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MONTHYEARML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery Project stage: Other ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus Project stage: Request ML20151S1931988-04-20020 April 1988 Forwards Application for Amend to License DPR-34,allowing 5 Consecutive Days to Perform Equalizing Charge W/Battery Project stage: Request ML20196L4891988-07-0101 July 1988 Documents Results of Page by Page Review of Tech Specs,Per K Heitner Request Following Initial Review of Proposed 880420 License Amend.No Technical Differences Between Util & NRC Tech Specs Exist.Word Processing Formats Different Project stage: Other ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries Project stage: Request ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 Project stage: Request ML20207E1491988-08-0505 August 1988 Resubmits Affected Pages of Tech Spec Limiting Condition for Operation 4.6.1, Auxiliary Electric Sys, Per 880727 Request.Amend Request Originally Submitted w/ . Attachments Changed in Format Only Project stage: Other ML20154J7691988-09-15015 September 1988 Forwards Amend 64 to License DPR-34 & Safety Evaluation. Amend Changes Tech Specs for Plant DC Power Sys & Allows for Future Changes to Station Batteries Project stage: Approval 1988-07-01
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos ML20212A0661986-12-19019 December 1986 Proposed Tech Specs Re Steam Line Rupture Detection/ Isolation Sys 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] |
Text
. _ .
'Q.
. s . Fort St. Vrain #1 ~
Technical Specifications
, ' Amendment No.
Page 4.6-4 charger or battery may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, l unless disconnected to perform an equalizing . charge,'
provided conditions l'through'4 below are satisfied.
s
- 1) The other station battery and- its associated; battery charger and both D'.C. buses are operabl . ,
? ,
1 2) D.C. bus independence is maintained and the I disconnect switch for the PPS battery is open,
- 3) Both diesel generators and their, associated essential 480v buses-are operable.
- 4) The PPS battery and battery charger / inverter are operable.
A battery and battery charger disconnected from a D.C.
l bus to perform an equalizing charge is considered-l inoperable, but may be disconnected for up to 5 l consecutive days provided conditions 1) 'through 4) 1 above are met, j 1
One D.C. bus may be inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided l l
the following conditions are satisfied:
- 1) The station battery and the associated battery charger of the operable D.C. bus are operable.
s 1
- 2) Instrument power inverter suoplied from the 3
l I
operable D.C. bus is operable. ;
< 3) Both diesel generators and their associated 480v essential buses are operable.
1 I
8804280259 DR 880420 r p ADOCK 05000267 DCD
. - .. Li - . . . . . , - - . - , - - - , - , - . , , - - - - - ~ = . 1
'~
s Fort St. Vrain 01 Technical Specifications Amendmentdo',
Page 4,6-8
, a:v >
The station batteries supply power for the instrument power inverters, protective devices and equipment ;
j operational control. During normal operation,.D.C. power i l is supplied by A.C. to 0.C. rectifiers, that is, battery I chargers, which also keep the' batteries fully charged.
- (FSAR Section 8.2.2.4.)
l Tne backup sources of electric pow'e r for th'e non-l interruptible A.C. Instrument Power Buses are provided ,
I from Instrument Power Transformers fed from the 480 VAC l essential buses through the Inverter / Static Transfer ,
l Switches. Interruptible Instrument Bus No. 3 receives its.
power from redundant instrument transformers which are supplied from the essential 480 volt switchgear. (FSAR Section 8.2.2.3.) 1 i.
l A redundant source of electric power for the D.C.
l instrument loads is available from bus tie breakers l between the two D.C. buses which allows the backup battery l charger to supply either one of the two buses while l maintaining D.C. bus independence. [
These backups and redundancies permit the temporary !
removal from service of an instrument power inverter, a
- l , battery, a D.C. bus or a battery charger.
- A diesel fuel storage capacity of 50,000 gallons is !
orovided. A supply of 20,000 gallons of ciesel fuel is ,
i adequate to provice for operation of the standby.
i generators for at least seven days under required loading
-- w - a . .w.--. - - ae a a M
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4 e
i ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATION i
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t i P-88116 Attachment 3 Page 1 of 5 s
SIGNIFICANT HAZARDS CONSIDERATION Description of the Amendment Request The proposed amendment request would modify Fort St.' Vrain Technical Specification 4.6.1,(e) regarding the D.C. buses, the station and PPS batteries and the battery chargers. The purpose of the proposed il amendment is to allow a station battery and associated batte ry d charger to be disconnected from its D.C. bus for up to 5 consecutive f days to perform an equalizing charge. During this period, the station ba ttery and associated battery charger would be declared inoperable. In addition, the purpose of this proposed amendment is to require that the D.C. bus tie breakers be configured such that D.C. bus independence is maintained and the disconnect switch for the PPS battery is open when a station battery or battery charger is e inoperable.
System Description I The Fort St. Vrain D.C. power systeri consists of two D.C. buses, three 125 VDC batteries, and four battery chargers. The two station batteries supply power for the two separate and normally independent D.C. buses which feed two of the three instrument power inverters, protective devices, and equipment operational control. The PPS 4
battery supplies power for the third instrument power inverter which feeds the third channel of the PPS. .Three of the four battery chargers are powered directly from the 480 VAC essential buses and j maintain the proper charges on each of the three 125 VDC batteries and supply D.C. power during normal operation. An electrical single-line diagram of the instrument power and the D.C. power system is attached.
