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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20132B5771996-12-10010 December 1996 Proposed Tech Specs 3.13 Re Fire Protection Sys ML20129C4521996-10-17017 October 1996 Proposed Tech Specs,Revising Pages 89,89a & 90 to Incorporate Changes from Amends 148 & 149 ML20128N6031996-10-11011 October 1996 Proposed Tech Specs,Revising Existing Requirements Re Amount of Foam Concentrate Required to Support Operability of Recirculation Motor Generator Set Foam Sys in TS 3.13.G.1 & 3.13.G.2 1999-09-21
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20196A7851998-10-0909 October 1998 Rev 19 to Vynp IST Program Plan ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20237E9571998-08-27027 August 1998 Start-Up Test Rept Vynp Cycle 20 ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20149M7451997-01-24024 January 1997 Startup Test Rept,Vermont Yankee Cycle 19 1999-09-21
[Table view] |
Text
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-VYNPS'
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3.2-' LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE: REQUIREMENTS:
3.2 PROTECTIVE INSTRUNENT SYSTEMS 4.2 PROTECTIVE INSTRUMENT SYSTEMS J
i Specification (cont'd) Specification (cont'd) i I. Recirculation Pump Trio Instrumentation I. Recirculation Pum9 Trio Instrumentation
- During reactor power operation, the The Recirculation Pump Trip Instrumentation l Recirculation Pump Trip Instrumentation shall shall be functionally' tested and calibrated in accordance with Table 4.2.1.
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j be operative in accordance with Table 3.2.1.
4 J. Control Room Toxic Gas Monitoring J. Control Room Toxic Cas Monitoring L' Whenever the Control Room is required to be The Toxic Gas Monitoring System manned, the Toxic Gas Monitoring-System shall Instrumentation shall be calibrated in be operable in accordance with Table 3.2.7. accordance with-Table 4.2.7.
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34a Amendment No. 58
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8412260260 841214 PDR ADOCK 05000271 P , PDR _ _-
VYNPS TABLE 3.2.6 POST-ACCIDENT INSTRUMENTATION
, Minimum Number of Opscable Instrument Instrument Channels Parameter Type of Indication Range 2 Drywell Atmospheric Temperature Recorder #16-19 0-3000F (Note 1) Recorder #TR-1-149 0-3000F 2 Containment Pressure (Note 1) Meter 16-19-29A 0-275 psia Meter 16-19-29B 0-275 psia
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1 Torus Pressure (Note 1) Recorder #16-19-44 0-80 psia 2 Torus Water Level (Note 3) Meter #16-19-10A 0-20 ft.
Meter #16-19-10B 0-20 ft.
2 Torus Water Temperature (Note 1) Meter #16-19-48 60-1800 F 2 Reactor Pressure (Note 1) Meter #PI-2-3-56A 0-1500 psig Meter #PI-2-3-56B 0-1500 psig 2 Reactor Vessel Water Level Meter #2-3-91A (-150)-0-(+150)"H 2O (Note 1) Meter #2-3-91B (-150)-0-(+150)"H 2O 1 Control Rod Position (Notes 1,2) Meter 0-48" RPIS 1 Neutron Monitor (Notes 1,2) Meter 0-125% Rated flux 1 Torus Air Temperature (Note 1) Recorder #TR-16-19-45 0-3000F 2/ valve Safety / Relief Valve Position Lights (SRV 2-71-A thru D) Closed - Open From Pressure Switches (Note 4) ,
49 Amendment No. 63
Fi . E..
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VYNPS TABLE 3.2.6 POST-ACCIDENT INSTRUMENTATION (continued)
Minimum Number of Op r:ble Instrument Instrument Channels Parameter Type of Indication- Range 1/ valve Safety Valve Position From Meter 21-2-1A/B Closed - Open Acoustic Monitor (Note 5) 2 Containment Hydrogen /0xygen Meter SR-VG-6A 0-30% hydrogen Monitor (Note 1) Meter SR-VG-6B 0-25% oxygen 2 Containment High-Range Radiation Meter RM-16 1 R/he-10 7 R/hr Monitor (Hote 6) 1A/B Amendment No. 63 49a
vrEFs -
TABLE 3.2.6~
POST-ACCIDENT INSTRUNENTATION (continued)
TABLE 3.2.6 NOTES Note 1-FromandafterthedatethataparameterisnotindicatedintheControlRoom,continuedreactoroperationis-l.
' permissible during the next seven. days. If reduced to one indication of a parameter operation is permissible-for 30 days.
