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| | author name = Hon A | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Shea J W | | | addressee name = Shea J |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000390 | | | docket = 05000390 |
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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801 April 7, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 7, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATTS BAR NUCLEAR PLANT, UNIT 1 -ISSUANCE OF AMENDMENT TO MODIFY ADMINSTRATIVE CONTROLS SECTIONS OF TECHNICAL SPECIFICATION BY ADOPTING TSTF-348 (TAC NO. MF1461) | | WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT TO MODIFY ADMINSTRATIVE CONTROLS SECTIONS OF TECHNICAL SPECIFICATION BY ADOPTING TSTF-348 (TAC NO. MF1461) |
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| ==Dear Mr. Shea:== | | ==Dear Mr. Shea:== |
| The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 96 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1. This amendment consists of changes to the license and the Technical Specifications (TSs) in response to your application dated April 12, 2013. The proposed amendment will modify Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report." The proposed change is consistent with NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States." In addition, the proposed amendment will modify TS 5.9.8, "PAMS [Post Accident Monitoring System] Report." These editorial changes update the TSs to remove an obsolete Thermoluminescent Dosimeter requirement, and correct enumeration as a result of a previous license amendment. | | |
| J.Shea A copy of the related Safety Evaluation is also enclosed. | | The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 96 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1. This amendment consists of changes to the license and the Technical Specifications (TSs) in response to your application dated April 12, 2013. |
| The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-390 | | The proposed amendment will modify Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report." The proposed change is consistent with NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States." |
| | In addition, the proposed amendment will modify TS 5.9.8, "PAMS [Post Accident Monitoring System] Report." These editorial changes update the TSs to remove an obsolete Thermoluminescent Dosimeter requirement, and correct enumeration as a result of a previous license amendment. |
| | |
| | J.Shea A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. |
| | Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 96 to NPF-90 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-90 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by the Tennessee Valley Authority (the licensee) dated April 12, 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 Title 10 of the Code of Federal Regulations (1 0 CFR) Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 1 0 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 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. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 30 days from the date of its issuance. | | : 1. Amendment No. 96 to NPF-90 |
| | : 2. Safety Evaluation cc w/encls: Distribution via Listserv |
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| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-90 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by the Tennessee Valley Authority (the licensee) dated April 12, 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 Title 10 of the Code of Federal Regulations (1 0 CFR) |
| | Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 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. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 30 days from the date of its issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION s .Ouic~~ |
| | lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
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| Changes to the Operating License and the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION s | | Changes to the Operating License and the Technical Specifications Date of Issuance: April 7, 2014 |
| lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance:
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| April 7, 2014 ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 3 of Operating License NPF-90 with the attached Page 3. Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain a marginal line indicating the area of change. REMOVE 5.0-27 5.0-32 INSERT 5.0-27 5.0-32 (4) TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and (5) TVA, pursuant to the Act and 1 0 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 0 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 TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15) Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
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| (4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20) During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented.
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| TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
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| Facility License No. NPF-90 Amendment No. 96 Reporting Requirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements 5.9.1 5.9.2 Watts Bar-Unit 1 The following reports shall be submitted in accordance with 10 CFR 50.4. DELETED Annual Radiological Environmental Operating Report --------------------------------------------------------NOTE----------------------------------------------------
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| A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. (continued) 5.0-27 Amendment 57, 96 Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.7 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days. Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4, or existing Regulatory Guide 1.108 reporting requirement.
