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| | docket = 05000390 | | | docket = 05000390 |
| | license number = NPF-090 | | | license number = NPF-090 |
| | contact person = Moroney B T, NRR/DORL, 415-3974 | | | contact person = Moroney B, NRR/DORL, 415-3974 |
| | case reference number = TAC MD5430 | | | case reference number = TAC MD5430 |
| | package number = ML073530482 | | | package number = ML073530482 |
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| {{#Wiki_filter:Accumulators | | {{#Wiki_filter:Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours |
| | _>7630 gallons and < 8000 gallons. |
| | SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 12 hours |
| | _>610 psig and |
| | * 660 psig SR 3.5.1.4 -------------------------- NOTE ------------------- 31 days The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) AND for each operating cycle. |
| | --.------------------------------------------------ NOTE --------- |
| | Only required to be Verify boron concentration in each accumulator is as performed for provided below depending on the number of tritium affected producing burnable absorber rods (TPBARs) installed accumulators. |
| | in the reactor core for this operating cycle: |
| | Once within 6 hours after each solution Number of TPBARs Boron Concentration Ranges volume increase of 0-400 > 3000 ppm and < 3300 ppm 75 gallons, that is not the result of addition from the refueling water storage tank. |
| | (continued) |
| | Watts Bar-Unit 1 3.5-2 Amendment 7, 21, 40, 48. 67 |
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| |
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| ====3.5.1 SURVEILLANCE====
| | RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 ----------------------- NOTE ------------------ |
| | Only required to be performed when ambient air temperature is < 60'F or > 105'F. |
| | Verify RWST borated water temperature is 24 hours |
| | > 60°F and < 105'F. |
| | SR 3.5.4.2 Verify RWST borated water volume is 7 days |
| | > 370,000 gallons. |
| | SR 3.5.4.3 ------------------------ NOTE ------------------ |
| | The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) for each operating cycle. |
| | Verify boron concentration in the RWST is as provided 7 days belowdepending on the number of tritium producing burnable absorber rods (TPBARs) installed in the reactor core for this operating cycle: |
| | Number of TPBARS Boron Concentration Ranges 0-400 >3100 ppm and < 3300 ppm Watts Bar-Unit 1 3.5-10 Amendment 7, 40, 48, 67 |
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| |
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| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours_> 7630 gallons and < 8000 gallons.SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 12 hours_> 610 psig and 660 psig SR 3.5.1.4 --------------------------
| | Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries shall be as shown in Figure 4.1-1. |
| NOTE -------------------
| | 4.1.2 Low Population Zone (LPZ) |
| 31 days The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) AND for each operating cycle.--.------------------------------------------------
| | The LPZ shall be as shown in Figure 4.1-2 (within the 3-mile circle). |
| NOTE ---------Only required to be Verify boron concentration in each accumulator is as performed for provided below depending on the number of tritium affected producing burnable absorber rods (TPBARs) installed accumulators.
| | 4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy or Zirlo fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. For Unit 1, Watts Bar is authorized to place a maximum of 400 Tritium Producing Burnable Absorber Rods into the reactor in an operating cycle. I 4.2.2 Control Rod Assemblies The reactor core shall contain 57 control rod assemblies. The control material shall be boron carbide with silver indium cadmium tips as approved by the NRC. |
| in the reactor core for this operating cycle: Once within 6 hours after each solution Number of TPBARs Boron Concentration Ranges volume increase of 0-400 > 3000 ppm and < 3300 ppm 75 gallons, that is not the result of addition from the refueling water storage tank.(continued)
| | (continued) |
| Watts Bar-Unit 1 3.5-2 Amendment 7, 21, 40, 48. 67 RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -----------------------
| | Watts Bar Unit 1 4.0-1 Amendment 8, 40, 48, 67}} |
| NOTE ------------------
| |
| Only required to be performed when ambient air temperature is < 60'F or > 105'F.Verify RWST borated water temperature is 24 hours> 60°F and < 105'F.SR 3.5.4.2 Verify RWST borated water volume is 7 days> 370,000 gallons.SR 3.5.4.3 ------------------------
| |
| NOTE ------------------
| |
| The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) for each operating cycle.Verify boron concentration in the RWST is as provided 7 days belowdepending on the number of tritium producing burnable absorber rods (TPBARs) installed in the reactor core for this operating cycle: Number of TPBARS Boron Concentration Ranges 0-400 >3100 ppm and < 3300 ppm Watts Bar-Unit 1 3.5-10 Amendment 7, 40, 48, 67 Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries shall be as shown in Figure 4.1-1.4.1.2 Low Population Zone (LPZ)The LPZ shall be as shown in Figure 4.1-2 (within the 3-mile circle).4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies.
