019 August 2019 Issuance of Amendment No 222 Revise Technical Specifications to Adopt TSTF Traveler TSTF-529, Clarify Use and Application Rules ML19100A1222019-05-31031 May 2019 Issuance of Amendment No. 221 License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML19052A5462019-04-0101 April 2019 Issuance of Amendment No. 220 Revision to the Emergency Plan ML18334A0132018-12-12012 December 2018 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-666-1 ML18283A0492018-10-18018 October 2018 Request for Relief I4R-6 from ASME Code Visual Examination Requirements for Reactor Vessel Head Penetration Nozzle Weld Specified by Code Case N-729-4 ML18040A6662018-03-12012 March 2018 Letter, Order, and Safety Evaluation Order Approving Indirect Transfer of Control of Renewed Facility Operating License No. NPF-42 ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17144A0092017-08-0202 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17202E9192017-08-0202 August 2017 Relief Request 14R-05 from Certain Pressure Test Requirements of the ASME Code for Reactor Pressure Vessel Leak-Off Lines for the Fourth 10 Year Inservice Inspection Interval ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16320A0322016-11-30030 November 2016 Request for Relief I4R-, Alternative Risk-Informed Methodology in Selecting Class 1 and 2 Piping Welds, for the Fourth 10-Year Inservice Inspection Interval ML16179A2932016-08-0303 August 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16179A4432016-08-0202 August 2016 Safety Evaluation, Request for Exemption from 10 CFR 50.46 and Appendix K to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15190A2022015-07-13013 July 2015 Relief Request 13R-12, Extension of the Third Inservice Inspection Program Interval to Perform Reactor Vessel Stud Hole Ligament Examinations ML15134A0022015-05-15015 May 2015 Relief Request Nos. 4PR-01 and 4PR-02 and Withdrawal of 4VR-02, Alternative to Requirements of ASME Code Case OMN-21 and OM Code ISTB-3510(b)(1) for Pumps, Fourth 10-Year Inservice Testing Program ML15040A0202015-02-12012 February 2015 Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code, Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML15023A2202015-01-28028 January 2015 Relief Request 13R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220 for the Third 10-Year Inservice Inspection Interval ML14321A8642014-12-10010 December 2014 Relief Requests 13R-08, Reactor Pressure Vessel (RPV) Interior Attachments and 13R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14209A0232014-08-14014 August 2014 Issuance of Amendment No. 210, Modify License Condition Related to Approval of Revised Cyber Security Plan Implementation Milestone 8 Completion Date ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML13282A5342013-12-0606 December 2013 Issuance of Amendment No. 207, Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, to Reflect Mass Input Transient Analysis ML13282A1472013-12-0202 December 2013 Issuance of Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves 2024-09-17
[Table view] Category:Technical Specifications
MONTHYEARML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 – Post Accident Monitoring (PAM) Report ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21061A0782021-04-23023 April 2021 Issuance of Amendment No. 228 Regarding Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ML21053A1172021-04-0808 April 2021 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18093A9142018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Chapter 16, Technical Requirements Manual (Relocated Technical Specifications) ML17166A4092017-08-28028 August 2017 Issuance of Amendment No. 218, Request to Adopt Emergency Action Level (EAL) Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML17024A2412017-03-24024 March 2017 Issuance of Amendment No. 217 Revision to the Cyber Security Plan Implementation Schedule ML16081A1942016-04-15015 April 2016 Issuance of Amendment No. 215, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 Consistent with TSTF-276-A, Revise DG Full Load Rejection Test WO 15-0051, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.142015-09-23023 September 2015 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10 and 3.8.1.14 ML15183A0522015-09-11011 September 2015 Issuance of Amendment No. 214, Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in Updated Safety Analysis Report ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) ML15169A2132015-07-28028 July 2015 Issuance of Amendment No. 212, Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation WO 15-0045, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2015-07-27027 July 2015 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML14156A2462014-08-0707 August 2014 Issuance of Amendment No. 209, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Replace Westinghouse Methodologies ML14157A0822014-07-0101 July 2014 Issuance of Amendment No. 208, Adopt TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using Consolidated Line Item Improvement Process ML14006A2182014-01-13013 January 2014 Correction to Amendment No. 206, Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test WO 13-0089, Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-12-17017 December 2013 Plant Specific Adoption of Technical Specification Task Force Traveler TSTF-522-A, Revision 0, Revised Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process ML13197A2102013-08-23023 August 2013 Issuance of Amendment No. 205, Revise Fire Protection License Condition and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis ML1107500362011-03-10010 March 2011 Changes to Technical Specification Bases - Revisions 45 Through 49 WO 10-0066, Correction of Typographical Error in Technical Specification 5.7.22010-10-21021 October 2010 Correction of Typographical Error in Technical Specification 5.7.2 ML1008205172010-07-23023 July 2010 Issuance of Amendment No. 188, Revise Technical Specifications for Use of Beacon Power Distribution Monitoring System ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-12010-04-13013 April 2010 Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 WO 10-0010, Updated Safety Analysis Report, Revision 232010-03-11011 March 2010 Updated Safety Analysis Report, Revision 23 ML1006401412010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps2010-03-0404 March 2010 Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML1006400442010-03-0303 March 2010 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.2008-08-14014 August 2008 Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).2008-07-10010 July 2008 Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr). ML0808400052008-04-0404 April 2008 Tech Pages for Amendment 178, Revision to Technical Specification 5.5.9 on the Steam Generator Program ML0803701212008-04-0303 April 2008 Tech Spec Pages for Amendment No. 177, Revise TS 3.3.2, ESFAS and TS 3.7.3, Main Feedwater Isolation Valves by Addition of Main Feedwater Regulating Valves and Associated Bypass Valves ML0729700282008-03-0303 March 2008 Tech Spec Pages for Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1 ML0720603282007-08-28028 August 2007 Tech Spec Pages for Amendment 174 Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program ML0705500202007-04-17017 April 2007 Tech Spec Pages for License Amendment No. 173 Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement2007-03-14014 March 2007 Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement ET 06-0053, Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-15015 December 2006 Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0631202612006-11-0707 November 2006 Tech Spec Pages for Amendment 171 Regarding Addition of Actuator Trains to Main Steam and Feedwater Isolation Valves Technical Specifications ML0630502562006-10-31031 October 2006 Technical Specifications, Revision to Reactor Coolant System Specific Activity ML0627201792006-09-28028 September 2006 Tech Spec Pages for Amendment 167 Regarding Extended Containment Isolation Valve Completion Times ML0627000632006-09-26026 September 2006 Tech Spec Pages for Amendment 166 Regarding Changes to the Reactor Coolant System (RCS) Leakage Detection Instrumentation Methodology ET 06-0026, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.2006-06-30030 June 2006 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program. ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-06-26026 June 2006 Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ML0612804712006-05-0808 May 2006 Tech Spec Pages for Amendment 164, Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0611702372006-04-26026 April 2006 Technical Specifications, Extended Diesel Generator Completion Times ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program2006-02-21021 February 2006 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program 2024-02-27
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 1, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION- ISSUANCE OF AMENDMENT RE:
ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) TRAVELER TSTF-522, REVISION 0, "REVISE VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS TO OPERATE FOR 10 HOURS PER MONTH" (TAC NO.
MF3243)
Dear Mr. Heflin:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 208 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 17, 2013.
The amendment revises TS Surveillance Requirement (SR) 3. 7.1 0.1 and SR 3. 7 .13.1 to reduce the required run time for periodic operation of the control room pressurization system filter trains and emergency exhaust system filter trains, with heaters on, from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 15 minutes. The amendment is consistent with plant-specific options provided in the NRC's model safety evaluation in Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month," as part of the consolidated line item improvement process.