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| 5.9.8 PAMS Report 5.9.9 When a Report is required by Condition B or F of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplan ned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status. Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification
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| : 5. 7 .2.12, Steam Generator (SG) Program. The report shall include: a. The scope of inspections performed on each SG, b. Active degradation mechanisms found, c. Nondestructive examination techniques utilized for each degradation mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, e. Number of tubes plugged during the inspection outage for each active degradation mechanism, f. Total number and percentage of tubes plugged to date, g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and h. The effective plugging percentage for all plugging in each SG. Watts Bar-Unit 1 5.0-32 Amendment 27, 38, 65, 96 I UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE NO. NPF-90
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| ==1.0 INTRODUCTION==
| | ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 3 of Operating License NPF-90 with the attached Page 3. |
| | Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain a marginal line indicating the area of change. |
| | REMOVE INSERT 5.0-27 5.0-27 5.0-32 5.0-32 |
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| TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390 By letter dated April 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13106A146), Tennessee Valley Authority (the licensee) proposed changes to the Technical Specifications (TSs) for Watts Bar Unit 1 (WBN1). The proposed editorial changes revise TS 5.9.2, "Annual Radiological Environmental Operating Report," and TS 5.9.8, "PAMS [Post Accident Monitoring System] Report." The licensee stated that the proposed change toTS 5.9.2 is consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States" (ADAMS No. ML040630068).
| | (4) TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and (5) TVA, 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. |
| TSTF-348 removes an obsolete Thermoluminescent Dosimeter (TLD) TS requirement.
| | C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below. |
| The change to TS 5.9.8 is necessary to correct enumeration as a result of a previous license amendment.
| | (1) Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal. |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15) |
| | Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational. |
| | (4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20) |
| | During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented. |
| | Facility License No. NPF-90 Amendment No. 96 |
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| ==2.0 REGULATORY EVALUATION==
| | Reporting Requirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. |
| | 5.9.1 DELETED 5.9.2 Annual Radiological Environmental Operating Report |
| | --------------------------------------------------------NOTE---------------------------------------------------- |
| | A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. |
| | The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. |
| | The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. |
| | (continued) |
| | Watts Bar-Unit 1 5.0-27 Amendment 57, 96 |
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| The NRCs regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (1 0 CFR), Part 50, Section 50.36, "Technical specifications." The TS requirements in 10 CFR 50.36 include the following categories:
| | Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.7 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days. Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4, or existing Regulatory Guide 1.108 reporting requirement. |
| (1) safety limits, limiting safety systems settings and control settings, (2) Limiting Conditions for Operation (LCO), (3) Surveillance Requirements (SRs), (4) design features, and (5) administrative controls.
| | 5.9.8 PAMS Report When a Report is required by Condition B or F of LCO 3.3.3, "Post Accident Monitoring (PAM) |
| Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. 3.0 TECHNICAL EVALUATION 3.1 TS 5.9.2, "Annual Radiological Environmental Operating Report" The licensee proposed to delete the following sentence, currently in the last paragraph of Specification 5.9.2: Enclosure "The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result." In Press Release No. 98-08, dated January 13, 1998 (ADAMS No. ML003708685), the NRC announced that it had ended its contract with 34 states to perform radiation monitoring around certain facilities as of the end of 1997. As a result, TSTF-348 revised STS 5.6.2, "Annual Radiological Environmental Operating Report," to delete reference to collocated dosimeters to reflect cancellation of the NRC environmental monitoring program with States. The licensee proposed to adopt this TSTF change without deviation in corresponding WBN1 TS 5.9.2. The proposed change removes an obsolete reporting requirement and is, therefore, corrective or editorial in nature. The staff finds this change acceptable.
| | Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplan ned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status. |
| 3.2 TS 5.9.8, "PAMS Report" The first sentence of WBN1 TS 5.9.8 currently states: "When a Report is required by Condition B or G of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days." The proposed change states: "When a Report is required by Condition B or F of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days." The proposed change corrects a cross-reference error introduced with the implementation of WBN1 License Amendment 72, issued December 23, 2008 (ADAMS No. ML082970645).
| | 5.9.9 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5. 7 .2.12, Steam Generator (SG) Program. The report shall include: |
| Deletion of TS 3.3.3, Condition D resulted in Conditions E, F, and G being changed to Conditions D, E, and F, respectively.
| | : a. The scope of inspections performed on each SG, |
| However, the impact of the December 23, 2008, change on TS 5.9.8 reference was not previously identified.
| | : b. Active degradation mechanisms found, |
| The NRC staff finds that the re-lettering change is editorial and clarifying in nature and is consistent with the current intent of the TS requirement.
