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| {{#Wiki_filter:October 28, 2008 | | {{#Wiki_filter:October 28, 2008 Mr. William R. Campbell, Jr. |
| | | Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
| Mr. William R. Campbell, Jr. | |
| Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATTS BAR NUCLEAR PLANT, UNIT 1 C CORRECTION TO AMENDMENT NO. 70 REGARDING CONTROL ROOM ENVELOPE HABITABILITY (TAC NO. MD7474) | | WATTS BAR NUCLEAR PLANT, UNIT 1 C CORRECTION TO AMENDMENT NO. 70 REGARDING CONTROL ROOM ENVELOPE HABITABILITY (TAC NO. MD7474) |
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| ==Dear Mr. Campbell:== | | ==Dear Mr. Campbell:== |
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| The U.S. Nuclear Regulatory Commi ssion (NRC) issued the Amendment No. 70 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1 on October 8, 2008 (Agencywide Document Access and Management System Accession No. ML082730231). This amendment was in response to your application dated October 26, 2007 (ML073380948). | | The U.S. Nuclear Regulatory Commission (NRC) issued the Amendment No. 70 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1 on October 8, 2008 (Agencywide Document Access and Management System Accession No. ML082730231). This amendment was in response to your application dated October 26, 2007 (ML073380948). |
| Amendment No. 70 revised the Technical Specifications (TS) to adopt TS Task Force (TSTF) | | Amendment No. 70 revised the Technical Specifications (TS) to adopt TS Task Force (TSTF) |
| Change Traveler TSTF-448, Revision 3, "Control Room Envelope Habitability." | | Change Traveler TSTF-448, Revision 3, Control Room Envelope Habitability. |
| | | Subsequent to issuance, it was discovered that pages 4 and 4a of the License, which contain license conditions, were inadvertently omitted. Enclosed are the corrected pages containing the license condition for Amendment No. 70. Please replace the authorization pages and insert the license pages in Amendment No. 70 issued on October 8, 2008. This corrects an administrative error and does not affect the technical content of Amendment No. 70 and its associated safety evaluation. |
| Subsequent to issuance, it was discovered that pages 4 and 4a of the License, which contain license conditions, were inadvertently omitted. Enclosed are the corrected pages containing the license condition for Amendment No. 70. Please replace the authorization pages and insert the license pages in Amendment No. 70 issued on October 8, 2008. This corrects an administrative error and does not affect the technical content of Amendment No. 70 and its associated safety evaluation. | | We regret any inconvenience this may have caused. If you have any questions, please contact me at (301) 415-3100. |
| | | Sincerely, |
| We regret any inconvenience this may have caused. If you have any questions, please contact me at (301) 415-3100. | | /RA/ |
| | | John G. Lamb, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 |
| Sincerely, | |
| /RA/ John G. Lamb, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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| Docket No. 50-390 | |
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| ==Enclosure:== | | ==Enclosure:== |
| License pages 4 and 4a | | License pages 4 and 4a cc w/enclosure: See next page |
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| cc w/enclosure: See next page | |
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| ML083010065 OFFICE LPWB/PM LPWB/LA LPWB/BC NAME JLamb BClayton LRagahavan DATE 10 / 28 / 08 10 / 28 /08 10 / 28 /08 William R. Campbell, Jr. Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
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| Mr. Gordon P. Arent New Generation Licensing Manager Tennessee Valley Authority 5A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Vice President Nuclear Support Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. H. Rick Rogers Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902
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| Mr. John C. Fornicola, Manager Nuclear Assurance Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381 Mr. Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
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| Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
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| Mr. Masoud Bajestani, Vice President Watts Bar Unit 2 Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Mr. Michael K. Brandon, Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Mr. Michael J. Lorek, Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
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| Senior Resident Inspector Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381
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| County Executive 375 Church Street Suite 215 Dayton, TN 37321
