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| : 1) Transmittal of TSTF-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No. | | : 1) Transmittal of TSTF-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No. |
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| ML033350006] | | ML033350006] |
| : 2) Federal Register Notice, Notice of Availability published on August 23, 2004 (69 FR 51864) | | : 2) Federal Register Notice, Notice of Availability published on August 23, 2004 (69 FR 51864) |
| : 3) Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450 - Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325] | | : 3) Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450 - Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325] |
| : 4) Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO) "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram | | : 4) Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO) "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram |
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| ==10.0 REFERENCES== | | ==10.0 REFERENCES== |
| : 1. Technical Specifications Task Force (TSTF)-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No. ML033350006] | | : 1. Technical Specifications Task Force (TSTF)-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No. ML033350006] |
| : 2. Federal Register Notice, Notice of Availability, published on August 23, 2004 (69 FR 51864) | | : 2. Federal Register Notice, Notice of Availability, published on August 23, 2004 (69 FR 51864) |
| : 3. NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric BWR/4 Plants," dated April 2012 [ADAMS Accession No. ML12104A192] | | : 3. NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric BWR/4 Plants," dated April 2012 [ADAMS Accession No. ML12104A192] |
| : 4. Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450, Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325] | | : 4. Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450, Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325] |
| : 5. Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram Time Testing Frequency (TS-450)," dated September 20, 2005 [ADAMS Accession No. ML052360292] | | : 5. Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram Time Testing Frequency (TS-450)," dated September 20, 2005 [ADAMS Accession No. ML052360292] |
| : 6. Letter from Eva A. Brown (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Units 2 and 3 - Issuance of Amendments Regarding Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency (TAC Nos. MC8037 and MC8038)," dated January 9, 2006 [ADAMS Accession No. ML060110296] | | : 6. Letter from Eva A. Brown (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Units 2 and 3 - Issuance of Amendments Regarding Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency (TAC Nos. MC8037 and MC8038)," dated January 9, 2006 [ADAMS Accession No. ML060110296] |
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TAC:MF5827, Control Rod SCRAM Time Testing Frequency (Approved, Closed) |
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Category:Letter type:CNL
MONTHYEARCNL-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 CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report 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 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel 2024-05-08
[Table view] Category:Technical Specifications
MONTHYEARML22348A0052023-01-25025 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 ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary 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) ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 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 ML20190A1052020-08-11011 August 2020 Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) 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-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe ML16330A1582017-01-17017 January 2017 Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality ML16028A4142016-04-26026 April 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15317A4782016-02-0909 February 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15344A3212016-01-0707 January 2016 Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits ML15321A4722015-12-23023 December 2015 Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation ML15287A2132015-12-16016 December 2015 Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits ML15324A2472015-12-14014 December 2015 Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control ML15287A3712015-12-0404 December 2015 Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029) ML15212A7962015-10-28028 October 2015 Issuance of Amendments to Transition to Fire Protection Program NFPA-805 ML15251A5402015-09-29029 September 2015 Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0 CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. ML15065A0492015-06-0202 June 2015 Issuance of Amendment Revising Pressure and Temperature Limit Curves CNL-15-070, Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-4852015-05-29029 May 2015 Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-485 CNL-15-019, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501) CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) CNL-15-033, License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use2015-02-12012 February 2015 License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use CNL-14-156, Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules2014-09-18018 September 2014 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules NL-14-081, Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Fer2014-05-16016 May 2014 Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferr CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry2014-05-16016 May 2014 Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-148, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-126, Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-4852013-11-22022 November 2013 Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-485 ML13199A2212013-08-30030 August 2013 Issuance of Amendments Re. Deletion of References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25% Extension of Surveillance Intervals ML13092A3932013-03-27027 March 2013 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) (Technical Specification Change TS-480) ML13070A3072013-02-28028 February 2013 Technical Specification Change TS-478 - Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, & 3, & Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 Xm Fuel ML11189A2172012-07-30030 July 2012 Issuance of Amendments Regarding Request to Add Technical Specification 3.7.3, Control Room Emergency Ventilation System, Action to Address Two Crev Subsystems Inoperable ML12114A0042012-04-18018 April 2012 Supplement to License Amendment Request to Transition to Areva Fuel ML1011601532010-04-16016 April 2010 Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request ML0923700452009-11-19019 November 2009 Issuance of Amendments Regarding Technical Specification Improvement to Adopt Technical Specification Task Force (TSTF) TSTF-476, Revision 1 ML0931001212009-10-31031 October 2009 Attachment 19, Browns Ferry Unit 1 -Technical Specification Change 467, ANP-2638NP, Revision 2, Applicability of Areva Np BWR Methods to Extend Power Uprate Conditions ML0931402652009-10-31031 October 2009 Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis Report 2023-01-25
[Table view] |
Text
TennesseeValleyAuthority ,1101MarketStreet,Chattanooga,Tennessee37402
CNL-15-019
March 9, 2015
10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency" (TS-501)
References:
- 1) Transmittal of TSTF-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No.