| | : c. Nondestructive examination techniques utilized for each degradation mechanism, |
| Therefore, the NRC staff finds this corrective change acceptable.
| | : d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, |
| | : e. Number of tubes plugged during the inspection outage for each active degradation mechanism, |
| | : f. Total number and percentage of tubes plugged to date, |
| | : g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and |
| | : h. The effective plugging percentage for all plugging in each SG. |
| | Watts Bar-Unit 1 5.0-32 Amendment 27, 38, 65, 96 I |
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| ==4.0 STATE CONSULTATION==
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390 |
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| In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendments.
| | ==1.0 INTRODUCTION== |
| The State official had no comments.
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| ===5.0 ENVIRONMENTAL===
| | By letter dated April 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13106A146), Tennessee Valley Authority (the licensee) proposed changes to the Technical Specifications (TSs) for Watts Bar Unit 1 (WBN1). The proposed editorial changes revise TS 5.9.2, "Annual Radiological Environmental Operating Report," and TS 5.9.8, "PAMS [Post Accident Monitoring System] Report." |
| | The licensee stated that the proposed change toTS 5.9.2 is consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States" (ADAMS No. ML040630068). TSTF-348 removes an obsolete Thermoluminescent Dosimeter (TLD) TS requirement. The change to TS 5.9.8 is necessary to correct enumeration as a result of a previous license amendment. |
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| CONSIDERATION The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
| | ==2.0 REGULATORY EVALUATION== |
| Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii) and (v). 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.
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| ==6.0 CONCLUSION==
| | The NRCs regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (1 0 CFR), Part 50, Section 50.36, "Technical specifications." The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and control settings, (2) Limiting Conditions for Operation (LCO), |
| | (3) Surveillance Requirements (SRs), (4) design features, and (5) administrative controls. |
| | Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. |
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| The Commission has concluded, based on the considerations discussed above, there is reasonable assurance that: (1) the health and safety of the public will not be endangered by operation in the proposed manner, (2) that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Contributors: | | ==3.0 TECHNICAL EVALUATION== |
| K. Hemphill Date: April 7, 2014 J. Shea A copy of the related Safety Evaluation is also enclosed. | | |
| The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-390 | | 3.1 TS 5.9.2, "Annual Radiological Environmental Operating Report" The licensee proposed to delete the following sentence, currently in the last paragraph of Specification 5.9.2: |
| | Enclosure |
| | |
| | "The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result." |
| | In Press Release No. 98-08, dated January 13, 1998 (ADAMS No. ML003708685), the NRC announced that it had ended its contract with 34 states to perform radiation monitoring around certain facilities as of the end of 1997. As a result, TSTF-348 revised STS 5.6.2, "Annual Radiological Environmental Operating Report," to delete reference to collocated dosimeters to reflect cancellation of the NRC environmental monitoring program with States. The licensee proposed to adopt this TSTF change without deviation in corresponding WBN1 TS 5.9.2. The proposed change removes an obsolete reporting requirement and is, therefore, corrective or editorial in nature. The staff finds this change acceptable. |
| | 3.2 TS 5.9.8, "PAMS Report" The first sentence of WBN1 TS 5.9.8 currently states: |
| | "When a Report is required by Condition B or G of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days." |
| | The proposed change states: |
| | "When a Report is required by Condition B or F of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days." |
| | The proposed change corrects a cross-reference error introduced with the implementation of WBN1 License Amendment 72, issued December 23, 2008 (ADAMS No. ML082970645). |
| | Deletion of TS 3.3.3, Condition D resulted in Conditions E, F, and G being changed to Conditions D, E, and F, respectively. However, the impact of the December 23, 2008, change on TS 5.9.8 reference was not previously identified. The NRC staff finds that the re-lettering change is editorial and clarifying in nature and is consistent with the current intent of the TS requirement. Therefore, the NRC staff finds this corrective change acceptable. |
| | |
| | ==4.0 STATE CONSULTATION== |
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| | In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendments. The State official had no comments. |
| | |
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| | The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii) and (v). 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== |
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| | The Commission has concluded, based on the considerations discussed above, there is reasonable assurance that: (1) the health and safety of the public will not be endangered by operation in the proposed manner, (2) that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| | Contributors: K. Hemphill Date: April 7, 2014 |
| | |
