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| {{#Wiki_filter:Entergy Nuclear Operations, Inc.m Vermont Yankee P.O. Box 0250 320 Governor Hunt Road En Vernon, VT 05354 Tel 802 257 7711 November 17, 2008 BVY 08-081 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 | | {{#Wiki_filter:m Entergy Nuclear Operations, Inc. |
| | Vermont Yankee P.O. Box 0250 En 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 November 17, 2008 BVY 08-081 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 |
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| ==Subject:== | | ==Subject:== |
| Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)Revision of Technical Specification Bases Page 29 | | Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) |
| | Revision of Technical Specification Bases Page 29 |
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| ==Dear Sir or Madam,== | | ==Dear Sir or Madam,== |
| This letter provides revised Technical Specification (TS) Bases page. TS Bases page 29 was revised to recognize an additional condition under which the APRMs may be bypassed provided the minimum number of operable channels is maintained. | | |
| The additional information is consistent with Vermont Yankee's licensing basis.This change to the TS Bases was processed in accordance with the TS Bases Control Program specified in TS 6.7.E and has been determined to not require a license amendment in accordance with 10CFR50.59. | | This letter provides revised Technical Specification (TS) Bases page. TS Bases page 29 was revised to recognize an additional condition under which the APRMs may be bypassed provided the minimum number of operable channels is maintained. The additional information is consistent with Vermont Yankee's licensing basis. |
| Therefore, prior NRC approval is not required.A revised TS Bases page is attached for your records. No NRC action is requested on this submittal. | | This change to the TS Bases was processed in accordance with the TS Bases Control Program specified in TS 6.7.E and has been determined to not require a license amendment in accordance with 10CFR50.59. Therefore, prior NRC approval is not required. |
| | A revised TS Bases page is attached for your records. No NRC action is requested on this submittal. |
| There are no new regulatory commitments being made in this submittal. | | There are no new regulatory commitments being made in this submittal. |
| If you have any questions concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.Sincerely, Michael J\.,oomUb Site Vice President Vermont Yankee Nuclear Power Station | | If you have any questions concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304. |
| | Sincerely, Michael J\.,oomUb Site Vice President Vermont Yankee Nuclear Power Station |
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| ==Attachment:== | | ==Attachment:== |
| | Revised Technical Specification Bases Page cc list (next page) |
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| Revised Technical Specification Bases Page cc list (next page)
| | BVY 08-081 Docket 50-271 Page 2 of 2 cc: Mr. Samuel J. Collins, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601 |
| BVY 08-081 Docket 50-271 Page 2 of 2 cc: Mr. Samuel J. Collins, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601 BVY 08-081 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specification Bases Page VYNPS BASES: 3.1 Reactor Protection System The reactor protection system automatically initiates a reactor scram to: 1. preserve the integrity of the fuel barrier;2. preserve the integrity of the primary system barrier; and 3. minimize the energy which must be absorbed, and prevent criticality following a loss of coolant accident.This specification provides the limiting conditions for operation necessary to preserve the ability *of the system to tolerate single failures and still perform its intended function even during periods when instrument channels may be out of service because of maintenance, testing, or calibration. | | |
| The basis for the allowable out-of-service times is provided in GE Topical Report NEDC-308512-A, "Technical Specification Improvement Analysis for BWR Reactor Protection System," March 1988.The reactor protection system is of the dual channel type. The system is made up of two independent logic channels, each having three subsystems of tripping devices. One of the three subsystems has inputs from the manual scram push buttons and the reactor mode switch. Each of the two remaining subsystems has an input from at least one independent sensor monitoring each of the critical parameters. | | BVY 08-081 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specification Bases Page |
| The outputs of these subsystems are combined in a 1 out 'of 2 logic; i.e., an input signal on either one or both of the subsystems.will cause a trip system trip. The outputs of the trip systems are arranged so that a t-rip on both logic channels is required to produce a reactor scram.The required conditions when the minimum instrument logic conditions are not met are chosen so as to bring station operation promptly to such a condition that the particular protection instrument is not required; or the station is placed in the protection or safe condition that the instrument initiates. | | |
| This is accomplished in a normal manner without subjecting the plant to abnormal operating conditions. | | VYNPS BASES: |
| When the minimum requirements for the number of operable or operating trip system and instrumentation channels are satisfied, the effectiveness of the protection system is preserved; i.e., the system can tolerate a single failure and still perform its intended function of scramming the reactor.Three APRM instrument channels are provided for each protection trip system to provide ,for high neutron flux protection. | | 3.1 Reactor Protection System The reactor protection system automatically initiates a reactor scram to: |
| APRM's A and E operate contacts in a trip subsystem, and APRM's C an E operate contacts in the other trip subsystem. | | : 1. preserve the integrity of the fuel barrier; |
| APRM's B, D, and F are arranged similarly in the other protection trip system. Each protection trip system has one more APRM than is necessary to meet the minimum number required. | | : 2. preserve the integrity of the primary system barrier; and |
| This allows the bypassing of one APRM per protection trip system for maintenance, testing, calibration, or to minimize single failure vulnerabilities associated with shared LPRMs, while maintaining the minimum number of channels required for inputs to each trip system. Operating with two APRMs bypassed meets all design and technical specification requirements. | | : 3. minimize the energy which must be absorbed, and prevent criticality following a loss of coolant accident. |
| Additional IRM channels have also been provided to allow bypassing of one such channel. For a description of the Neutron Monitoring Systems, see FSAR Section 7.5.The bases for the scram settings for the IRM, APRM, high reactor pressure, reactor low water level, turbine control valve fast closure, and turbine stop valve closure are discussed in Specification 2.1.Amendment No. 24, -+-4, 44-4, B, BVY 08-081 29}} | | This specification provides the limiting conditions for operation necessary to preserve the ability *of the system to tolerate single failures and still perform its intended function even during periods when instrument channels may be out of service because of maintenance, testing, or calibration. The basis for the allowable out-of-service times is provided in GE Topical Report NEDC-308512-A, "Technical Specification Improvement Analysis for BWR Reactor Protection System," March 1988. |
| | The reactor protection system is of the dual channel type. The system is made up of two independent logic channels, each having three subsystems of tripping devices. One of the three subsystems has inputs from the manual scram push buttons and the reactor mode switch. Each of the two remaining subsystems has an input from at least one independent sensor monitoring each of the critical parameters. The outputs of these subsystems are combined in a 1 out 'of 2 logic; i.e., an input signal on either one or both of the subsystems.will cause a trip system trip. The outputs of the trip systems are arranged so that a t-rip on both logic channels is required to produce a reactor scram. |
| | The required conditions when the minimum instrument logic conditions are not met are chosen so as to bring station operation promptly to such a condition that the particular protection instrument is not required; or the station is placed in the protection or safe condition that the instrument initiates. This is accomplished in a normal manner without subjecting the plant to abnormal operating conditions. |
| | When the minimum requirements for the number of operable or operating trip system and instrumentation channels are satisfied, the effectiveness of the protection system is preserved; i.e., the system can tolerate a single failure and still perform its intended function of scramming the reactor. |
| | Three APRM instrument channels are provided for each protection trip system to provide ,for high neutron flux protection. APRM's A and E operate contacts in a trip subsystem, and APRM's C an E operate contacts in the other trip subsystem. APRM's B, D, and F are arranged similarly in the other protection trip system. Each protection trip system has one more APRM than is necessary to meet the minimum number required. This allows the bypassing of one APRM per protection trip system for maintenance, testing, calibration, or to minimize single failure vulnerabilities associated with shared LPRMs, while maintaining the minimum number of channels required for inputs to each trip system. Operating with two APRMs bypassed meets all design and technical specification requirements. |
| | Additional IRM channels have also been provided to allow bypassing of one such channel. For a description of the Neutron Monitoring Systems, see FSAR Section 7.5. |