A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 208 to NPF-42
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 License No. NPF-42
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Wolf Creek Generating Station (the facility)
Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated December 17, 2013, 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, as amended, 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.
Enclosure 1
- 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-42 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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~-c~
Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 1 , 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 208 RENEWED FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Renewed Facility Operating License No. NPF-42 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.
Renewed Facility Operating License REMOVE INSERT 4 4 Technical Specifications REMOVE INSERT 3.7-28 3.7-28 3.7-35 3.7-35
4 (5) The Operating Corporation, 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; and (6) The Operating Corporation, 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.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations 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 The Operating Corporation is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100%
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. 208, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4) Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER #5)*
Deleted per Amendment No. 141.
- The parenthetical notation following the title of many license conditions denotes the section of the supporting Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-42 Amendment No. 208
CREVS 3.7.10 ACTIONS . (continued)_
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train pressurization filter unit 31 days for 2: 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for 2: 15 continuous minutes.
SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or 18 months simulated actuation signal.
SR 3.7.10.4 Perform required unfiltered air in leakage testing of the In accordance with CRE and CBE boundaries in accordance with the the Control Room Control Room Envelope Habitability Program. Habitability Program Wolf Creek- Unit 1 3.7-28 Amendment No. 123, 134, 171, 177, 179,184,208
EES 3.7.13 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies Time of Condition E not in the fuel building.
met.
QB Two EES trains inoperable during movement of irradiated fuel assemblies in the fuel building for reasons other than Condition E.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each EES train for~ 15 continuous minutes 31 days with the heaters operating.
SR 3.7.13.2 Perform required EES filter testing in accordance with In accordance with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.13.3 Verify each EES train actuates on an actual or 18 months simulated actuation signal.
(continued)
Wolf Creek
- Unit 1 3.7-35 Amendment No. ~23,132, 134, 171, 177, 484,208
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By letter dated December 17, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A238), Wolf Creek Nuclear Operating Corporation (the licensee), submitted a request to revise the Technical Specifications (TSs) for the Wolf Creek Generating Station (WCGS). Specifically, the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month" (ADAMS Accession No. ML100890316), dated March 30, 2010.
The proposed change would revise TS Surveillance Requirements (SRs), which currently require operating each of the pressurization filter units of the Control Room Emergency Ventilation System (CREVS) trains and each Emergency Exhaust System (EES) train for at least 10 continuous hours, with the heaters operating at a frequency of 31 days. The SRs would be changed to require at least 15 continuous minutes of system operation, with the heaters operating at a frequency of 31 days.
Specifically, the licensee proposes to change TS 3.7.1 0, "Control Room Emergency Ventilation System (CREVS)," and TS 3.7.13, "Emergency Exhaust System (EES)." In particular, SR
- 3. 7.1 0.1 and SR 3. 7 .13.1, which currently require operating the respective systems for at least 10 continuous hours with heaters operating at a frequency of 31 days, would be changed to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days.
The licensee stated that the license amendment request is consistent with NRC-approved TSTF-522. The availability of this TS improvement was announced in the Federal Register on September 20, 2012 (77 FR 58421 ), as part of the consolidated line item improvement process.
Enclosure 2
2.0 REGULATORY EVALUATION
One of the reasons air filtration and adsorption systems are required at nuclear power plants is to lower the concentration of airborne radioactive material that may be released from the site to the environment due to a design basis event. Lowering the concentration of airborne radioactive materials can mitigate doses to plant operators and members of the public in the event of a design basis event. A typical system consists of ventilation ductwork, fans, dampers, valves, instrumentation, prefilters or demisters, high-efficiency particulate air (HEPA) filters, heaters, and activated charcoal adsorbers. These systems are tested by operating the systems and monitoring the response of the overall system as well as individual components.
Laboratory tests of charcoal adsorbers are also performed to ensure the charcoal adsorbs an acceptable amount of radioactive gasses.
