|
---|
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
-_
.VYNPS .
3.10 LIMITING CONDITIONS FOR OPERATION' 4.'10 SURVEILLANCE HEQUIREMENTS
- 3. Emergency Buses' 3. Emerrency Buses The emergency 4160 volt Buses 3 and 4..and The emergency 4160 volt buses'and 480 volt 480 volt Buses 8 and 9 shall be energized'and buses shall be checked daily. ,
operable. .
- 4. Off-Site Power 4. Off-Site Power
- a. At least one off-site transmission line The status of the off-site power sources and at least one start-up transformer in shall be checked daily, service. ,
- b. One of the following additional sources of delayed access power:
The main stepup transformer and unit auxiliary transformer available and capable of supplying power to the emergency 4160 volt buses or, The 4160 volt tie line to Vernon flydro-Electric Station capable of supplying power to either of the two emergency 4160 volt buses.
5, 480 V Uninterruptible Power Systems S. 480 V Uninterruptible Power Systems Both 480 V Uninterruptible Power Systems a. The requirements of Specifications (UPS-1A, UPS-1B) and their respective Motor 4.lO.A.2(a) and (b) shall be satisfied Control Centers (89A, 89B) shall be energized for each 480 V Uninterruptible Power and operable. System battery bank.
- b. Each Uninterruptible Power System
- 850'.1210346 850304 performance discharge test every 5 years.
PDR ADOCK 05000271 P PDR l Amendment No.-26 1/S e
i.
t VCPS ,
~.
3.10 1.IMITING CONDITIONS FOR OPERATION 4.10 SURVEl!.t.ANCE REQUIREMENTS
- c. Each 480 V Uninterrupt.ible Power System shall be checked daily,
- d. 480 V Motor Control Centers 89A and 89B shall be checked daily.
- c. Once per operating cycle, the actual cotiditions under which the 480 V Uninterruptible Power Systems are required will be simulated and a test conducted to demonstrate equipment performance.
> i 6. Reactor Protection System Power Protection 6. Reactor Protection System Power Protection l
,' Two RPS power protection panels for each Once per operating cycle, the operability of 1 inservice RPS MG set or alternate power each overvoltage, undervoltage, and l source shall be operable. underfrequency protective device shall be i demonstrated by the performance of an instrument channel calibration test.
Settings shall be verified tc be in accorde.nce with Table 4.10.1.
I ll$a {
=
~'
VYNPS .
3.10 LIMITING CONDITIO*fS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS
- 3. Off-Site Power 3. Off-Site Power
- a. From and after the date that both startup a. When it is determined that one of the transformers and one diesel generator or diesel generators or associated-buses is associated buses-ete made or found to be inoperable, the requirements of inoperable for any reason, reactor operation Specification 4.5.H.1 shall be satisfied.
may continue provided the requirements of Specification 3.5.H.1 are satisfied.
- b. From ano after the date that both b. When it is determined that both delayed delayed-access of f-site power sources become access off-site power sources are: ,
unavailable, reactor operation may continue unavailable, both diesel generators, for seven days provided both emergency diesel associated buses and all low pressure generators, associated buses, and all low core and containment cooling systems pressure core and containment cooling systems shall be demonstrated to be operaole are operable, inunediately and daily thereaf ter.
- 4. 480 V Uninterruptible Power Systems 4. 480 V Uninterruptible Power System From and after the date that one When it is determined that one -
Uninterruptible Power System or its Uninterruptible Power System or its associated Motor Control Center are made or associat,ed Motor Control Center is found to be inoperable for any reason, the inoperable, the requirements of. Specification requirements of Specification 3.5.A.4 shall 4.5.A.4 shall be satisfied, be satistied.
- 5. RPS Protection System Power Protection From and after the date that one or more of th RPS power protection panels on an inservice RPS MG set or an alternate power
- source is made or found to be inoperable, the
.i panel shall be restored to operable status j within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the panel cannot be
- restored to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, j it shall be tripped.
Amendment No. 26 Ill w __ _ _ _ _ _ .
e VYKPS ,
3.10 LIMITING CONDITIONS FOR OPERATION 4.10 ' SURVEILLANCE REQUIREMENTS C. Diesel Puel C. Diesel Fuel There shall be a minimum of 25,000 1. The quantity of diesel generator usable gallons of diesel fuel in the fuel shall be logged weekly and diesel fuel oil storage tank. atter each operation of the unit.