ML033350006]
- 2) Federal Register Notice, Notice of Availability published on August 23, 2004 (69 FR 51864)
- 3) Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450 - Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325]
- 4) Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO) "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram
Time Testing Frequency (TS-450)," dated September 20, 2005 [ADAMS Accession No. ML052360292]
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 50.90, "Application for amendment of license, construction permit, or early site permit," Tennessee Valley Authority (TVA) is submitting a request for an amendment to the Technical Specifications (TS) for Browns Ferry Nuclear Plant (BFN) Unit 1.
U. S. Nuclear Regulatory Commission CNL-15-019
Page 2 March 9, 2015
The proposed license amendment revises the TS testing frequency for the surveillance
requirement (SR) in TS 3.1.4, "Control Rod Scram Times."
The proposed change is consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency" (Reference 1), which was approved generically for the boiling water reactor (BWR) Standard TS, NUREG-1433 (BWR/4). The required frequency of SR 3.1.4.2, control rod scram time testing, is changed from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."
The availability of this TS improvement was announced in the Federal Register on August 23, 2004 (69 FR 51864) (Reference 2) as part of the consolidated line item improvement process (CLIIP).
TVA previously submitted a similar License Amendment Request (LAR) for BFN Unit 1 as part of a joint BFN Units 1, 2, and 3 Application for TS Change (TS-450) on July 29, 2005 (Reference 3). The NRC Acceptance Review Results for BFN Unit 1 (Reference 4) noted that, given the shutdown of BFN Unit 1 since 1985, with scheduled return to service in 2007, "the information presented for Unit 1 does not support review of this request under the CLIIP, as no actual plant-specific data for Unit 1 was provided."
This letter resubmits that application for a BFN Unit 1 TS change with plant-specific data as
required by TSTF-460-A.
Enclosure 1 of this letter provides the description, proposed change, technical analysis, regulatory analysis, and a discussion of environmental considerations. The attachments to the provide the existing facility operating license pages and Bases marked to show the proposed change (Attachments 1 and 2) and revised (final typed) pages (Attachments 3 and 4).
In accordance with 10 CFR 50.91(a) (1), "Notice for Public Comment," the analysis about the issue of no significant hazards consideration using the standards in 10 CFR 50.92 is being provided to the Commission in the regulatory analysis section of the Enclosure 1.
In accordance with 10 CFR 50.91(b) (1), "Notice for Public Comment; State Consultation," a copy of this application and its reasoned analysis about no significant hazards considerations is being provided to the Alabama Department of Public Health.
TVA requests review and approval of the proposed license amendment by September 30, 2015 and requests the implementation date be specified as within 60 days of the approval date.
There is one new regulatory commitment associated with this submittal.
Please direct any questions concerning this matter to Mr. Edward D. Schrull at (423) 751-3850.
Evaluation of Proposed Change Browns Ferry Nuclear Plant Unit 1 Application to Adopt TSTF-460-A, "Control Rod Scram Time Testing Frequency" (TS-501) 1.0
SUMMARY
DESCRIPTION
2.0 DETAILED
DESCRIPTION
2.1 Proposed
Changes
2.2 Need for Proposed Changes
3.0 BACKGROUND
4.0 REGULATORY
REQUIREMENTS AND GUIDANCE
5.0 TECHNICAL ANALYSIS
6.0 COMMITMENTS
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION
8.0 ENVIRONMENTAL
EVALUATION
9.0 PRECEDENT
10.0 REFERENCES
Evaluation of Proposed Change E 1 of 3 1.0
SUMMARY
DESCRIPTION The proposed change revises the required testing frequency for the surveillance requirement (SR) in Technical Specifications (TS) 3.1.4, "Control Rod Scram Times," from 120 days cumulative operation in MODE 1 to 200 days cumulative operation in MODE 1. This change is consistent with U.S. Nuclear Regulatory Commission (NRC) approved Technical Specifications Task Force (TSTF) Standard Technical Specific ations (STS) Change Traveler TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency" (Reference 1). The availability of this TS improvement was announced in the Federal Register on August 23, 2004, (69 FR 51854) (Reference 2) as part of the consolidated line item improvement process (CLIIP).
This proposed change will update TS 3.1.4 to be consistent with NUREG-1433, Revision 4 (Reference 3).
2.0 DETAILED
DESCRIPTION 2.1 Proposed Changes The proposed change revises TS 3.1.4, "Control Rod Scram Times," based on TSTF Change Traveler TSTF-460-A, Revision 0, that has been approved generically for the boiling water reactor (BWR) Standard TS, NUREG-1433 (BWR/4). The required frequency of SR 3.1.4.2, control rod scram time testing, is changed from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1." The 200 day frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle.