| | J. Shea A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. |
| | Sincerely, IRA/ |
| | Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 |
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| ==Enclosures:== | | ==Enclosures:== |
| | | : 1. Amendment No. 96 to NPF-90 |
| Sincerely, IRA/ Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | : 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: |
| : 1. Amendment No. 96 to NPF-90 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: | | PUBLIC LPL2-2 r/f RidsNrrDssStsb RidsNrrDoriDpr RidsNrrDorllpl2-2 RidsNrrPMWattsBar1 RidsNrrLABCiayton RidsRgn2MaiiCenter RidsAcrsAcnw_MaiiCTR KHemphill, NRR RidsNrrPMWattsBar2 ADAMS Access1on No.: ML14071A339 *b,Y memo ML14059A324 OFFICE NRR/LPL2-2/PM NRR/LPL2-2/LA NRR/STSB/BC* |
| PUBLIC LPL2-2 r/f RidsNrrPMWattsBar1 RidsAcrsAcnw | | NAME AHon BCiayton REIIiott DATE 3/14/14 3/14/14 3/10/14 OFFICE OGC/NLO NRR/LPL2-2/BC NRR/LPL2-2/PM NAME MYoung JQuichocho AHon DATE 3/26/14 4/7/14 4/7/14 OFFICIAL AGENCY RECORD}} |
| _MaiiCTR RidsNrrDssStsb RidsNrrLABCiayton KHemphill, NRR RidsNrrDoriDpr RidsNrrDorllpl2-2 RidsRgn2MaiiCenter RidsNrrPMWattsBar2 ADAMS A ccess1on N o.: ML 14071A339
| |
| *b ,Y memo ML 14059A324 OFFICE NRR/LPL2-2/PM N RR/LPL2-2/LA NRR/STSB/BC* | |
| NAME AHon BCiayton REIIiott DATE 3/14/14 3/14/14 3/10/14 OFFICE OGC/NLO NRR/LPL2-2/BC NRR/LPL2-2/PM NAME MYoung JQuichocho AHon DATE 3/26/14 4/7/14 4/7/14 OFFICIAL AGENCY RECORD}} | |
Letter Sequence Approval |
|---|
TAC:MF1461, Cancellation of NRC Environmental Monitoring Program with States (Approved, Closed) |
|
MONTHYEARML13144A2412013-06-0303 June 2013
Acceptance of Requested Licensing Action Regarding Application to Modify Administrative Control Section of Technical Specification 5.9.2 Per TSTF-348
Project stage: Acceptance Review
ML14071A3392014-04-0707 April 2014
Issuance of Amendment to Modify Administrative Controls Sections of Technical Specification by Adopting TSTF-348
Project stage: Approval
2013-06-03
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024
Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI)
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20243012024-10-17017 October 2024
Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301
ML24282B0412024-10-15015 October 2024
Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2
ML24260A1682024-10-0404 October 2024
Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5
ML24261C0062024-10-0404 October 2024
Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96
ML24284A1072024-09-26026 September 2024
Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
IR 05000390/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005
ML24218A1442024-08-27027 August 2024
Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
IR 05000390/20244022024-08-20020 August 2024
– Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public
CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024
Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),
ML24219A0262024-08-12012 August 2024
Request for Withholding Information from Public Disclosure
IR 05000390/20240022024-08-0707 August 2024
Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev
ML24204A2652024-07-25025 July 2024
Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24170A8002024-07-15015 July 2024
Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
IR 05000390/20244402024-07-12012 July 2024
95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter
05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024
Inoperability of Both Trains of Unit 2 Low Head Safety Injection
ML24131A0012024-07-0202 July 2024
Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2
CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024
Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024
License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24100A7642024-05-16016 May 2024
Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062)
IR 05000390/20240012024-05-14014 May 2024
Integrated Inspection Report 05000390/2024001 and 05000391/2024001
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024
Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO
IR 05000391/20240072024-04-30030 April 2024
Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
ML24087A1912024-04-18018 April 2024
Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024
Hydrologic Engineering Center River Analysis System Project Milestone Status Update
CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024
License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)
CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024
Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
IR 05000390/20244012024-04-0202 April 2024
– Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public)
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024
Annual Insurance Status Report
CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024
Guarantee of Payment of Deferred Premiums - 2023 Annual Report
CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024
Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule
ML24081A0262024-03-21021 March 2024
Emergency Plan Implementing Procedure Revisions
ML24079A0312024-03-19019 March 2024
Wb 2024-301, Corporate Notification Letter (210-day Ltr)
2024-09-05
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24218A1442024-08-27027 August 2024
Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
ML24170A8002024-07-15015 July 2024
Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts
ML24100A7642024-05-16016 May 2024
Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062)
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
ML23319A2452024-01-29029 January 2024
Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML23293A0572023-12-0606 December 2023
Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML23122A2322023-06-0707 June 2023
Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs)
ML23131A1812023-05-23023 May 2023
Correction to Amendment No. 161 to Facility Operating License No. NPF-90
ML23125A2202023-05-0505 May 2023
Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances)
ML23072A0652023-04-0505 April 2023
Units 1 and 2 – Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22257A0512022-11-0404 November 2022
Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A
ML22276A1612022-10-24024 October 2022
Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML22187A0192022-09-20020 September 2022
Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps
ML22187A1812022-09-20020 September 2022
Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train
ML22014A2062022-05-0404 May 2022
Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors
ML21347A9672022-02-0101 February 2022
Correction of Errors Incurred During Issuance of the Initial Facility Operating License, and Issuance of License Amendment Nos. 6, 21, and 39
ML21306A2872022-01-25025 January 2022
Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement
ML21334A2952022-01-18018 January 2022
Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement
ML21334A3892022-01-12012 January 2022
Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis
ML21271A1372021-12-16016 December 2021
Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building
ML21260A2102021-11-22022 November 2021
Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level
ML21189A3072021-11-0303 November 2021
Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program
ML21158A2842021-09-17017 September 2021
Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation
ML21153A0492021-07-26026 July 2021
Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510
ML21161A2392021-06-24024 June 2021
Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria
ML21148A1002021-06-17017 June 2021
Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology
ML21099A2462021-05-14014 May 2021
Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML21078A4842021-05-0505 May 2021
Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications
ML21015A0342021-03-0909 March 2021
Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation
ML21034A1692021-02-26026 February 2021
Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
ML20232C6222021-02-11011 February 2021
Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037
ML21027A1672021-02-0909 February 2021
Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment
ML20350B4932021-01-25025 January 2021
Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML21005A1252021-01-12012 January 2021
Correction of Errors Incurred During Issuance of License Amendment Nos. 43 and 45
ML20268A0822021-01-12012 January 2021
Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications
ML20245E4132020-12-0808 December 2020
Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20239A7912020-10-28028 October 2020
Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2
ML20226A4442020-10-21021 October 2020
Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate
ML20238C0612020-09-21021 September 2020
Correction of Typographical Error Incurred During Issuance of License Amendment No. 104
ML20167A1482020-08-19019 August 2020
Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer
ML20156A0182020-08-10010 August 2020
Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve
ML20076A1942020-04-30030 April 2020
Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants
ML20057E2422020-03-30030 March 2020
Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003)
ML20028F7332020-02-28028 February 2020
Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3
ML20024F8352020-02-24024 February 2020
Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train
ML20015A4792020-01-30030 January 2020
Correction to Amendment No. 30 to Facility Operating License Npf-96 Regarding Use of Optimized Zirlo Fuel Rod Cladding
2024-08-27
[Table view]
Category:Safety Evaluation
MONTHYEARML24218A1442024-08-27027 August 2024
Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
ML24170A8002024-07-15015 July 2024
Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts
ML24100A7642024-05-16016 May 2024
Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062)
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
ML23319A2452024-01-29029 January 2024
Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML23293A0572023-12-0606 December 2023
Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML23233A0042023-08-28028 August 2023
– Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds
ML23125A2202023-05-0505 May 2023
Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances)
ML23072A0652023-04-0505 April 2023
Units 1 and 2 – Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12
ML23048A3042023-03-0808 March 2023
Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047)
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22293A4082022-11-14014 November 2022
Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
ML22257A0512022-11-0404 November 2022
Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A
ML22276A1612022-10-24024 October 2022
Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML22272A5682022-10-12012 October 2022
Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code
ML22187A1812022-09-20020 September 2022
Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train
ML22187A0192022-09-20020 September 2022
Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps
ML22014A2062022-05-0404 May 2022
Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors
ML22084A0012022-04-0505 April 2022
Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes
ML22070A0022022-03-28028 March 2022
Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report
ML21306A2872022-01-25025 January 2022
Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement
ML21334A2952022-01-18018 January 2022
Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement
ML21334A3892022-01-12012 January 2022
Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis
ML21271A1372021-12-16016 December 2021
Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building
ML21260A2102021-11-22022 November 2021
Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level
ML21189A3072021-11-0303 November 2021
Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program
ML21158A2842021-09-17017 September 2021
Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation
ML21153A0492021-07-26026 July 2021
Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510
ML21161A2392021-06-24024 June 2021
Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria
ML21148A1002021-06-17017 June 2021
Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology
ML21099A2462021-05-14014 May 2021
Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML21130A6012021-05-13013 May 2021
Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B
ML21078A4842021-05-0505 May 2021
Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications
ML21110A0372021-04-29029 April 2021
Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B
ML21064A4082021-03-10010 March 2021
Correction of Safety Evaluation for License Amendment Nos. 143 and 50 (EPID L-2020-LLA-0005) (Non-Proprietary)
ML21015A0342021-03-0909 March 2021
Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation
ML21034A1692021-02-26026 February 2021
Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
ML20232C6222021-02-11011 February 2021
Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037
ML21027A1672021-02-0909 February 2021
Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment
ML20350B4932021-01-25025 January 2021
Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML20268A0822021-01-12012 January 2021
Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications
ML20245E4132020-12-0808 December 2020
Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20239A7912020-10-28028 October 2020
Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2
ML20226A4442020-10-21021 October 2020
Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate
ML20167A1482020-08-19019 August 2020
Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer
ML20156A0182020-08-10010 August 2020
Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve
ML20076A1942020-04-30030 April 2020
Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants
2024-08-27
[Table view]
Category:Technical Specifications
MONTHYEARWBL-24-019, Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2024-04-30030 April 2024
Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
ML23319A2452024-01-29029 January 2024
Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024
Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024
Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability
CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024
Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)
CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023
Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22276A1612022-10-24024 October 2022
Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML22187A0192022-09-20020 September 2022
Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps
ML22187A1812022-09-20020 September 2022
Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train
CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022
Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)
CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022
Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)
WBL-22-017, Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2022-03-22022 March 2022
Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report
ML21260A2102021-11-22022 November 2021
Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level
ML21158A2842021-09-17017 September 2021
Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation
ML21099A2462021-05-14014 May 2021
Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML21078A4842021-05-0505 May 2021
Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications
ML21015A0342021-03-0909 March 2021
Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation
ML21034A1692021-02-26026 February 2021
Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
ML20232C6222021-02-11011 February 2021
Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20226A4442020-10-21021 October 2020
Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate
ML20273A0432020-09-29029 September 2020
Plants Unit 1 and 2 - Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual
ML20156A0182020-08-10010 August 2020
Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve
CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2020-03-0202 March 2020
Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat
ML20028F7332020-02-28028 February 2020
Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3
ML19276E5572019-12-0909 December 2019
Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-500, DC Electrical Rewrite - Update to TSTF-360
ML19238A0052019-11-26026 November 2019
Issuance of Amendment Nos. 129 and 32 Regarding Changes to Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9
CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019
Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)
CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019
Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)
ML18277A1102019-08-27027 August 2019
Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection
ML19112A0042019-07-25025 July 2019
Issuance of Amendment Nos. 127 and 30 Regarding the Use of Optimized Zirlo Fuel Rod Cladding
ML19098A7742019-06-0707 June 2019
Issuance of Amendments Regarding Technical Specifications Changes Pertaining to 120-Volt Alternating Current Vital Buses
ML18255A1562018-10-30030 October 2018
Issuance of Amendment to Modify Technical Specification 3.3.1 Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure
ML18079A0292018-06-26026 June 2018
Issuance of Amendments Regarding Adoption of TSTF-547, Clarification of Rod Position Requirements (CAC Nos. MF8912and MF8913; EPID L-2016-LLA-0034)
ML17311A7862017-12-0707 December 2017
Issuance of Amendment Regarding Ventilation Filter Testing Program (CAC No. MF9584; EPID L-2017-LLA-0207)
ML17215A2432017-10-0202 October 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566)
CNL-17-029, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources2017-03-0606 March 2017
Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources
ML16343A8142017-01-0505 January 2017
Issuance of Amendment Regarding One-Time Extension of Intervals for Surveillance Requirements 3.6.11.2 and 3.6.11.3
NL-16-164, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)2016-10-17017 October 2016
Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)
CNL-16-164, Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)2016-10-17017 October 2016
Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)
ML16159A0572016-07-29029 July 2016
Issuance of Amendment Regarding Revised Technical Specification 4.2.1 Fuel Assemblies to Increase the Maximum Number of Tritium Producing Burnable Absorber Rods
CNL-16-047, Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria2016-05-0404 May 2016
Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria
ML15344A3182015-12-23023 December 2015
Issuance of Amendment Regarding Fire Protection License Conditions
ML15348A1122015-12-14014 December 2015
Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program
ML15301A1402015-10-22022 October 2015
Current Facility Operating License NPF-96, Tech Specs, Revised 11/08/2017
ML15251A5872015-10-22022 October 2015
Issuance of Facility Operating License No. NPF-96 Watts Bar Nuclear Plant, Unit 2
2024-04-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 7, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT TO MODIFY ADMINSTRATIVE CONTROLS SECTIONS OF TECHNICAL SPECIFICATION BY ADOPTING TSTF-348 (TAC NO. MF1461)
Dear Mr. Shea:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 96 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1. This amendment consists of changes to the license and the Technical Specifications (TSs) in response to your application dated April 12, 2013.
The proposed amendment will modify Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report." The proposed change is consistent with NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States."
In addition, the proposed amendment will modify TS 5.9.8, "PAMS [Post Accident Monitoring System] Report." These editorial changes update the TSs to remove an obsolete Thermoluminescent Dosimeter requirement, and correct enumeration as a result of a previous license amendment.
J.Shea A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 96 to NPF-90
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-90
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (the licensee) dated April 12, 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 Title 10 of the Code of Federal Regulations (1 0 CFR)
Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 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. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s .Ouic~~
lant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and the Technical Specifications Date of Issuance: April 7, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 3 of Operating License NPF-90 with the attached Page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain a marginal line indicating the area of change.
REMOVE INSERT 5.0-27 5.0-27 5.0-32 5.0-32
(4) TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and (5) TVA, 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.
(1) Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 96 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Facility License No. NPF-90 Amendment No. 96
Reporting Requirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.9.1 DELETED 5.9.2 Annual Radiological Environmental Operating Report
NOTE----------------------------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
(continued)
Watts Bar-Unit 1 5.0-27 Amendment 57, 96
Reporting Requirements 5.9 5.9 Reporting Requirements (continued) 5.9.7 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days. Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4, or existing Regulatory Guide 1.108 reporting requirement.
5.9.8 PAMS Report When a Report is required by Condition B or F of LCO 3.3.3, "Post Accident Monitoring (PAM)
Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplan ned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.9.9 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5. 7 .2.12, Steam Generator (SG) Program. The report shall include:
- a. The scope of inspections performed on each SG,
- b. Active degradation mechanisms found,
- c. Nondestructive examination techniques utilized for each degradation mechanism,
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
- e. Number of tubes plugged during the inspection outage for each active degradation mechanism,
- f. Total number and percentage of tubes plugged to date,
- g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and
- h. The effective plugging percentage for all plugging in each SG.