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| County Mayor P. O. Box 156 Decatur, TN 37322 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532
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| TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
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| Amendment No. 70 License No. NPF-90
| | ML083010065 OFFICE LPWB/PM LPWB/LA LPWB/BC NAME JLamb BClayton LRagahavan DATE 10 / 28 / 08 10 / 28 /08 10 / 28 /08 William R. Campbell, Jr. |
| : 1. The Nuclear Regulatory Commission (the Commission) has found that: | | Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc: |
| | Mr. Gordon P. Arent Site Vice President New Generation Licensing Manager Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 5A Lookout Place P. O. Box 2000 1101 Market Street Spring City, TN 37381 Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Mr. Ashok S. Bhatnagar Senior Licensing Manager Senior Vice President Nuclear Power Group Nuclear Generation Development Tennessee Valley Authority and Construction 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Vice President Industry Affairs Nuclear Support Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President Mr. H. Rick Rogers Watts Bar Unit 2 Vice President Watts Bar Nuclear Plant Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael K. Brandon, Manager Licensing and Industry Affairs General Counsel Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A West Tower P.O. Box 2000 400 West Summit Hill Drive Spring City, TN 37381 Knoxville, TN 37902 Mr. Michael J. Lorek, Plant Manager Mr. John C. Fornicola, Manager Watts Bar Nuclear Plant Nuclear Assurance Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Senior Resident Inspector Watts Bar Nuclear Plant Mr. Larry E. Nicholson, General Manager U.S. Nuclear Regulatory Commission Performance Improvement 1260 Nuclear Plant Road Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs |
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| A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the
| | County Executive 375 Church Street Suite 215 Dayton, TN 37321 County Mayor P. O. Box 156 Decatur, TN 37322 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 |
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| 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. | | TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-90 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this 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. |
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| 2 2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operati ng License No. NPF-90 is hereby amended to read as follows: | | 2 |
| (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, 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. | | : 2. Accordingly, the license is amended by changes to the Operating License and 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 Appendices A and B, as revised through Amendment No. 70, 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 60 days from the date of its issuance. | | : 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 60 days from the date of its issuance. |
| FOR THE NUCLEAR REGULATORY COMMISSION | | FOR THE NUCLEAR REGULATORY COMMISSION |
| | | /RA/ |
| /RA/ L. Raghavan, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | L. Raghavan, Chief Watts Bar Special Projects Branch 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 Technical Specifications | | Changes to the Operating License and Technical Specifications Date of Issuance: October 8, 2008 |
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| Date of Issuance: October 8, 2008 | |
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| CORRECTION TO AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390
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| Replace Page 4 of Operating License NPF-90 with the attached Page 4.
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| Insert Page 4a of Operating License NPF-90 with the attached Page 4a.
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| The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.
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| (5) Reactor Vessel Fracture Toughness Testing Supplemental fracture toughness testing (J-R) will be performed in accordance with a testing procedure that has been previously reviewed and approved by the NRC staff on Surveillance Capsule W specimens (removed from Cycle 3 Refueling Outage) and Capsule X specimens (to be removed from Cycle 5 Refueling Outage). The supplemental test results will be included in the report to be submitted in accordance with 10 CFR 50, Appendix H requirements for each Capsule specimen and will include an evaluation of the effects on TVA's equivalent margins analysis which was submitted October 15, 1993 and approved by NRC in Supplemental Safety Evaluation Report (SSER) 14.
| | CORRECTION TO AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 4 of Operating License NPF-90 with the attached Page 4. |
| | Insert Page 4a of Operating License NPF-90 with the attached Page 4a. |
| | The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change. |
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| (6) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: | | (5) Reactor Vessel Fracture Toughness Testing Supplemental fracture toughness testing (J-R) will be performed in accordance with a testing procedure that has been previously reviewed and approved by the NRC staff on Surveillance Capsule W specimens (removed from Cycle 3 Refueling Outage) and Capsule X specimens (to be removed from Cycle 5 Refueling Outage). The supplemental test results will be included in the report to be submitted in accordance with 10 CFR 50, Appendix H requirements for each Capsule specimen and will include an evaluation of the effects on TVA's equivalent margins analysis which was submitted October 15, 1993 and approved by NRC in Supplemental Safety Evaluation Report (SSER) 14. |
| (a) Fire fighting response strategy with the following elements: 1. Pre-defined coordinated fire response strategy and guidance | | (6) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas: |
| | (a) Fire fighting response strategy with the following elements: |
| | : 1. Pre-defined coordinated fire response strategy and guidance |
| : 2. Assessment of mutual aid fire fighting assets | | : 2. Assessment of mutual aid fire fighting assets |
| : 3. Designated staging areas for equipment and materials | | : 3. Designated staging areas for equipment and materials |
| : 4. Command and control | | : 4. Command and control |
| : 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: 1. Protection and use of personnel assets | | : 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following: |
| | : 1. Protection and use of personnel assets |
| : 2. Communications | | : 2. Communications |
| : 3. Minimizing fire spread | | : 3. Minimizing fire spread |
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| : 5. Identification of readily-available pre-staged equipment | | : 5. Identification of readily-available pre-staged equipment |
| : 6. Training on integrated fire response strategy | | : 6. Training on integrated fire response strategy |
| : 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing | | : 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: |
| : 2. Dose to onsite responders | | : 1. Water spray scrubbing |
| | | : 2. Dose to onsite responders (7) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate. |
| (7) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate. | | Amendment No. 70 |
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| Amendment No. 70 | |
| - 4a - (8) Upon implementation of Amendment No. 70 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.10.4, in accordance with TS .7.2.20.c.(i), the assessment of CRE habitability as required by Specification 5.7.2.20.c.(ii), and the measurement of CRE pressure as required by Specification 5.7.2.20.d, shall be considered met following implementation:
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| (a) The first performance of SR 3.7.10.4, in accordance with Specification 5.7.2.20.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004, letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
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| (b) The first performance of the per iodic assessment of CRE habitability, Specification 5.7.2.20.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
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| (c) The first performance of the periodic measurement of CRE pressure, Specification 5.7.2.20.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from May 10, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.
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| D. The following exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Therefore, these exemptions are granted pursuant to 10 CFR 50.12.
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| (1) Deleted
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| Amendment No. 70}} | | - 4a - |
| | (8) Upon implementation of Amendment No. 70 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.10.4, in accordance with TS .7.2.20.c.(i), the assessment of CRE habitability as required by Specification 5.7.2.20.c.(ii), and the measurement of CRE pressure as required by Specification 5.7.2.20.d, shall be considered met following implementation: |
| | (a) The first performance of SR 3.7.10.4, in accordance with Specification 5.7.2.20.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004, letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. |
| | (b) The first performance of the periodic assessment of CRE habitability, Specification 5.7.2.20.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. |
| | (c) The first performance of the periodic measurement of CRE pressure, Specification 5.7.2.20.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from May 10, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously. |
| | D. The following exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Therefore, these exemptions are granted pursuant to 10 CFR 50.12. |
| | (1) Deleted Amendment No. 70}} |
Letter Sequence Other |
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TAC:MD7474, Control Room Habitability (Approved, Closed) |
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MONTHYEARML0823810742008-08-25025 August 2008
Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed Nshcd STF-448 Control Room Habitability
Project stage: Other
ML0823810652008-08-25025 August 2008
Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing
Project stage: Other
ML0827302612008-10-0808 October 2008
Issuance of Amendment Regarding Control Room Envelope Habitability
Project stage: Approval
ML0830100652008-10-28028 October 2008
Correction to Amendment No. 70 Regarding Control Room Envelope Habitability
Project stage: Other
ML0832504502008-11-24024 November 2008
Correction to Amendment No. 70 Regarding Control Room Envelope Habitability
Project stage: Other
2008-10-08
[Table View] |
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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
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
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
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)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
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
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-24-010, 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
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
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
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
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-24-025, 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] |
Text
October 28, 2008 Mr. William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 C CORRECTION TO AMENDMENT NO. 70 REGARDING CONTROL ROOM ENVELOPE HABITABILITY (TAC NO. MD7474)
Dear Mr. Campbell:
The U.S. Nuclear Regulatory Commission (NRC) issued the Amendment No. 70 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1 on October 8, 2008 (Agencywide Document Access and Management System Accession No. ML082730231). This amendment was in response to your application dated October 26, 2007 (ML073380948).