Revisions to the TS Bases are also included in this application for information, as shown in Attachments 2 and 4 to this enclosure. The Bases are revised to reference the new frequency and to reduce the percentage of the tested rods which can be "slow" from 20% to 7.5%.
2.2 Need for Proposed Changes The proposed change will restore BFN Unit 1 consistency with BFN Units 2 and 3 TS and BWR/4 Standard TS, NUREG-1433 Rev. 4.
The Tennessee Valley Authority (TVA) previously submitted a similar License Amendment Request (LAR) for BFN Unit 1 as part of a joint BFN Units 1, 2, and 3 Application for TS Change
TS-450 on July 29, 2005 (Reference 4), "Application for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency." The NRC Acceptance Review for BFN Unit 1 (Reference 5) noted that, given the shutdown status of BFN Unit 1 since 1985, with scheduled return to service not until 2007, "the information presented for Unit 1 does not support review of this request under the CLIIP, as no actual plant-specific data for Unit 1 was provided."
The LAR TS-450 was subsequently approved for implementation for BFN Units 2 and 3 on January 9, 2006 (Reference 6).
This LAR (TS-501) resubmits that Control Rod Scram Time Testing Frequency amendment request for BFN Unit 1 with plant-specific data as required by TSTF-460-A.
Evaluation of Proposed Change E 2 of 3
3.0 BACKGROUND
The background for this application is addressed by the CLIIP Notice of Availability published on August 23, 2004 (69 FR 51854) and TSTF-460-A, Rev. 0.
4.0 REGULATORY
REQUIREMENTS AND GUIDANCE
The applicable regulatory requirements and guidance associated with this application are addressed by the CLIIP Notice of Availability published on August 23, 2004 (69 FR 51864) and TSTF-460-A, Rev.0.
5.0 TECHNICAL ANALYSIS
TVA has reviewed the safety evaluation (SE) published on August 23, 2004 (69 FR 51854) as part of the CLIIP Notice of Availability. This verification included a review of the NRC staff's SE and the supporting information provided to support TSTF-460-A. TVA has concluded that the justifications presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to BFN Unit 1 and justify this amendment for the incorporation of the changes to the
BFN Unit 1 TS.
As described in the CLIIP model SE, part of the justification for the change in surveillance frequency is the high reliability of the BFN Unit 1 control rod drive system. As requested in the notice of availability published on August 23, 2004 (69 FR 51854), the historical performance of the control rod drive system at BFN Unit 1 is as follows:
The control rod insertion time test results at BFN Unit 1 have shown the control rod scram rates to be highly reliable with scram rates that do not significantly change over an operating cycle. During the most recent eight years of operation, out of 2,475 control rod insertion tests, only one control rod has been slower than the insertion time limit.
The extensive historical database substantiates the claim of high reliability of the BFN Unit 1 control rod drive system. The current TS requires that 10 percent of the BFN Unit 1 control rods, or 19 rods, be tested via sampling every 120 cumulative days of operation in MODE 1.
6.0 COMMITMENTS
As discussed in the CLIIP model SE published in the Federal Register on August 23, 2004 (69 FR 51854) for this TS improvement, TVA is making the following regulatory commitment with the understanding that the NRC will include it as a condition for the issuance of the requested amendment:
TVA will incorporate the revised acceptance criterion value of 7.5 percent into the TS Bases for BFN Unit 1 in accordance with the Bases Control Program described in TS 5.5.10.
Evaluation of Proposed Change E 3 of 3 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION The Tennessee Valley Authority (TVA) has reviewed the proposed no significant hazards consideration determination published on August 23, 2004, (69 FR 51854) as part of the CLIIP. TVA has concluded that the proposed determination presented in the notice is applicable to BFN Unit 1 and the determination is hereby incorporated by reference to satisfy the
requirements of 10 CFR 50.91(a).
8.0 ENVIRONMENTAL
EVALUATION
TVA has reviewed the environmental evaluation included in the model SE published on August 23, 2004 (69 FR 51854) as part of the CLIIP. TVA has concluded that the staff's findings presented in that evaluation are applicable to BFN Unit 1 and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT
This application is being made in accordance with the CLIIP. TVA is not proposing variations or deviations from the TS changes described in TSTF-460-A or the NRC staff's model SE published on August 23, 2004 (69 FR 51854).