Watts Bar-Unit 1 5.0-32 Amendment 27, 38, 65, 96 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390
1.0 INTRODUCTION
By letter dated April 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13106A146), Tennessee Valley Authority (the licensee) proposed changes to the Technical Specifications (TSs) for Watts Bar Unit 1 (WBN1). The proposed editorial changes revise TS 5.9.2, "Annual Radiological Environmental Operating Report," and TS 5.9.8, "PAMS [Post Accident Monitoring System] Report."
The licensee stated that the proposed change toTS 5.9.2 is consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler, TSTF-348, "Cancellation of NRC Environmental Monitoring Program with States" (ADAMS No. ML040630068). TSTF-348 removes an obsolete Thermoluminescent Dosimeter (TLD) TS requirement. The change to TS 5.9.8 is necessary to correct enumeration as a result of a previous license amendment.
2.0 REGULATORY EVALUATION
The NRCs regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (1 0 CFR), Part 50, Section 50.36, "Technical specifications." The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and control settings, (2) Limiting Conditions for Operation (LCO),
(3) Surveillance Requirements (SRs), (4) design features, and (5) administrative controls.
Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
3.0 TECHNICAL EVALUATION
3.1 TS 5.9.2, "Annual Radiological Environmental Operating Report" The licensee proposed to delete the following sentence, currently in the last paragraph of Specification 5.9.2:
Enclosure
"The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result."
In Press Release No. 98-08, dated January 13, 1998 (ADAMS No. ML003708685), the NRC announced that it had ended its contract with 34 states to perform radiation monitoring around certain facilities as of the end of 1997. As a result, TSTF-348 revised STS 5.6.2, "Annual Radiological Environmental Operating Report," to delete reference to collocated dosimeters to reflect cancellation of the NRC environmental monitoring program with States. The licensee proposed to adopt this TSTF change without deviation in corresponding WBN1 TS 5.9.2. The proposed change removes an obsolete reporting requirement and is, therefore, corrective or editorial in nature. The staff finds this change acceptable.
3.2 TS 5.9.8, "PAMS Report" The first sentence of WBN1 TS 5.9.8 currently states:
"When a Report is required by Condition B or G of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days."
The proposed change states:
"When a Report is required by Condition B or F of LCO 3.3.3, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days."
The proposed change corrects a cross-reference error introduced with the implementation of WBN1 License Amendment 72, issued December 23, 2008 (ADAMS No. ML082970645).
Deletion of TS 3.3.3, Condition D resulted in Conditions E, F, and G being changed to Conditions D, E, and F, respectively. However, the impact of the December 23, 2008, change on TS 5.9.8 reference was not previously identified. The NRC staff finds that the re-lettering change is editorial and clarifying in nature and is consistent with the current intent of the TS requirement. Therefore, the NRC staff finds this corrective change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii) and (v). 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, there is reasonable assurance that: (1) the health and safety of the public will not be endangered by operation in the proposed manner, (2) that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Contributors: K. Hemphill Date: April 7, 2014
J. Shea A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA/
Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 96 to NPF-90
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 r/f RidsNrrDssStsb RidsNrrDoriDpr RidsNrrDorllpl2-2 RidsNrrPMWattsBar1 RidsNrrLABCiayton RidsRgn2MaiiCenter RidsAcrsAcnw_MaiiCTR KHemphill, NRR RidsNrrPMWattsBar2 ADAMS Access1on No.: ML14071A339 *b,Y memo ML14059A324 OFFICE NRR/LPL2-2/PM NRR/LPL2-2/LA NRR/STSB/BC*
NAME AHon BCiayton REIIiott DATE 3/14/14 3/14/14 3/10/14 OFFICE OGC/NLO NRR/LPL2-2/BC NRR/LPL2-2/PM NAME MYoung JQuichocho AHon DATE 3/26/14 4/7/14 4/7/14 OFFICIAL AGENCY RECORD