Cote 2 - Control rod position and neutron _ monitor instruments are considered to be redundant to each other. "
Cote 3 - From and after the date that this parameter is reduced to one indication in the Control Room.-continued j
, reactor operation is permissible during the next 30 days. If both channels are inoperable and indication l cannot be restored in six hours, an orderly shutdown shall be initiated and the reactor shall be in a" hot shutdown condition in six hours and a cold shutdown condition in the following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
l Cote 4 - From and after the date that safety / relief valve positi from pressure switches is unavailable, reactor .
I operation may continue provided safety / relief valve po M. ion can be determined from recorder 2-166 !
l (thermocouple. 0-6000F) and meter 16-19-48 (torus waL. temperature, 60-1800 F). If both indications are l not available, the reactor shall be in a hot shutdown condition in six hours and a cold shutdown condition in. .;
j the following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
i Note 5 - From and after the date that safety valve position from the acoustic monitor is unavailable, reactor l operation may continue provided safety valve position can be determined from recorder 2-166 (thersocouple, !
I 0-6000 F and Metee 16-19-29A or B (containment pressure 0-275 psia). If both indications are not available, !
the reactor shall be in a hot shutdown condition in six hours and in a cold shutdown condition in the l t
- following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Cote 6 - Within 30 days following the loss of one indication, or 7 days following the loss of both indications,-
i restore the inoperable channel (s) to an operable status or a special report to the Commission pursuant to
! Specification 6.7 aust be prepared and submitted within the subsequent 14 days, outlining the action taken, ,
the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
{
Amendment No. 63 49b ~l I
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'VYNPS .
TABLE 3.2.7 T0XIC CAS MONITORING SYSTEM Minimum Number of Required Action When Miniaana Operable Instrument Trip Conditions of Operations Are Not Channels Function Settina Satisfied 2 Initiate emergency Chlorine i S ppm Note 1 Control Room breathing Ammonia s 75 ppa sic Vinyl Chloride 1 800 ppm Carbon Dioxide s 800 ppa Methanol 1 300 ppa Note 1 - Within 30 days following the loss of one indication, or 7 days following the loss of both indications, restore the inoperable channel (s) to an operable status or a special report to the Connaission pursuant to l
Specification 6.7 naast be prepared and submitted within the subsequent 14 days, outlining the action taken, the cause of the inoperability, and the plans and schedula for restoring the system to operable status.
49C Amendment No. 63 ,
VYMPS TABLE 4.2.6 CALIBitATION REQUIRENINTS POST-ACCIDENT INSTRUNENTATION i
l l Parameter Calibration Instnament Check Drywell Atmosphere Temperature Every 6 months Once each day-.
C:ntainment Pressure Once/ Operating Cycle Once each day Tarua Pressure Every 6 months Once each day T:rus Water Level once/ Operating cycle once each day Tsrus Water Temperature Every 6 months Once each day Racetor Pressure Once/ Operating Cycle .Once each day R cctor Vessel Water Level Once/ Operating Cycle Once each day C:ntrol Rod Position (Note 5) Once each day Neutron Monitor Same as Reactor Protection Once each day Systems Terus Air Temperature Every 6 months Once each day Safsty/ Relief Valve Position Every refueling outage (Note 9) Once each day (a Functional Test to be performed quarterly)
SOfsty Valve Position Every refueling outage (Note 9) Once each day (a Functional Test to be performed quarterly) .
Amendment No. 63 60
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9 VYNPS TABLE 4.2.6 CAT.TBRATION REQUIREIENTS POST-ACCIDENT INSTRUNENTATION (Cont)
Earameter Calibration Instrument Check Containment Hydrogen /0xygen Monitor Once/ Operating Cycle Once each day Centainment High-Range. Radiation Monitor Once/ Operating Cycle Once each day-i Amendment No. 60s
- $ d: 64 .;
VYNPS TABLE 4.2.7 T0XIC GAS MONITORING SYSTEM - CALIBRATION REOUIREMENTS Parameter Calibration Instrument Check T xic Cas Monitoring System Once/ Operating Cycle Once each day Amendment No.
61b
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VYNPS 3.2 (Continued) standby gas treatment system operation so that none of the activity released'during:the refueling accident-leave the Reactor Building via the normal ventilation stack but 'that all activity is processsed by the standby' gas.
treatment system. Trip settings for the monitors in the ventilation duct are based upoa initiation of the-normal ventilation isolation and standby gas treatment system operation at a radiation level equivalent to the maximum release rate of.0.08/E Ci/see given in. Specification 3.8.C.1.a. The monitoring ~ system in the plant stack represents a backup to this system to limit gross radioactivity releases to the environs,.
.The purpose of isolating the mechanical. vacuum pump'line is to limit release of radioactivity from the main condenser. During an accident, fission products would be transported from~the reactor through the main steam-line to the main condenser. The fission product radioactivity would be sensed by the main steam line radiation monitors which initiate isolation.
Post-accident instrumentation parameters for Containment Pressure. Torus Water Level, Containment' Hydrogen / Oxygen Monitor, and Containment High-Range Radiation Monitor, are redundant, environmentally and seismically qualified instruments provided to enhance the operators' ability to follow the course of an event.
The purpose of each of these instruments is to provide detection and measurement capability during and following an accident as required by NUREG-0737 by ensuring continuous on-scale indication of the following: containment pressure in the 0 to 275 psia range; torus water level in the O to 20 foot range (i.e., the bottom to 5 feet above the normal water level of the torus pool); containment hydrogen / oxygen concentrations-(0 to 30% hydrogen '
and 0 to 25% oxygen); and containment radiation in the 1 R/hr to 107 R/hr gasma. The Control Room Toxic Cas Monitor assures that the Control Room operators, Wherever required to be in the Control Room, will be adequately protected against the effects of an accidental release of toxic gases and that the plant can be safely. operated-or shut down under design basis accident conditions.
4.2 PROTECTIVE INSTRUMENTATION The protective instrumentation systems covered by this Specification are listed in Table 4.2. Most of these protective systems are composed of two or more independent and redundant subsystems which are combined in a dual-channel arrangement. Each of these subsystems contains an arrangement of electrical relays which operate to initiate the required system protective action.
The relays in a subsystem are actuated by a number of means, including manually-operated switches, ,
process-operated switches (sensors), bistable devices operated by analog sensor signals, timers, limit switches, and other relays. In most cases, final subsystem relay actuation is obtained by satisfying the. logic conditions ,
t established by a number of these relay contacts in a logic. array. When a subsystem is actuated, the final subsystem relay (s) can operate protective equipment, such as valves and puses, and can perform other protective
, actions, such as tripping the main turbine generator unit. +
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Amendment No 66 i ,
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VYMPS. .
I 4.2 (Continued) '
1 l With the dual-channel arrangement o'f these subsystems, tho' single failure of'a ready circuit-can be' tolerated i because the redundant subsystem or system (,in the case of high pressure coolant' injection) will then initiate j .the necessary protective action. If a failure in one of these circuits occurs in such a way that an action is l taken, the operator is inunediately alerted to the failure. If the failure occurs and causes no action, it could i then remain undetected, causing'a loss of the redundancy in the dual-channel arrangement. Losses in redundancy '
i of this nature are found by periodically testing the relay circuits in the subsystems to assure that they are j operating properly.
- It has been the practice in boiling water reactor plants to functionally test protective instrumentat' ion sensors d
and sensor. relays on-line on a monthly frequency. Since logic circuit tests result in the actuation of plant
. equipment, testing of this nature was done while the plant was shutdown for refueling. In this way, the testing of. equipment would not jeopardize plant operation. However, a refueling interval'could be as long as-eighteen l , months, which is too long a period to allow an undetected failure to exist.
j This specification is a periodic testing program which is based upon the overall on-line testing'of protective i
instrumentation systems,. including logic circuits,as well as sensor circuits. Table 4.2 outlined the test,.
calibration, and logic system functional test schedule for the protective instrumentation systems. The testing of a subsystem includes a functional test of each relay wherever practicable. .The testing of each relay l includes all circuitry necessary to make the relay operate, and also the proper functioning of the relay i contacts. Functicnal testing of the inaccessible temperature switches associated.with the isolation systems is i accomplished remotely by application of a heat source to individual switches.
i l All subsystems are functionally tested, calibrated, and operated in their entirety if practicable. Certain l
exceptions are necessary because the actuation of certain relays would jeopardize plant operation oc present an operational hardship.
I l
For example, certain relays trip recirculation system discharge valves, and the actuation of these' relays would
! cause a severe plant transient. In cases of this nature, the devices in the relay circuit will be tested, but- .
the relay will only be actuated during a refueling outage. The number of relays in this category is very small l
l compared to the total number of identical relays being tested on-line.
1 i Amendment No 67
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