A bus tie circuit is provided for maintenance and service purposes.
A disconnect feature permits the performance of an equalizing charge during plant operation, while the associated 0.C. bus is energized by the backup battery charger. Independence is maintained by ensuring the D.C. bus tie breakers associated with the operable station battery are open, as is the disconnect switch for the PPS battery.
3 Reasons for the Change i
Per IEEE 450-1980 proper maintenance of a battery will prolong the life of a battery and will aid in assuring that it is capable of performing its design function. As part of this maintenance, action l
l l
'I
s P-88116 Attachment 3 Page 2 of 5 may be required in the form of an equalizing charge to prevent conditions which can reduce the battery life, but do not necessarily indicate a loss of capacity. An equalizing charge normally . requires that an eqcalizing voltage be applied continuously for 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> to 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> or longer based on manufacturer's instructions.
At Fort St. Vrain, it is necessary to disconnect a station battery and associated battery charger from its D.C. bus during the performance of an equalizing charge to preclude damage to the loads on the D.C. bus. However, the existing Technical Specifications allow only 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for this condition. Based on manufacturer's instructions, up to 5 consecutive days may be required to perform an adequate equalizing charge. Therefore, the battery can not receive an adequate equalizing charge while the plant is operating under the existing Technical Specifications.
The proposed change would allow a station battery and associated battery charger to be disconnected from its D.C. bus to perform an equalizing charge. This would allow appropriate corrective action to be taken to properly maintain the batteries and prevent damage to the loads on the D.C. bus. As stated above, the performance of an equalizing charge is to prevent the life of the battery frcm being reduced and to prevent a loss of capacity. Therefore, in the event of an accident, such as the loss of all A.C. power, the equal ir.ng charge could be terminated and the battery could be reccnnected to the D.C. bus to perform its intended function.
The practice of electrically connecting the D.C. buses together when a battery or battery charger is inoperable as required in the existing Technical S;,ecifications is not in accordance with the 2 0 guidance provided in Safety Guide 6. The slightly improved defense against random failures achieved by the bus tie is more than offset by the additional vulnerability to common mode failures which the existing Technical Specification requirement creates. The bus tie allows a station battery and associated battery charger to be ,
disconnected from the D.C. system and to align the backup battery I charger to supply power to the D.C. bus while niai ntaini ng D.C. bus independence.
l l
l l
l I
i l
1 1
(
1
1
- l P-88116 Attachment 3 Page 3 of 5 Evaluation PSC has analyzed the proposed amendment request for significant hazards consideration using the standards in Title 10, Code of Federal Regulation, Part 50.92. The proposed amendment request involves no significant hazards consideration, since the proposed amendment would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated.
Either one of the two station batteries is adequate to supply the required shutdown D.C. loads for four hours following the loss of all A.C. power. (FSAR 8.2.3.4). In the event all A.C. power is lost, the inoperable battery being charged can readily be !
reconnected to the system to perform its design function. For other possible accidents that could occur, the associated D.C.
bus is supplied by the backup battery charger while maintaining D.C. bus independence such that both D.C. buses are available.
Therefore, this charge cannot increase the probability or i consequences of an accident. )
- 2. create the possibility of a new or different kind of accident e from any previously evaluated, y ;
This change extends the period of time that a stapion battery and !
associated battery charger can be disconnected from its D.C. bus by allowing up to 5 consecutive days to perform an equalizing charge. This is required for proper maintenance of the batteries.
Ensuring D.C. bus independence is maintained and the disconnect switch for the PPS battery is open when a station battery and/or associated battery charger is inoperable eliminates the possibility of a common mode failure. Therefore, it does not create the possibility of a new or different kind of accident.
l
- 3. involve a significant reduction in a margin of safety. !
The D.C. loads normally supplied by the station battery and associated battery charger are being supplied by the backup battery charger during the performance of an equalizing charge !
while maintaining D.C. bus independence. The allowance of up to 5 consecutive days to perform an equalizing charge will assure ,
the station battery i s capable of sati sfying its design l requirements. The disconnecting of a station battery and battery '
charger for up to 5 consecutive days does not reduce the margin of safety of the Auxiliary Electric Power System to provide e e- -- *- ,-,e nm. , --
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. t P-88116
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-Attachment 3 Page 4 of 5
/~ adequate electric power since the required power- source still
f exists. The. station battery can be reconnected to supply the required electrical loads to effect a safe shutdown of the plant.
Ensuring D.C. bus independence eliminates the possibility of a common mode. failure. Therefore, continued operation -under this configuration will not reduce significantly a margin of safety.
Conclusion Based on' the above evaluation, it is concluded that operation of Fort. St.' Vrain in accordance with the proposed changes will- involve '
no significant hazards consideration. PSC considers the changes to be an improvement in the overall plant reliability as the allowance .
for up to 5 consecutive days for the station batteries to be disconnected from its D.C. bus to perform an equalizing charge will provide the means to properly maintain the station batteries and prevent damage to any of the loads on the D.C. bus. In addition, ,
deleting the requirement that the D.C. bus tie breaker is closed and '
replacing it with the requirement that D.C. bus independence is maintained and the disconnect swi'tch for the;PPS battery is open ensures D.C. bus independence is not compromised. ,
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