Amendment No. 70 revised the Technical Specifications (TS) to adopt TS Task Force (TSTF)
Change Traveler TSTF-448, Revision 3, Control Room Envelope Habitability.
Subsequent to issuance, it was discovered that pages 4 and 4a of the License, which contain license conditions, were inadvertently omitted. Enclosed are the corrected pages containing the license condition for Amendment No. 70. Please replace the authorization pages and insert the license pages in Amendment No. 70 issued on October 8, 2008. This corrects an administrative error and does not affect the technical content of Amendment No. 70 and its associated safety evaluation.
We regret any inconvenience this may have caused. If you have any questions, please contact me at (301) 415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
License pages 4 and 4a cc w/enclosure: See next page
ML083010065 OFFICE LPWB/PM LPWB/LA LPWB/BC NAME JLamb BClayton LRagahavan DATE 10 / 28 / 08 10 / 28 /08 10 / 28 /08 William R. Campbell, Jr.
Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Gordon P. Arent Site Vice President New Generation Licensing Manager Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 5A Lookout Place P. O. Box 2000 1101 Market Street Spring City, TN 37381 Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Mr. Ashok S. Bhatnagar Senior Licensing Manager Senior Vice President Nuclear Power Group Nuclear Generation Development Tennessee Valley Authority and Construction 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Vice President Industry Affairs Nuclear Support Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President Mr. H. Rick Rogers Watts Bar Unit 2 Vice President Watts Bar Nuclear Plant Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael K. Brandon, Manager Licensing and Industry Affairs General Counsel Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A West Tower P.O. Box 2000 400 West Summit Hill Drive Spring City, TN 37381 Knoxville, TN 37902 Mr. Michael J. Lorek, Plant Manager Mr. John C. Fornicola, Manager Watts Bar Nuclear Plant Nuclear Assurance Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Senior Resident Inspector Watts Bar Nuclear Plant Mr. Larry E. Nicholson, General Manager U.S. Nuclear Regulatory Commission Performance Improvement 1260 Nuclear Plant Road Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs
County Executive 375 Church Street Suite 215 Dayton, TN 37321 County Mayor P. O. Box 156 Decatur, TN 37322 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-90
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2
- 2. Accordingly, the license is amended by changes to the Operating License and 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 Appendices A and B, as revised through Amendment No. 70, 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 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: October 8, 2008
CORRECTION TO AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 4 of Operating License NPF-90 with the attached Page 4.
Insert Page 4a of Operating License NPF-90 with the attached Page 4a.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.
(5) Reactor Vessel Fracture Toughness Testing Supplemental fracture toughness testing (J-R) will be performed in accordance with a testing procedure that has been previously reviewed and approved by the NRC staff on Surveillance Capsule W specimens (removed from Cycle 3 Refueling Outage) and Capsule X specimens (to be removed from Cycle 5 Refueling Outage). The supplemental test results will be included in the report to be submitted in accordance with 10 CFR 50, Appendix H requirements for each Capsule specimen and will include an evaluation of the effects on TVA's equivalent margins analysis which was submitted October 15, 1993 and approved by NRC in Supplemental Safety Evaluation Report (SSER) 14.
(6) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
- 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:
- 1. Water spray scrubbing
- 2. Dose to onsite responders (7) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.
Amendment No. 70
- 4a -
(8) Upon implementation of Amendment No. 70 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.10.4, in accordance with TS .7.2.20.c.(i), the assessment of CRE habitability as required by Specification 5.7.2.20.c.(ii), and the measurement of CRE pressure as required by Specification 5.7.2.20.d, shall be considered met following implementation:
(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.7.2.20.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004, letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b) The first performance of the periodic assessment of CRE habitability, Specification 5.7.2.20.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.7.2.20.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from May 10, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.
D. The following exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Therefore, these exemptions are granted pursuant to 10 CFR 50.12.
(1) Deleted Amendment No. 70