| | The bases for the scram settings for the IRM, APRM, high reactor pressure, reactor low water level, turbine control valve fast closure, and turbine stop valve closure are discussed in Specification 2.1. |
| | Amendment No. 24, -+-4, 44-4, B, BVY 08-081 29}} |
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Category:Letter type:BVY
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024 Nuclear Onsite Property Damage Insurance BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023 Proof of Financial Protection BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023 Update to 2022 Radiological Effluent Release Report BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023 Update to Nuclear Onsite Property Damage Insurance BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023 Report of Investigation Pursuant to 1O CFR 20, Appendix G BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating Report BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-012, Pre-Notice of Disbursement from Decommissioning Trust2023-05-0202 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-009, 2022 Individual Monitoring NRC Form 5 Report2023-04-24024 April 2023 2022 Individual Monitoring NRC Form 5 Report BVY 23-008, Pre-Notice of Disbursement from Decommissioning Trust2023-04-0606 April 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-006, Status of Decommissioning and Spent Fuel Management Fund for Year Ending 20222023-03-29029 March 2023 Status of Decommissioning and Spent Fuel Management Fund for Year Ending 2022 BVY 23-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-03-29029 March 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-005, Nuclear Onsite Property Damage Insurance2023-03-13013 March 2023 Nuclear Onsite Property Damage Insurance BVY 23-004, Pre-Notice of Disbursement from Decommissioning Trust2023-03-0202 March 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-003, Pre-Notice of Disbursement from Decommissioning Trust2023-01-31031 January 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-030, Documentary Evidence of Performance Bond2022-12-30030 December 2022 Documentary Evidence of Performance Bond BVY 22-028, Re Proof of Financial Protection2022-11-28028 November 2022 Re Proof of Financial Protection BVY 22-027, Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station2022-11-11011 November 2022 Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station BVY 22-026, Pre-Notice of Disbursement from Decommissioning Trust2022-10-31031 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022 Notification of Revised Decommissioning Cost Estimate BVY 22-018, Pre-Notice of Disbursement from Decommissioning Trust2022-06-0808 June 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-015, 2021 Radiological Environmental Operating Report2022-05-0505 May 2022 2021 Radiological Environmental Operating Report BVY 22-017, Pre-Notice of Disbursement from Decommissioning Trust2022-05-0505 May 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-014, 2021 Radiological Effluent Release Report2022-04-28028 April 2022 2021 Radiological Effluent Release Report BVY 22-012, Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d)2022-04-12012 April 2022 Biennial Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) BVY 22-011, Pre-Notice of Disbursement from Decommissioning Trust2022-04-0404 April 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-009, Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 20212022-03-23023 March 2022 Status of Decommissioning and Spent Fuel Management Fund for the Year Ending 2021 BVY 22-008, Pre-Notice of Disbursement from Decommissioning Trust2022-02-24024 February 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-005, ISFSI Decommissioning Funding Plan2022-02-24024 February 2022 ISFSI Decommissioning Funding Plan 2024-01-04
[Table view] Category:Technical Specification
MONTHYEARBVY 15-055, Revision of Technical Specifications Bases Pages2015-11-16016 November 2015 Revision of Technical Specifications Bases Pages BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 BVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 32014-06-11011 June 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 13-084, Revision of Technical Specification Bases Page2013-09-0909 September 2013 Revision of Technical Specification Bases Page BVY 13-053, Revision of Technical Specifications Bases Pages2013-07-24024 July 2013 Revision of Technical Specifications Bases Pages BVY 13-062, Revised of Technical Specification Bases Pages2013-06-26026 June 2013 Revised of Technical Specification Bases Pages BVY 13-043, Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit2013-05-14014 May 2013 Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit BVY 13-023, License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 22013-04-29029 April 2013 License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 2 BVY 13-022, Revision of Technical Specification Bases Pages2013-03-26026 March 2013 Revision of Technical Specification Bases Pages BVY 12-078, Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information2012-11-20020 November 2012 Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information2012-08-0707 August 2012 Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-068, Revision of Technical Specification Bases Pages Due to License Amendment 2482011-09-30030 September 2011 Revision of Technical Specification Bases Pages Due to License Amendment 248 BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves2011-05-16016 May 2011 Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves BVY 11-037, Revision of Technical Specification Bases Pages Due to License Amendment 2462011-04-21021 April 2011 Revision of Technical Specification Bases Pages Due to License Amendment 246 BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool2010-11-0808 November 2010 Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool BVY 10-056, Submittal of Revision of Technical Specification Bases Pages2010-10-0606 October 2010 Submittal of Revision of Technical Specification Bases Pages BVY 10-047, Revision of Technical Specifications Bases Page2010-08-18018 August 2010 Revision of Technical Specifications Bases Page BVY 10-027, Revision of Technical Specification Bases Pages2010-05-21021 May 2010 Revision of Technical Specification Bases Pages BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes2010-04-13013 April 2010 Technical Specifications Proposed Change No. 290 Administrative Changes BVY 10-021, Revision of Technical Specification Bases Pages2010-03-31031 March 2010 Revision of Technical Specification Bases Pages BVY 09-074, Revision of Technical Specifications Bases Pages2009-12-0909 December 2009 Revision of Technical Specifications Bases Pages BVY 09-072, Technical Specification Bases Pages Associated with License Amendment 2362009-12-0909 December 2009 Technical Specification Bases Pages Associated with License Amendment 236 BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-055, Revision of Technical Specifications Bases Page2009-09-28028 September 2009 Revision of Technical Specifications Bases Page BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves2009-09-16016 September 2009 Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls2009-08-26026 August 2009 Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls BVY 09-044, Revision of Technical Specifications Bases Pages2009-07-28028 July 2009 Revision of Technical Specifications Bases Pages BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test2009-05-0505 May 2009 Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test BVY 09-021, Submittal of Revision of Technical Specification Bases Pages2009-03-31031 March 2009 Submittal of Revision of Technical Specification Bases Pages BVY 09-014, Submittal of Revised Technical Specification Bases Pages2009-02-24024 February 2009 Submittal of Revised Technical Specification Bases Pages BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements2009-02-24024 February 2009 Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements ML0836500072008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 62008-12-18018 December 2008 Vermont Yankee Nuclear Power Station, Response to Request for Additional Information on Technical Specifications Proposed Change No. 273, Supplement 6 BVY 08-087, Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations2008-12-18018 December 2008 Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations BVY 08-081, Submittal of Revision of Technical Specification Bases Page 292008-11-17017 November 2008 Submittal of Revision of Technical Specification Bases Page 29 BVY 08-076, Revision of Technical Specification Bases Pages2008-10-14014 October 2008 Revision of Technical Specification Bases Pages BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications2008-09-22022 September 2008 Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications BVY 08-069, Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems2008-09-22022 September 2008 Transmittal of Technical Specifications Proposed Change No. 281, Revision to Battery Systems BVY 08-066, Submittal of Corrected Technical Specification Page2008-08-26026 August 2008 Submittal of Corrected Technical Specification Page BVY 08-060, Submittal of Revision of Technical Specification Bases Page 2202008-08-25025 August 2008 Submittal of Revision of Technical Specification Bases Page 220 BVY 08-046, Revision of Technical Specification Bases Page 972008-07-28028 July 2008 Revision of Technical Specification Bases Page 97 BVY 08-031, Revision of Technical Specification Bases Page2008-05-29029 May 2008 Revision of Technical Specification Bases Page BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications2008-02-12012 February 2008 Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications 2015-03-25
[Table view] Category:Bases Change