Current testing requirements for the air filtration and adsorption systems state that the systems should be operated for at least 10 continuous hours with heaters operating at a frequency of 31 days. These requirements are based on original NRC staff guidance for testing air filtration and adsorption systems that has been superseded. The current NRC staff guidance states that at least 15 continuous minutes of ventilation system operation with heaters operating every 31 days is acceptable for those plants that test ventilation system adsorption at a relative humidity of less than 95 percent.
The licensee proposed revising its SRs, which currently require operating the ventilation systems for at least 10 continuous hours with the heaters operating at a frequency of 31 days, to require at least 15 continuous minutes of ventilation system operation at a frequency of 31 days.
The regulatory requirements for the design and testing of these systems are contained in Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.67, "Accident source term," and Part 100, "Reactor Site Criteria," as well as 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criteria 19, 41, 42, 43, and 61.
NRC Regulatory Guide (RG) 1.52, Revision 2, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" (ADAMS Accession No. ML003740139) was published in March 1978. RG 1.52, Revision 2 provided guidance and criteria acceptable to the NRC staff for licensees to implement the regulations in 10 CFR related to air filtration and adsorption systems.
Regulatory Position 4.d of RG 1.52, Revision 2 states that Each ESF [engineered safety feature] atmosphere cleanup train should be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per month, with the heaters on (if so equipped), in order to reduce the buildup of moisture on the adsorbers and HEPA filters.
The purpose of this position is to minimize the moisture content in the system and thereby enhance efficiency in the event the system is called upon to perform its design basis function.
Testing requirements for air filtration and adsorption systems currently require operating the heaters in the respective ventilation and filtering systems for at least 10 continuous hours every
31 days. The current Standard TS (STS) Bases explain that operation of heaters for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> would eliminate moisture on the charcoal adsorbers and HEPA filters.
Following subsequent industry experience and testing, the NRC staff learned that 10 continuous hours of system operation would dry out the charcoal adsorber for a brief period of time but, following heater de-energization, the level of moisture accumulation in adsorbers would rapidly return to the pre-test level. The NRC staff found this information persuasive and subsequently issued NRC Generic Letter (GL) 99-02: "Laboratory Testing of Nuclear-Grade Activated Charcoal," dated June 3, 1999 (ADAMS Accession No. ML082350935 and errata sheet dated August 23, 1999, at ADAMS Accession No. ML031110094). GL 99-02 requested licensees to confirm that their charcoal testing protocols accurately reflected the adsorber gaseous activity capture capability. GL 99-02 also requested licensees to account for the effects of moisture accumulation in adsorbers.
As a result, the NRC staff updated RG 1.52 in June 2001 to include the new information (ADAMS Accession No. ML011710176). RG 1.52, Revision 3, Regulatory Position 6.1 states, that Each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes each month, with the heaters on (if so equipped), to justify the operability of the system and all its components.
One of the reasons for the previous 10-hour requirement for ventilation system operation with heaters operating was to minimize the effects of moisture on the adsorber's ability to capture gaseous activity. However, these effects are already accounted for in the Ventilation Filter Testing Program (VFTP). WCGS TS 5.5.11, "Ventilation Filter Testing Program (VFTP),"
requires testing charcoal adsorbers in a manner to account for the effects of moisture on the adsorber's ability to capture gaseous activity. Therefore, the licensee proposed to remove the 10-hour requirement for ventilation system operation with heaters operating from SR 3. 7.1 0.1 and SR 3.7.13.1.
The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. The regulations at 10 CFR 50.36 require that the TS include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
The NRC's guidance for the format and content of the STS applicable to WCGS can be found in NUREG-1431, "Standard Technical Specifications- Westinghouse Plants."
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes Current SR 3.7.10.1 states:
Operate each CREVS train pressurization filter unit for ~ 10 continuous hours with the heaters operating and each CREVS train filtration filter unit for
~ 15 minutes.
Revised SR 3.7.10.1 would state:
Operate each CREVS train pressurization filter unit for ~ 15 continuous minutes with the heaters operating and each CREVS train filtration filter unit for
~ 15 continuous minutes.
Current SR 3. 7 .13.1 states:
Operate each EES train for~ 10 continuous hours with the heaters operating.
Revised SR 3. 7 .13.1 would state:
Operate each EES train for~ 15 continuous minutes with the heaters operating.
3.2 NRC Staff Evaluation The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, guidance in the STS as modified by TSTF-522, and the regulatory requirements of 10 CFR 50.36.
The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in RG 1.52, Revision 3, which states that each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes with heaters on. The proposed change would require at least 15 minutes of CREVS and EES operation with the heaters operating. Therefore, the NRC staff concludes that the proposed changes are consistent with the guidance in RG 1.52, Revision 3.
The NRC staff evaluated the licensee's proposed changes against the applicable regulatory guidance in the STS, as modified by TSTF-522. The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431, "Standard Technical Specifications- Westinghouse Plants" by TSTF-522. Therefore, the NRC staff concludes that the proposed changes are consistent with guidance in the STS, as modified by TSTF-522.
The NRC staff compared the proposed changes to the existing SRs, as well as the regulatory requirements of 10 CFR 50.36. The existing SRs provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. The proposed changes reduce the amount of required system operational time from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to
15 minutes. The 10-hour operational requirement for heaters was based on using the SRs to eliminate moisture in the adsorbers and thus ensure that the adsorbers would capture gaseous activity. As discussed in Section 2.0 of this safety evaluation, the effects of moisture on the adsorber's ability to capture gaseous activity are now accounted for in the licensee's VFTP.
Since the SRs are no longer relied upon to ensure that the effects of moisture on the adsorber's ability to capture gaseous activity are accounted for, the 10-hour heater operational requirement is unnecessary. The NRC staff found that reducing the required minimum system operation time to 15 minutes, consistent with RG 1. 52, Revision 3, in conjunction with the VFTP, is sufficient to justify operability of the system and all its components. The NRC staff concludes that the proposed SRs meet the regulatory requirements of 10 CFR 50.36 because they provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. Therefore, the NRC staff concludes that the proposed changes are acceptable.
The regulation at 10 CFR 50.36 states: "A summary statement of the bases or reasons for such specifications ... shall also be included in the application, but shall not become part of the technical specifications." The licensee may make changes to the TS Bases without prior NRC staff review and approval in accordance with TS 5.5.14, "Technical Specifications (TS) Bases Control Program." Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff determined that these TS Bases changes are consistent with the proposed TS changes and provide the purpose for each requirement in the specification consistent with the Commission's "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors,"
dated July 22, 1993 (58 FR 39132).
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had o comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or changes to surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on March 18, 2014 (79 FR 15151).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: M. Hamm, NRR/DSS/STSB Date: July 1, 2014
A. Heflin A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRA/
Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 208 to NPF-42
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDssStsb Resource LPL4-1 r/f RidsNrrLAJBurkhardt Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrPMWolfCreek Resource RidsNrrDoriDpr Resource RidsRgn4MaiiCenter Resource RidsNrrDorllpl4-1 Resource MHamm, NRR/DSS/STSB ADAMS Access1on N o.: ML14157A082 *v1a
. memo d ate d May 2 8, 20 14 OFFICE N RR/DORLILPL4-1 /PM NRR/DORLILPL4-1/LA NRR/DSS/STSB/BC*
NAME FLyon JBurkhardt REIIiott DATE 7/1/14 6/17/14 5/28/14 OFFICE OGC NRR/DORLILPL4-1 /BC NRR/DORLILPL4-1 /PM NAME JWachutka MMarkley Flyon DATE 6/25/14 7/1/14 7/1/14 OFFICIAL RECORD COPY