| |
| Each assembly shall consist of a matrix of Zircalloy or Zirlo fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. | |
| Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. For Unit 1, Watts Bar is authorized to place a maximum of 400 Tritium Producing Burnable Absorber Rods into the reactor in an operating cycle.4.2.2 Control Rod Assemblies The reactor core shall contain 57 control rod assemblies. | |
| The control material shall be boron carbide with silver indium cadmium tips as approved by the NRC.I (continued) | |
| Watts Bar Unit 1 4.0-1 Amendment 8, 40, 48, 67}} | |
Letter Sequence Other |
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MONTHYEARML0204507012002-02-11011 February 2002 Unit - Request for Additional Information Re Tritium Production Program Interface Issue 7 Project stage: RAI ML0205800822002-02-19019 February 2002 Response to Request for Additional Information Re Tritium Production - Holtec Analysis. Submits New non-proprietary Version (Revision 3) of Holtec International Report HI-2012620 Project stage: Response to RAI ML0205806122002-02-21021 February 2002 License Amendment, FSAR Change for Revised Spent Fuel Cooling Analysis Methodology - TAC Nos. MB1807 and MB1884 Project stage: Other ML0205800052002-02-21021 February 2002 Responses to RAI Regarding Tritium Producing Burnable Absorber Rods (TPBARS) Project stage: Response to RAI ML0205804302002-02-21021 February 2002 Tennessee Valley Authority Response to NRC Request for Additional Information Re Tritium Producing Burnable Absorber Rods (TPBARS) at Watts Bar Nuclear Plant Project stage: Response to RAI ML0210003612002-04-0505 April 2002 Response to Request for Additional Information Re Tritium Production - Interface Issue Number 2 - Procurement and Fabrication Issues Project stage: Response to RAI ML0211905572002-04-25025 April 2002 Second Request for Additional Information Tritium Production Program Interface Issue 7 Project stage: RAI ML0212806302002-05-0808 May 2002 Request for Additional Information Re Tritium Production Program Interface Issue 5 Project stage: RAI ML0214401522002-05-21021 May 2002 Request for Additional Information Regarding Tritium Production - Interface Issue Number 7 Light Load Handling Systems Project stage: Request ML0214401422002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 7 - Light Load Handling Systems Project stage: Request ML0214401352002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 5 - Control Room Habitability Systems Project stage: Request ML0214901392002-05-23023 May 2002 Response to Request for Additional Information Re Radiological Impact Project stage: Response to RAI ML0221004492002-07-29029 July 2002 Request for Additional Information Tritium Production Program Project stage: RAI ML0221401972002-07-30030 July 2002 Tritium Production -- Post-LOCA Hot Leg Emergency Core Cooling System (ECCS) Recirculation Time -- Supplemental Information Project stage: Supplement ML0222601522002-08-0909 August 2002 Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0831800942002-08-0909 August 2002 Plants - Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0223209052002-08-20020 August 2002 Environmental Assessment and Finding of No Significant Impact for Incore Irradiation Services for the U. S. Department of Energy'S Tritium Production Program Project stage: Other ML0225409252002-09-23023 September 2002 Amendment No. 40, Irridiate Up to 2304 Tritium-Producing Burnable Absorber Rods in the Reactor Core Project stage: Acceptance Review ML0227502952002-09-23023 September 2002 Technical Specification Pages for Amendment No. 40, Irradiated Up to 2304 Tritium Producing Burnable Absborber Rods in the Reactor Core Project stage: Other ML0802203782008-01-18018 January 2008 Tech Spec Pages for Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Other ML0735205462008-01-18018 January 2008 Issuance of License Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML0821800942008-07-31031 July 2008 WCAP-16932-NP, Rev. 1, Control Rod Insertion Following a Cold Leg LOCA for Watts Bar Unit 1. Project stage: Request ML0821800932008-08-0101 August 2008 Watt'S Bar, Unit 1, Technical Specifications Change - Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Request ML0827502132008-10-0606 October 2008 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 (Tac No. MD9396) Project stage: Withholding Request Acceptance ML0828314472008-10-14014 October 2008 Request for Additional Information Regarding Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of -Coolant Accident (Tac MD9396) Project stage: RAI ML0829401702008-10-28028 October 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0830401042008-11-0707 November 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0833601912008-11-25025 November 2008 Response to Request for Additional Information Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of-Coolant Accident Project stage: Response to RAI ML0834303042008-12-0909 December 2008 Potential Schedule Impact Regarding Revision of Technical Specifications, Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Other ML0835101022008-12-19019 December 2008 Withdrawal of Questions Number 6 from Letter Dated October 28, 2008, Regarding Proposed Amendment to Revise Technical Specifications for Boron Requirements for the Cold Leg Accumulations and Refueling Water Storage Tank Project stage: Withdrawal ML0902202552008-12-31031 December 2008 Response to Request for Additional Information Emergency Core Cooling System Boron Requirements Project stage: Response to RAI ML0900900442008-12-31031 December 2008 Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle Project stage: Other ML0900600402009-01-26026 January 2009 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 Project stage: Withholding Request Acceptance ML0909205062009-05-0404 May 2009 Issuance of Amendment Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML1004703202010-02-0909 February 2010 Clarification Regarding the Number of Tritium Producing Burnable Absorber Rods in Operating Cycle 10 and Program Update Project stage: Other CNL-14-053, Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core2014-04-0808 April 2014 Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core Project stage: Other ML15030A5082015-01-30030 January 2015 Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System Project stage: Other 2008-10-14
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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
Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
_>7630 gallons and < 8000 gallons.
SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
_>610 psig and
- 660 psig SR 3.5.1.4 -------------------------- NOTE ------------------- 31 days The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) AND for each operating cycle.
--.------------------------------------------------ NOTE ---------
Only required to be Verify boron concentration in each accumulator is as performed for provided below depending on the number of tritium affected producing burnable absorber rods (TPBARs) installed accumulators.
in the reactor core for this operating cycle:
Once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution Number of TPBARs Boron Concentration Ranges volume increase of 0-400 > 3000 ppm and < 3300 ppm 75 gallons, that is not the result of addition from the refueling water storage tank.
(continued)
Watts Bar-Unit 1 3.5-2 Amendment 7, 21, 40, 48. 67
RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 ----------------------- NOTE ------------------
Only required to be performed when ambient air temperature is < 60'F or > 105'F.
Verify RWST borated water temperature is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
> 60°F and < 105'F.
SR 3.5.4.2 Verify RWST borated water volume is 7 days
> 370,000 gallons.
SR 3.5.4.3 ------------------------ NOTE ------------------
The number of TPBARs in the reactor core is contained in the Core Operating Limits Report (COLR) for each operating cycle.
Verify boron concentration in the RWST is as provided 7 days belowdepending on the number of tritium producing burnable absorber rods (TPBARs) installed in the reactor core for this operating cycle:
Number of TPBARS Boron Concentration Ranges 0-400 >3100 ppm and < 3300 ppm Watts Bar-Unit 1 3.5-10 Amendment 7, 40, 48, 67
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries shall be as shown in Figure 4.1-1.
4.1.2 Low Population Zone (LPZ)
The LPZ shall be as shown in Figure 4.1-2 (within the 3-mile circle).
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy or Zirlo fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. For Unit 1, Watts Bar is authorized to place a maximum of 400 Tritium Producing Burnable Absorber Rods into the reactor in an operating cycle. I 4.2.2 Control Rod Assemblies The reactor core shall contain 57 control rod assemblies. The control material shall be boron carbide with silver indium cadmium tips as approved by the NRC.
(continued)
Watts Bar Unit 1 4.0-1 Amendment 8, 40, 48, 67