MONTHYEARBVY 15-055, Revision of Technical Specifications Bases Pages2015-11-16016 November 2015 Revision of Technical Specifications Bases Pages BVY 15-024, Revision of Technical Specifications Bases Pages2015-03-25025 March 2015 Revision of Technical Specifications Bases Pages ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14202A2062014-07-16016 July 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 2 ML13323A5182013-11-14014 November 2013 Technical Specifications Proposed Change No. 306 Eliminate Certain ESF Requirements During Movement of Irradiated Fuel BVY 13-084, Revision of Technical Specification Bases Page2013-09-0909 September 2013 Revision of Technical Specification Bases Page BVY 13-053, Revision of Technical Specifications Bases Pages2013-07-24024 July 2013 Revision of Technical Specifications Bases Pages BVY 13-062, Revised of Technical Specification Bases Pages2013-06-26026 June 2013 Revised of Technical Specification Bases Pages BVY 13-043, Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit2013-05-14014 May 2013 Technical Specifications Proposed Change No. 304, Revision to Low Pressure Safety Limit BVY 13-023, License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 22013-04-29029 April 2013 License Amendment Request; Changes to 10 CFR 50.63 Licensing Basis, Supplement 2 BVY 13-022, Revision of Technical Specification Bases Pages2013-03-26026 March 2013 Revision of Technical Specification Bases Pages BVY 12-078, Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information2012-11-20020 November 2012 Technical Specifications Proposed Change 297, Supplement 2 Response to Request for Additional Information BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information2012-08-0707 August 2012 Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change2012-04-17017 April 2012 Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change BVY 12-006, Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance2012-02-0101 February 2012 Technical Specifications Proposed Change No. 298, Rod Worth Minimizer Bypass Allowance BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-068, Revision of Technical Specification Bases Pages Due to License Amendment 2482011-09-30030 September 2011 Revision of Technical Specification Bases Pages Due to License Amendment 248 BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves2011-05-16016 May 2011 Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves BVY 11-037, Revision of Technical Specification Bases Pages Due to License Amendment 2462011-04-21021 April 2011 Revision of Technical Specification Bases Pages Due to License Amendment 246 BVY 10-056, Submittal of Revision of Technical Specification Bases Pages2010-10-0606 October 2010 Submittal of Revision of Technical Specification Bases Pages BVY 10-047, Revision of Technical Specifications Bases Page2010-08-18018 August 2010 Revision of Technical Specifications Bases Page BVY 10-027, Revision of Technical Specification Bases Pages2010-05-21021 May 2010 Revision of Technical Specification Bases Pages BVY 10-017, Technical Specifications Proposed Change No. 290 Administrative Changes2010-04-13013 April 2010 Technical Specifications Proposed Change No. 290 Administrative Changes BVY 10-021, Revision of Technical Specification Bases Pages2010-03-31031 March 2010 Revision of Technical Specification Bases Pages BVY 09-072, Technical Specification Bases Pages Associated with License Amendment 2362009-12-0909 December 2009 Technical Specification Bases Pages Associated with License Amendment 236 BVY 09-074, Revision of Technical Specifications Bases Pages2009-12-0909 December 2009 Revision of Technical Specifications Bases Pages BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves BVY 09-055, Revision of Technical 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Extended Power Uprate - Risk Analysis of Containment Overpressure BVY 05-074, Transmittal of Vermont Yankee Technical Specification Proposed Change No. 263 - Supplement No. 31 Extended Power Uprate - Response for Additional Information2005-08-0404 August 2005 Transmittal of Vermont Yankee Technical Specification Proposed Change No. 263 - Supplement No. 31 Extended Power Uprate - Response for Additional Information BVY 05-072, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 30 Extended Power Uprate - Response to Request for Additional Information2005-08-0101 August 2005 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 30 Extended Power Uprate - Response to Request for Additional Information ML0511902932005-04-22022 April 2005 Response to Request for Additional Information - Technical Specification Proposed Change No. 268. One- Time Integrated Leak Rate Test (ILRT) . One-time Integrated Leak Rate Test (ILRT) Interval Extension 2015-03-25
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m Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0250 En 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 November 17, 2008 BVY 08-081 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Revision of Technical Specification Bases Page 29
Dear Sir or Madam,
This letter provides revised Technical Specification (TS) Bases page. TS Bases page 29 was revised to recognize an additional condition under which the APRMs may be bypassed provided the minimum number of operable channels is maintained. The additional information is consistent with Vermont Yankee's licensing basis.
This change to the TS Bases was processed in accordance with the TS Bases Control Program specified in TS 6.7.E and has been determined to not require a license amendment in accordance with 10CFR50.59. Therefore, prior NRC approval is not required.
A revised TS Bases page is attached for your records. No NRC action is requested on this submittal.
There are no new regulatory commitments being made in this submittal.
If you have any questions concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.
Sincerely, Michael J\.,oomUb Site Vice President Vermont Yankee Nuclear Power Station
Attachment:
Revised Technical Specification Bases Page cc list (next page)
BVY 08-081 Docket 50-271 Page 2 of 2 cc: Mr. Samuel J. Collins, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601
BVY 08-081 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specification Bases Page
VYNPS BASES:
3.1 Reactor Protection System The reactor protection system automatically initiates a reactor scram to:
- 1. preserve the integrity of the fuel barrier;
- 2. preserve the integrity of the primary system barrier; and
- 3. minimize the energy which must be absorbed, and prevent criticality following a loss of coolant accident.
This specification provides the limiting conditions for operation necessary to preserve the ability *of the system to tolerate single failures and still perform its intended function even during periods when instrument channels may be out of service because of maintenance, testing, or calibration. The basis for the allowable out-of-service times is provided in GE Topical Report NEDC-308512-A, "Technical Specification Improvement Analysis for BWR Reactor Protection System," March 1988.
The reactor protection system is of the dual channel type. The system is made up of two independent logic channels, each having three subsystems of tripping devices. One of the three subsystems has inputs from the manual scram push buttons and the reactor mode switch. Each of the two remaining subsystems has an input from at least one independent sensor monitoring each of the critical parameters. The outputs of these subsystems are combined in a 1 out 'of 2 logic; i.e., an input signal on either one or both of the subsystems.will cause a trip system trip. The outputs of the trip systems are arranged so that a t-rip on both logic channels is required to produce a reactor scram.
The required conditions when the minimum instrument logic conditions are not met are chosen so as to bring station operation promptly to such a condition that the particular protection instrument is not required; or the station is placed in the protection or safe condition that the instrument initiates. This is accomplished in a normal manner without subjecting the plant to abnormal operating conditions.
When the minimum requirements for the number of operable or operating trip system and instrumentation channels are satisfied, the effectiveness of the protection system is preserved; i.e., the system can tolerate a single failure and still perform its intended function of scramming the reactor.
Three APRM instrument channels are provided for each protection trip system to provide ,for high neutron flux protection. APRM's A and E operate contacts in a trip subsystem, and APRM's C an E operate contacts in the other trip subsystem. APRM's B, D, and F are arranged similarly in the other protection trip system. Each protection trip system has one more APRM than is necessary to meet the minimum number required. This allows the bypassing of one APRM per protection trip system for maintenance, testing, calibration, or to minimize single failure vulnerabilities associated with shared LPRMs, while maintaining the minimum number of channels required for inputs to each trip system. Operating with two APRMs bypassed meets all design and technical specification requirements.
Additional IRM channels have also been provided to allow bypassing of one such channel. For a description of the Neutron Monitoring Systems, see FSAR Section 7.5.
The bases for the scram settings for the IRM, APRM, high reactor pressure, reactor low water level, turbine control valve fast closure, and turbine stop valve closure are discussed in Specification 2.1.
Amendment No. 24, -+-4, 44-4, B, BVY 08-081 29