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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 TABLE 3.2.1 ,
EMERGENCY CORE COOLING SYSTEM AC1UATION INSTRUMCfTATION Core Spray - A & B (Note 1)
Minimum Number of Required Action When operable Instrument Minimum Conditions Channels per Trip for operation System Trio Function Trio Level Settina are Not satisfied 2 High Drywell Pressure 1 2 5 psig Note 2 2 ,
Low-Low Reactor vessel Water __82.5*
> above top of Note 2 Level enriched fuel 1 Low Reactor Pressure 300 1 P 5 350 psig Note 2 l (PT-2-3-56C/D(H))
2 Low Reactor Pressure 300 1 P 5 350 psig Note 2 l
(PT-2-3-56A/B(H) & 52C/D(H))
1 (14A-K16A & B) onds he.pij Note 2 2 - Fu=y (E-so-1A/B) Discharge >100 psig Note 5 Pressure Auxiliary Power Monitor -- Note $ t 1
Note 5 I 1 Pump Bus Power Monitor --
Trip System Logic -- Note 5 1
I 9911090071 981102~
PDR ADOCK 05000271 P PDR t ja Anendment No. 44, 68, 449, 441,144,M2
VYNPS TABLE 3.2.1 ~
(Cont'd)
D4EROENCY CORE COOLitK2 SYSTEM ACWATION INSTRUMENTATIotl Low Pressure Coolant Injection System A & B (Note ~1)
Required Action When Hinimum Number of Minimum conditions Operable Instrument. for Operation Channele per Trip are Not Satisfied System Trio Function Trio Level Settina 300 g p g 350 peig Note 2 1- Low Reactor Pressure l
. (PT-2-3-56C/D(H))
$ 2.5 peig Note 2 2 High Drywell Pressure (PT-10-101A-D(H)) .
182.5" above top of Note 2 2 Low-Low Reactor vessel Water enriched fuel Level M Delay (10A-K51A & J 0 seconds [ [ Note 5 Note 5 1 Reactor Vessel Shroud Level 12/3 core height Note 5 1 Time Delhy (10A-K72A,p B) 560 seconds 3 $ (, f f Note 5 1 '! == h (10A-K50A & B) haeconde " Note"2-n==u Pressure 100 g p 5 150 psig 1
(PS-2-128A & B) Note 5 RHR Pump A & C Discharge A100 peig 2 per pump Pressuro ' Note 2 High Drywell Pressure $ 2.5 psig
r Amendment flo. H , 44. 68, He,
I l
1 l
VYNPS l
Egg, 3 . 5. (Cont'd) n e Degraded Grid Protective System has been installed be to assure thatsubjected to sustaine safety-related electrical equipment will notThis systemthe incorporates voltage relays on 41 degraded voltage. minimum voltage Dnergency Buses 3 and 4 which damage areety-related of saf set to actuate at equipment. l required to prevent for 10 seconds, eitherBased relayupon willan If Degraded Grid conditions exist l actuate an alarm to alert operators of this condition.of these conditions the ope disconnect the off-site power. In addition, if an ESP signal is for assessment initiated in conjunction with low voltage below the relay seepoint 10 seconds, the off-site power will be automatically disconnected.
The Reactor Core Isolation Cooling (RCIC) System provides makeup water to or replace the reactor vessel during shutdown and isolation to supplementthe use of the Emergency C of a the normal makeup sources withoutThe RCIC Reactor System is initiated vessel highautomatically water upon rece Systems.
reactor vessel low-low water level signal. However, the system level signal results in shutdown of the RCIC System. reactor vessel low-low water level signal.
on a subsequent will restart suction from the condensate We RCIC System is normally lined up to takeSuetion will automatically switch over from t tank storage storage tank. tank to the suppression pool on low condensate storage level.
Upon receipt of a LOCA initiation signal, if normal AC power is available, all RHR pumps both Core Spray pumps start simultaneously with no intentional time delay. If normal AC power is not available, RHR pumps A and D start immediately on restoration of power, RHR pumps B and C start within 3 to 5 seconds of restoration of power and both Core Spray pumps start within 8 to 10 seconds of restoration of power. The purpose of these time delays is to stagger the star the RHR and Core Spray pumps on the associated Division I and Division 2 Buses, thus limiting i
the starting transients on the 4.16 kV emergency buses. De time delay functions are only necessary when power is being supplied from the standby power sources (EDGs). The time delays remain in the pump start logic at all times as the time delay relay contact is in pa the Auxiliary Power Monitor relay contact. Either contact closure will initiate pump start. Thus, the time delays do not affect low pressure ECCS pump operation with normal AC power j available. With normal AC power not available, the pump start relays which would have started the B and C RHR pumps and both Core Spray pumps are blocked by the Auxiliary Power Monitor contacts and the pump start time delay relays become the controlling devices.
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l l
1
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79 Amendment No. 94, 111 1 f
VERMONT YANKEE NUCLEAR POWER CORPORATION Docket No.50-27i BV'Y 98 18 .
, Page 1 of 1 '
ATTACHMENT 4 Revised New Technical Specification Paaae 1
1 i
1
'41 I l'
I l
t
~~ -
g p3 TABLE 3.2.1 .
~
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTAT*ON- ,
i
.i Core Spray - A & B (Note 1) [
Minimum Number of Required Action When }
Operable Instrument Minimum Conditions ;
Channels per Trip . for Operation .!
System Trip Function Trip Level Setting are Not Satisfied !
2 High Drywell Pressure $2.5 psig- Note 2 [
2 Low-Low Reactor Vessel Water >82.5" above top of Note 2 .
Level enriched fuel j 1 Low Reactor Pressure 300 $ P $ 350 psig. . Note 2 I (PT-2-3-56C/D(M)) f 2 Low Reactor Pressure 300 $ P $ 350 psig Note 2 (PT-2-3-56A/B(M) & 52C/D(M))
l 1 Pump Start Time Delay 8 $ t $ 10 seconds Note 2 (14A-K16A & B) 2 . Pump (P-46-1A/B) Discharge >100 psig- Note 5 I Pressure i L
1 . Auxiliary Power Monitor --
Note 5 {,
1 Pump Bus Power Monitor --
Note 5 [
2 Trip System Logic --
Note 5 :
5 i
~r 4 i i
?
i Amendment No. 44, 68, . 4-14, 4M, 444, -142- 38 [
i !
l b
VYNPS TABLE a.2.1 (Cont'd) ,
EMERGENCY CORE COOLING SYSTE.M ACTUATION INSTRUMENTATION Low Pressure Coolant Injection System A & B (Note'1)-
Minimum Number of Required Action When -[
Operable Instrument Minimum conditions .
. Channels per Trip for Operation System Trip Function Trip Level Setting are Not Satisfied !
1 Low Reactor Pressure 300 $ p $ 350 psig Note 2.
(PT-2-3-56C/D(Mi) 1 2 High Drywell Pressure $2.5 psig Note 2 (PT-10-101A-D(M))
2 Low-Low Reactor Vessel Water 282.5" above top of Note 2 Level enriched fuel 1 Reactor Vessel Shroud Level 22/3 core height Note 5 1 Time Delay (10A-K72A & B) <60 secands Note 5 1 Pump-Start Time Delay 3 $ t 3 5 seconds Note 5
~
l (10A-K50A & B) 1 Low Reactor Pressure 100 $ p 5 150 psig Note 2 (PS-2-128A & B) 2 per pump RHR Pump A & C Discharge 2100 psig Note 5 Pressure 2 High Drywell Pressure $2.5 psig Note 2 (PT-10-101A-D(S1))
Amendment No. 44, 44, 68, 444, 44e 39 i
VYNPS BASES: ' 3.2~ (Cont'd)
The Degraded Grid Protective System has been installed to assure that safety-related electrical equipment will not be subjected to sustained degraded voltage. This system incorporates voltage relays on 4160 Volt Emergency Buses 3 and 4 which are set to actuate at the minimum voltage required to prevent damage of safety-related equipment.
If Degraded Grid conditions exist for 10 seconds, either relay will actuate an alarm to alert operators of this condition. Based upon an assessment of these conditions the operator may choose to manually disconnect the off-site power.
In addition, if an ESF signal is initiated in conjunction with low voltage below the relay setpoint for 10 seconds, the off-site power will be automatically disconnected.
The Reactor Core Isolation Cooling (RCIC) System provides makeup water to the ]
reactor vessel during shutdown and isolation to supplement or replace the normal '
makeup sources without the use of the Emergency Core Cooling Systems. The RCIC j System is initiated automatically upon receipt of a reactor vessel low-low we.cer l level signal. Reactor vessel high water level signal results in shutdown of the l RCIC System. However, the system will restart on a subsequent reactor vessel low-low water level signal. The RCIC System is normally lined up to take
' suction from the condensate storage tank. Suction will automatically switch over from the condensate storage tank to the suppression pool on low condensate storage tank level.
Upon receipt of a LOCA initiation signal, if normal AC power is available, all )
RHR pumps and both Core Spray pumps start simultaneously with no intentional !
time delay. If normal AC power is not available, RHR pumps A and D start l immediately on restoration of power, RHR pumps B and C start within 3 to 5 seconds of restoration of power and boch Core Spray pumps statt within 8 to 10 seconds of restoration of power. The purpose of these time delays is to stagger ;
the start of the RHR and Core Spray pumps on the associated Division 1 and 1 Division 2 Buses, thus limiting the starting transients on the 4.16 kV emergency buses. The time delay functions are only necessary when power is being supplied from the standby power sources (EDGs). The time delays remain in the pump start logic at all times as the time delay relay contact is in parallel with the I Auxiliary Power Monitor relay contact. Either contact closure will initiate pump start. Thus, the time delays do not affect low pressure ECCS pump operation with normal AC power available. With normal AC power not available, the pump start relays which would have started the B and C RHR pumps and both Core Spray pumps are blocked by the Auxiliary Power Monitor contacts and the pump start time delay relays become the controlling devices.
l Amendment No. M, 4M 79