- 2. Once a month a sample of diesel fuel shall be taken and checked for quality. The quality shall be within the applicable limits specified on Table I of ASTM D915-68 and logged.
_. q f
R VYNPS Tabte 4.10._1 ~
Reactor Protection System Power Protection Setyoint Parameter Panel A1 A2, Bl a_BJ, Panel C1 and_C2 Overvoltage 1 125.5 volts 1 125.5 volts Overvoltage Time Delay s 0.35 seconds s 4 seconds Undervoltage 1 111 volts 2 111 volts Undervoltage Time Delay 1 0.35 seconds 1 4.0 seconds Underfrequency 2 56.5 Hz g 56.5 Itz Underf requency Time , 31ay 1 0.35 seconds s 0.35 seconds 177b
O
.' VYMPS
. AUXILIARY FLECTRIC POWER SYSTEMS LA.
The objective of this Specification is to assure that adequate power will be available to operate the emergency safeguards equipment. Adequate power can be provided by any one of the following sources: either of the startup transformers, backfeed through the main transformer, the 4160 volt line f rom the Vernon liydroelectric Station or either of the two diesel generators. The backf eed through the nwin transformer and 4160 volt Vernon - ~
line are both delayed access off-site power sources, Backfeeding through the main transformer can be accomplished by disconnecting the main generator from the main transformer and energizing the auxiliary transformer from the 345 kV switchyard through the main transformer. The thre required to perform this disconnectioni is approximately six hours. The 4160 volt line f rom the Vernon Ilydroelectric Station can be connected to either of the two emergency buses within seconds by simple manual switching operation in the Main Control Room.
Two 480 V Uninterruptible Power Systems, each consisting of a battery bank, battery charger, and a sold state inverter, supply power to the LPCIS valves via designated Motor Control Centers. The 480 V Unin;crruptible Power Systems are redundant and independent of any on- site power sources.
This Specification assures that at least two off-site and two on-site power sources, and both 480 V Uninterruptible Power Systems will be available before the reactor is taken beyond "just critical" testing. In addition to assuring power source availability, all of the associated switchgear must be operable as specified to assure that the emergency cooling equipment can be operated, if required, from the power sources.
Station service power is supplied to the stat ion through either the unit auxiliary transformer or the startup transformers. In order to start up the station, at least one startup transformer is required to supply the station auxiliary load. After the unit is synchronized to the system, the unit auxiliary transformer carries the station auxiliary load, except for the station cooling tower loads which are always supplied by one of the startup transformers. The station cooling tower loads are not required to perform an engineered safety feature function in the event of an accident; therefore, an alternate source of power is not essential. Normally one startup transformer supplies 4160 volt Buses 1 and 3, and the other supplies Buses 2 and 4; bowever, the two startup transformers are designed with adequate capacity such that, should one become or be umde inoperable, temporary connections can be made to supply the total station load (less the cooling towers) from the other startup transformer.
I Amendment No. 58 178
VY;PS
~ .
A battery charger is supplied for each battery. In addition,'the two 125 volt station batteries and.the two 24:
. . volt ECCS instrumentation batteries each have a spare charger available. Since one space 24 volt and one 125 s volt charger are available, one battery' charger can be allowed out of service for maintenance and repairs.
Power for the Reactor Protection System is supplied by 120 V ac motor generators with an alternate supply from MCC-8B. 1Dc) redundant. Class IE, seismically qualified power protection panels are connected in series with each ac powet source. These panels provide overvoltage, undervoltage, and underfrequency protection for the system. Setpoints are chosen to be' consistent with the input power requirements of the equipment connected to the bus.
B. ' Adequate power is available to operate the emergency safeguards equipment from either startup transformer or for minimum engineered safety features.from either of the emergency diesel generators. .Therefore, reactor operation is permitted for up to seven days with both delayed-access of f-site power sources . lost.
Each of the diesel generator units is, capable of supplying 100 percent of the minimum emergency loads required under postulated design basis accident conditions. Each unit is physically and electrically independent of the-other and of any off-site power source. Therefore, one diesel generator can be allowed out of service for.a period of seven days without jeopardizing the safety of the station.
178a
-