10.0 REFERENCES
- 1. Technical Specifications Task Force (TSTF)-460, Revision 0, "Control Rod Scram Time Testing Frequency," dated September 17, 2003 [ADAMS Accession No. ML033350006]
- 2. Federal Register Notice, Notice of Availability, published on August 23, 2004 (69 FR 51864)
- 3. NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric BWR/4 Plants," dated April 2012 [ADAMS Accession No. ML12104A192]
- 4. Letter from William D. Crouch (TVA) to the U.S. Nuclear Regulatory Commission, "Browns Ferry Nuclear Plant - Units 1, 2, and 3 - Technical Specifications Change 450, Application for Technical Specification Improvement to Revise Control of Scram Time Testing Frequency," dated July 29, 2005 [ADAMS Accession No. ML052220325]
- 5. Letter from Michael L. Marshall, Jr (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Unit 1 - Acceptance Review Results of License Amendment Request Regarding Revision to Control Rod Scram Time Testing Frequency (TS-450)," dated September 20, 2005 [ADAMS Accession No. ML052360292]
- 6. Letter from Eva A. Brown (NRC) to Karl W. Singer (TVA CNO), "Browns Ferry Nuclear Plant, Units 2 and 3 - Issuance of Amendments Regarding Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency (TAC Nos. MC8037 and MC8038)," dated January 9, 2006 [ADAMS Accession No. ML060110296]
ATTACHMENT 1 Marked up Proposed Technical Specification Pages
ATTACHMENT 2 Marked up Proposed Technical Specification Bases Pages
Control Rod Scram Times B 3.1.4 (continued)
BFN-UNIT 1 B 3.1-31 Revision 0, 9 , Amendment No. 239 November 21, 2000 BASES SURVEILLANCE SR 3.1.4.2 REQUIREMENTS (continued) Additional testing of a sample of control rods is required to verify the continued performance of t he scram function during the cycle. A representative sample contains at least 10% of the control rods. This sample remains representative if no more
than 20% of the control rods in the sample tested are
determined to be "slow." With more than 20% of the sample
declared to be "slow" per the criter ia in Table 3.1.4-1, additional control rods are tested until this 20% criterion (i.e., 20% of the entire sample) is satisfied, or until the total number of "slow" control rods (throughout the core from all Surveillances)
exceeds the LCO limit. For planned testing, the control rods
selected for the sample should be different for each test. Data
from inadvertent scrams shoul d be used whenever possible to avoid unnecessary testing at power, even if the control rods with
data may have been previously tested in a sample. The
120 day Frequency is based on operating experience that has
shown control rod scram times do not significantly change over
an operating cycle. This Frequency is also reasonable based
on the additional Surveillances done on the CRDs at more
frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."
ATTACHMENT 3 Final Typed Revised Technical Specification Pages
BFN-UNIT 1 Renewed License No. DPR-33 Amendment No. 000 (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in
amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal. (2) Technical Specifications
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. , are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.
Control Rod Scram Times 3.1.4 BFN-UNIT 1 3.1-13 Am endment No. 234, 239, 000 SURVEILLANCE REQUIREMENTS -----------------------------------------------------NOTE-------------------------------------------
During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator. ------------------------------------
SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each cont rol rod scram time is within the limits of Table 3.1.
4-1 with reactor steam dome pressure 800 psig.
Prior to exceeding
40% RTP after
each reactor
shutdown 120 days SR 3.1.4.2 Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure 800 psig.
200 days cumulative operation in
MODE 1 (continued)
ATTACHMENT 4 Final Typed Revised Technical Specification Bases Pages
Control Rod Scram Times B 3.1.4 (continued)
BFN-UNIT 1 B 3.1-31 Revision 0, 9 Amendment No. 239, 000 BASES SURVEILLANCE SR 3.1.4.2 REQUIREMENTS (continued) Additional testing of a sample of control rods is required to verify the continued performance of t he scram function during the cycle. A representative sample contains at least 10% of the
control rods. This sample remains representative if no more
than 7.5% of the c ontrol rods in the sample tested are determined to be "slow." With more than 7.5% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional
control rods are tested until this 7.5% criterion (i.e., 7.5% of the entire sample) is satisfied, or until the total number of "slow" control rods (throughout the co re from all Surveillances) exceeds the LCO limit. For plann ed testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power , even if the control rods with data may have been previously tested in a sample. The
200 day Frequency is based on oper ating experience that has shown control rod scram times do not significantly change over
an operating cycle. This Frequen cy is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."
Enclosure 2 License Amendment Request for Adoption of TSTF-460-A, Control Rod Scram Time Testing Frequency (TS-501) Regulatory Commitment COMMITMENT COMPLETION DATE
TVA will incorporate the revised acceptance criterion value of 7.5 percent into the TS Bases for BFN Unit 1 in accordance with the Bases Control Program described in TS 5.5.10.
Sixty days following issuance of the License Amendment approving the TS-501 request to adopt TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency"