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Category:Technical Specifications
MONTHYEARML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18347B3592019-01-11011 January 2019 12-13-18-License Transfer Conforming Amendment Markup ML18253A2022018-10-11011 October 2018 Conforming License Amendment Approval of License Transfer Request(License DPR-28, Docket 50-271 and 72-59) ML18156A1812018-08-15015 August 2018 ISFSI Only Tech Spec Amendment Package ML16014A1692016-03-14014 March 2016 Vermont Yankee Nuclear Power Station - Issuance of Amendment No. 265 to Renewed Facility Operating License Re: Cyber Security Plan Implementation Schedule (CAC No. MF6403) ML15117A5512015-10-0707 October 2015 Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML14304A5882015-02-12012 February 2015 Issuance of Amendment No. 261, Revise Technical Specifications to Eliminate Certain Requirements During Movement of Irradiated Fuel and Core Alterations Consistent with TSTF-51 ML14346A0652015-02-0404 February 2015 Issuance of Amendment No. 261, Revise Site Emergency Plan for Permanently Defueled Condition to Reflect Change in On-Shift Staffing and Emergency Response Staffing ML14217A0722014-12-22022 December 2014 Issuance of Amendment No. 260, Revise and Remove Certain Requirements from Technical Specification Section 6.0, Administrative Controls, No Longer Applicable for Its Permanently Defueled Condition BVY 14-083, Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 32014-12-0505 December 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 3 ML13212A2012013-08-15015 August 2013 Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout BVY 12-085, Technical Specifications Proposed Change No. 302 Inoperable Control Rods2012-12-17017 December 2012 Technical Specifications Proposed Change No. 302 Inoperable Control Rods CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 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 11-069, Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation2011-09-29029 September 2011 Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure2010-08-19019 August 2010 Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure 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 ML0917400402009-07-13013 July 2009 License Amendment, Relocation of Reactor Building Crane Technical Specification BVY 09-035, Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages2009-05-20020 May 2009 Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages ML0901206582009-02-11011 February 2009 Issuance of Amendment Battery Systems BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information2008-12-18018 December 2008 Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information BVY 08-075, Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 22008-12-15015 December 2008 Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 2 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 08-062, Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information2008-09-15015 September 2008 Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information BVY 08-053, Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary2008-09-0404 September 2008 Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary BVY 08-047, Technical Specification Proposed Change No. 276, Response to Request for Additional Information2008-07-29029 July 2008 Technical Specification Proposed Change No. 276, Response to Request for Additional Information ML0817601182008-06-23023 June 2008 Technical Specifications, Amendments to Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0811201212008-04-17017 April 2008 Technical Specifications, Amendment No. 231 ML0806602032008-02-12012 February 2008 Vermont Yankee, Technical Specifications Proposed Change No. 273, Instrumentation Technical Specifications BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System2008-02-0606 February 2008 Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System BVY 07-056, Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements2007-10-18018 October 2007 Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements BVY 07-063, Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits2007-10-18018 October 2007 Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0708607332007-03-26026 March 2007 Technical Specifications, Modify Requirements for Inoperable Snubbers by Relocating the Current TS Requirements Limiting Condition for Operation (LCO) 3.6.1 and Surveillance Requirement (SR) 4.6.1 ML0629103402006-08-28028 August 2006 Correction to Technical Specification Page 255 Amendment No. 226 BVY 06-067, Correction to Technical Specification Page2006-07-27027 July 2006 Correction to Technical Specification Page ML0603901072006-03-0202 March 2006 Vermont Yankee, Tech Spec Pages for Amendment 229 Regarding Extended Power Uprate BVY 06-018, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages2006-02-22022 February 2006 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages ML0604101192006-02-0303 February 2006 2006/02/03-Vermont Yankee - Technical Specification Proposed Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Potential Adverse Flow Effects BVY 05-105, Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages2005-12-12012 December 2005 Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages ML0526400902005-09-20020 September 2005 Technical Specifications, Drywell Spray Header and Nozzle Air Test Frequency BVY 05-083, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information2005-09-10010 September 2005 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information ML0522800592005-08-15015 August 2005 Tech Spec Pages for Amendment 226 Administrative Changes ML0519202762005-07-0707 July 2005 Tech Spec Pages for Amendment 225 Regarding Extend Intermediate Range Monitor Surveillance Test Frequencies ML0519202462005-06-30030 June 2005 Attachment 1 - Response to Request for Additional Information - Instrumentation Technical Specifications, Vermont Nuclear Power Station, Technical Specifications BVY 05-032, Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies2005-03-31031 March 2005 Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies ML0509003992005-03-29029 March 2005 Technical Specification Pages Re Alternative Source Term ML0508004322005-03-16016 March 2005 TS Pages for Amendment 221 to License DPR-28, Relocating Current Definition of Surveillance Frequency to New Technical Specification (TS) Sections 4.0.2 and 4.0.3 and Revises Requirements for Missed Surveillance in TS Section 4.0.3 ML0435102452004-12-14014 December 2004 Technical Specification Pages, Elimination of Requirements for Hydrogen/Oxygen Monitors ML0514500312004-06-0909 June 2004 E-Mail from R. Ennis of USNRC to Various, Regarding State of Vermont Comments on EPU and AST ML0411202522004-04-14014 April 2004 Technical Specification Pages for Vermont Yankee Nuclear Power Station, License Amendment, Issuance of Amendment Implementation of Arts/Mellla 2019-09-11
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VYNPS TABLE 4.1.1 SCRAM INSTRUMENTATION AND LOGIC SYSTEMS FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENTATION, LOGIC SYSTEMS AND CONTROL.CIRCUITS Instrument Channel Group 3) Functional Test(7) Minimum Frequency(4)
Mode Switch in Shutdown A Place Mode Switch in Shutdown Each Refueling Outage Manual Scram A Trip Channel and Alarm Every 3 Months IRM High Flux( 10 ) C Trip Channel and Alarm( 5 ) Within 31 Days Before Entering 1
STARTUP/HOT STANDBY"') and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling Inoperative C Trip Channel and Alarm Within 31 Days Before Entering STARTUP/HOT STANDBY"') and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling APRM High Flux B Trip Output Relays(5) Every 3 Months High Flux (Reduced) B Before Each Startup & Weekly Trip Output Relays{ 5 )
During Refueling(6 )
Inoperative B Trip Output Relays Every 3 Months Flow Bias B Trip Output Relays(s) Every 3 Months High Reactor Pressure B Trip Channel and Alarm(5) Every 3 Months High Drywell Pressure B Trip Channel and Alarm(5) Every 3 Months 2 8 Low Reactor Water Level( )( ) B Trip Channel and Alarm(5) Every 3. Months High Water Level in Scram Discharge B Trip Channel and Alarm(5) Every 3 Months Volume Main Steam Line Iso. Valve Closure A Trip Channel and Alarm Every 3 Months Turbine Con. Valve Fast Closure A Trip Channel and Alarm Every 3 Months Turbine Stop Valve Closure A Trip Channel and Alarm Every 3 Months Scram Test Switch (5A-S2(A-D)) A Trip Channel and Alarm Once each week (9)
First Stage Turbine Pressure - A Trip Channel and Alarm Every 6 Months Permissive (PS-5-14(A-D))
Amendment No. 44, G4E, 5, -s, 4-64, 486, GE4 , 225 25
VYNPS TABLE 4.1.1 NOTES
- 1. Not used
- 2. An instrument check shall be performed on reactor water level and reactor pressure instrumentation once per day.
- 3. A description of the three groups is included in the basis of this Specification.
- 4. Functional tests are not required when the systems are not required to be operable or are tripped. If tests are missed, they shall be performed prior to returning the systems to an operable status.
- 5. This instrumentation is exempted from the Instrument Functional Test Definition (1.G.). This Instrument Functional Test will consist of injecting a simulated electrical signal into the measurement channels.
- 6. Frequency need not exceed weekly.
- 7. A functional test of the logic of each channel is performed as indicated.
This coupled with placing the mode switch in shutdown each refueling outage constitutes a logic system functional test of the scram system.
- 8. The water level in the reactor vessel will be perturbed and the corresponding level indicator changes will be monitored. This test will be performed every month.
- 9. The automatic scram contactors shall be exercised once every week by either using the RPS channel test switches or performing a functional test of any automatic scram function. If the contactors are exercised using a functional test of a scram function, the weekly test using the RPS channel test switch is considered satisfied. The automatic scram contactors shall also be exercised after maintenance on the contactors.
- 10. When the IRM-High Flux trip function is required to be operable, an instrument check shall be performed on IRM instrumentation once per day.
- 11. Not required to be performed when entering STARTUP/HOT STANDBY MODE from RUN MODE until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering STARTUP/HOT STANDBY MODE.
Amendment No. GE, G-&, 4-8-, G, 225 26
VYNPS TABLE 4.1.2 SCRAM INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Group (1) Calibration Standard(4) Minimum Frequency(2)
High Flux IRM C Standard Voltage Source Once/Operating Cycle I Output Signal(7)(10) (1)
High Flux APRM Output Signal B Heat Balance Once Every 7 Days Output Signal (Reduced) (7) B Heat Balance Once Every 7 Days Flow Bias B Standard Pressure and Voltage Refueling Outage Source LPRM (LPRM ND-2-1-104(80)) BC5 ) Using TIP System Every 2,000 MWD/T average core exposure (8)
High Reactor Pressure B Standard Pressure Source Once/Operating Cycle Turbine Control Valve Fast Closure A Standard Pressure Source Every 3 Months High Drywell Pressure B Standard Pressure Source Once/Operating Cycle High Water Level in Scram Discharge B Water Level Once/Operating Cycle Volume Low Reactor Water Level B Standard Pressure Source Once/Operating Cycle Turbine Stop Valve Closure A (6) Refueling Outage First Stage Turbine Pressure A Pressure Source Every 6 Months and After Permissive (PS-5-14(A-D)) Refueling Main Steam Line Isolation Valve A (6) Refueling Outage Closure Amendment No. 44, G4, As, i-, 64, 7-6,4-64, 46, 49-L, 214, 225 27
VYNPS TABLE 4.1.2 NOTES
- 1. A description of the three groups is included in the bases of this Specification.
- 2. Calibration tests are not required when the systems are not required to be operable or are tripped. If tests are missed, they shall be performed prior to returning the systems to an operable status.
- 3. Deleted.
- 4. Response time is not part of the routine instrument check and calibration, but will be checked every operating cycle.
- 5. Does not provide scram function.
- 6. Physical inspection and actuation.
- 7. The IRM and SRM channels shall be determined to overlap during each startup after entering the STARTUP/HOT STANDBY MODE and the IRM and APRM channels shall be determined to overlap during each controlled shutdown, if not performed within the previous 7 days.
- 8. The specified frequency is met if the calibration is performed within 1.25 times the interval specified, as measured from the previous performance.
- 9. APRM trip unit calibration only.
- 10. Neutron detectors are excluded.
- 11. Not required to be performed when entering STARTUP/HOT STANDBY MODE from RUN MODE until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering STARTUP/HOT STANDBY MODE.
Amendment No. Q4., 4-8, 4-91, 24-, 24-9, 225 28
VYNPS BASES: 4.1 (Cont'd)
The calibration of the APRM High Flux Flow Bias trip units provides a check of the actual trip setpoints. If the trip setting is found to be less conservative than accounted for in the appropriate setpoint calculation, but is not beyond the Allowable Value specified in Table 3.1.1, the channel performance is still within the requirements of the plant safety analysis. However, if the trip setting is found to be less conservative than the Allowable Value specified in Table 3.1.1, the channel should be declared inoperable. Under these conditions, the setpoint should be readjusted to be equal to or more conservative than accounted for in the appropriate setpoint calculation. The specified trip unit calibration frequency (i.e., every 3 months) is consistent with the assumptions of the VYNPS setpoint methodology and the reliability analysis of NEDC-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System," March 1988.
IRM surveillance requirements are modified by Note 11 to Table 4.1.1 and Note 11 to Table 4.1.2 for functional and calibration testing, respectively. These Notes allow functional testing and calibration of IRM instrument channels to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering the STARTUP/HOT STANDBY MODE from the RUN MODE. This allowance is necessary since testing of IRM instrument channels cannot be performed in the RUN MODE without utilizing jumpers, lifted leads, or movable links. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period is considered to provide reasonable time to complete testing.
The IRM calibration requirements are modified by Note 10 to Table 4.1.2 to exclude neutron detectors from calibration of the IRM - High Flux instrument channels. This is acceptable because the neutron detectors are passive devices with minimal drift, and because of the difficulty of simulating a meaningful signal.
LPRM gain settings are determined from the local flux profiles measured by the Traversing Incore Probe (TIP) System. This establishes the relative local flux profile for appropriate representative input to the APRM System. The 2,000 megawatt-days per short ton (MWD/T) frequency is based on operating experience with LPRM sensitivity changes, and that the resulting nodal power uncertainty, combined with other identified uncertainties, remains less than the total uncertainty (i.e., 8.7%) allowed by the GETAB safety limit analysis.
Amendment No. 4G, 4, 4-9-1, 2414,225 33a