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| | number = ML20062F955 | | | number = ML20062F955 |
| | issue date = 12/11/1978 | | | issue date = 12/11/1978 |
| | title = Appl for Amend to Append a of Facil Oper Lic#DPR-34,changing Tech Specs for Fire Protec Sys Re Halon Fire Suppression Sys & Smoke Detectors & Alarms for Control Room & Cable Areas & Fixed Water Spray Sys for Auxiliary Elec Room | | | title = Appl for Amend to Append a of Facil Oper Lic DPR-34,changing Tech Specs for Fire Protec Sys Re Halon Fire Suppression Sys & Smoke Detectors & Alarms for Control Room & Cable Areas & Fixed Water Spray Sys for Auxiliary Elec Room |
| | author name = Millen C | | | author name = Millen C |
| | author affiliation = PUBLIC SERVICE CO. OF COLORADO | | | author affiliation = PUBLIC SERVICE CO. OF COLORADO |
Appl for Amend to Append a of Facil Oper Lic DPR-34,changing Tech Specs for Fire Protec Sys Re Halon Fire Suppression Sys & Smoke Detectors & Alarms for Control Room & Cable Areas & Fixed Water Spray Sys for Auxiliary Elec RoomML20062F955 |
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Fort Saint Vrain |
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12/11/1978 |
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Millen C PUBLIC SERVICE CO. OF COLORADO |
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ML20062F953 |
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NUDOCS 7812220069 |
Download: ML20062F955 (6) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 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 ML20151R8141988-04-20020 April 1988 Application for Amend to License DPR-34,deleting 10CFR51.5(b)2 ML20149M2851988-02-0808 February 1988 Application for Amend to License DPR-34,revising Tech Specs Re Plant Protective Sys Trip Setpoints & Operating Requirements ML20149N0371988-02-0505 February 1988 Application for Amend to License DPR-34,changing Administrative Controls to Reflect Organizational Changes ML20238C3431987-12-23023 December 1987 Application for Amend to License DPR-34,revising Tech Specs Re safety-related Cooling Sys,Per 871202-03 meetings.W/re- Drafted Tech Specs & Discussions of NRC Comments from Aug 1987 & 871202-03 Meetings ML20236C6271987-10-15015 October 1987 Application for Amend to License DPR-34,deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements from Tech Specs ML20235W8521987-10-0101 October 1987 Application for Amend to License DPR-34,revising Tech Spec Sections Elco 8.1.1 to Clarify Actions on Inoperble Halogen Monitors & ESR 8.1.1 & 8.1.2 to Clarify Conditions Re Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20216H7221987-06-25025 June 1987 Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements ML20210B6831987-04-23023 April 1987 Application for Amend to License DPR-34,changing Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys.Fee Paid ML20206P3811987-04-0808 April 1987 Application for Amend to License DPR-34,revising Interim Tech Spec 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserved Shutdown Sys,Per Rev 4 to FSAR ML20207Q5381987-01-21021 January 1987 Application to Amend License DPR-34,changing Tech Specs for Limiting Condition for Operation 4.6.1, Auxiliary Electric Sys, to Bring Consistency to Electrical Sys Nomenclature. Fee Paid ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs ML20207D1891986-12-23023 December 1986 Application for Amend to License DPR-34,revising Tech Specs to Delete Snubber Tables & Correct Typos 1997-04-03
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan ML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20246J3091989-08-30030 August 1989 Amend 72 to License DPR-34,imposing Early Shutdown on Plant by Limiting Reactor Power to 2% of Full Power After 900630 ML20245J3671989-08-14014 August 1989 Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20248D6461989-03-31031 March 1989 Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20236A1351989-02-27027 February 1989 Amend 68 to License DPR-34,modifying Limiting Condition for Operation 4.4.1 & Surveillance Requirement 5.4.1 to Include Fixed High Temp Trip Setpoint for Steam Line Rupture & Detection Sys ML20205F9781988-10-24024 October 1988 Amend 65 to License DPR-34,amending Tech Specs Paragraph 2.D(3) to Require Compliance W/Amended Physical Security Plan & to Conform to 10CFR73.55 Requirements ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20154J7931988-09-15015 September 1988 Amend 64 to License DPR-34,changing Tech Specs for Plant DC Power Sys & Allowing for Future Changes to Station Batteries ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20207F0061988-08-0505 August 1988 Amend 61 to License DPR-34,deleting Requirement to Monitor Temp of Dew Point Moisture Monitors in Section 4.4 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error 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 1997-05-05
[Table view] |
Text
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of the Facility Operating Licenst )
)
of ) Docket No. 50-267
)
PUBLIC SERVICE COMPANY OF COLORADO )
Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 OF THE PUBLIC SERVICE COMPANY OF COLORADO F0R THE FORT ST. VRAIN NUCLEAR GENERATING STATION This application for Amendment to Appendix A of Facility Operating License, License No. DPR-34, ,
is submitted for NRC review and approval.
( Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By --
- C. K. liillen, Senior Vice President KELLY, STANSFIELD & 0'DONNELL Bryant O'Donnell Robert E. Thompson Public Service Company Building Denver, Colorado 80202 l
Attorneys for Applicant j I
7812220069
Attochment 1 Specification LCO 4.10.2 - Halon Fire Suppression System, Three Room Control Complex, Limiting Condition for Operation The Halon Fire Suppiassion system for the control room, auxiliary electric room, and the 480 volt switchgear room shall be operable during reactor power operation. If the Halon system becomes inoperable and cannot be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be shutdown in an orderly manner.
Basis for Specification LCO 4.10.2 The Halon system provides fire suppression capability for the control roon, auxiliary elettric room, and the 480 volt switchgear room. Halon is a non-toxic, halogsnated c emical fire suppressant. The Halen system is a total flooding extinguishing system divided into three sections. One section supplies the 480 volt switchgear room, the second section supplies the control room, and the third the auxiliary electric toom. Total flooding of these areas with halon will extinguish an active fire without requiring abandonment of the area.
The auxiliary electric room Halon System Section is automatically initiated by the simultaneous actuation of a detector in zone #2 and #3 of Table 4.10-3; the 480 volt room Halon System Section is automatically initiated by the simultaneous actuation of a detector in fire detection zone #5 and #6 of Table 4.10-3.
The Halon System Section for the 480 volt switchgear room may be manually initiated by a switch located just outside the door of the room. The Halon System for the auxiliary electric room may be manually initiated by a switch .
located just outside of the room. The Halon System Section of the control room is manually initiated by a switch located in the control room. In the event ,
that electrical power is not available to initiate Halon System operation, each Halon storage bottle is provided with a manually operated release mechanism i
which will release the bottle contents when operated.
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Attachment 2 Specification LCO 4.10.3 - Smoke Detectors and Alarms for Three Room Control Complex and Congested Cable Areas, Limiting Condition for Operation The reactor stall not be operated at power unless the minimum number of smoke detectors for each of the zones listed in Table 4.10-3 are operable.
If the minimum number of detectors of each zone are not operable, the following actions shall be taken:
An individual shall.be designated to inspect the area or areas with inoperable detectors once per hour.
The inoperable detectors shall be made operable within thirty (30) days or the reactor shall be shut down in an orderly manner.
~
Basis for Specification LCO 4.10.3 The smoke d'etection and alarm system provides detection and alarm capa-bility for the control room, auxiliary electric room, the 480 volt switch gear room, the congested cable areas located at the "G" and "J" column rows and selected reactor building HVAC return air ducts in various areas which are not normally manned.
In addition the system will automatically initiate operation of the Halon
- fire suppression system in the auxiliary electric room or the 480 volt switch- .
gear room upon actuation of a detector in both of the zones in each room.
The system alerts the operator to the possibility of a fire in the con-gested cable areas and to the necessity of investigation of conditions in these areas.
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- . - Atttchment 2 1
TABLE 4.10-3 SMOKE DETECTORS AND ALiRMS NUMBER OF MINIMUM NUMBER
- ZONE DETECTOR,S OPERABLE
- 1) Control Room 6 4 3 2) Auxiliary Electric Room 3 2
- 3) Auxiliary Electric Room 3 2
- 4) Auxiliary Electric Room Return Air Duct 1 0*
- 5) 480 Volt Switchgear Room 3 2
- 6) 480 Volt Switchgear Room 3 2
- 7) Reactor Building "J" Wall Elevation
. Rev. 4756' to 4791' 4 2
- 8) Reactor Building "J" Wall Elevation 4791' to 4829' 4 2
- 9) Reactor Building "J" Wall Elevation 4829' to 4849' ' "
2 1
- 10) Reactor Building "J" Wall Elevation 4849' to 4881' 2 1
- 11) Turbine Building "G" Wall Elevation i
4791' to 4811' 2 1
! 12) Turbine Building "G" Wall Elevation f
i 4811' to 4829' 2 1
- 13) Reactor Building HVAC Return Air Duct 1
at Elevation 4932' 1 1
- 14) Reactor Building HVAC Return Air Ducts 4 2
- 15) Reactor Building HVAC Return Air Duct 6 4
- To be returned to service as soon as practicable after loss of function. ,
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- Attachment 3 Specification LCO 4.10.5 - Fixed Water Spray Systems for the Auxiliary Electric Room. 480 Volt Switchgear Room, and Congested Cable Areas The fixed water spray systems providing supplementary fire protection
- in the 480 volt switchgear room, auxiliary electrical equipment room, and con-gested cable areas of the reactor building side of the "J" vall and turbine building side of the "G" wall shall be operable during reactor power operation.
If the spray systems become inoperable and cannot be made operable within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the reactor shall be shut down in an orderly manner.
Basis for Specification LCO 4.10.5 The fixed water spray systems provide backup fire suppression in the congested j cable areas. In the 480 volt switchgear room and the auxiliary electric room, the systems are a backup to the installed Halon system. If the fixed water spray systems were inoperable, the smoke detectors and alarm system of LCO 4.10.3 would be available for detection and alarm of a fire. In all areas where it is installed the fixed water spray system is a backup to normal fire fighting techniques.
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- * - Attachment 4 Specification SR 5.10.6 - Fixed Water Spray System, Surveillance Requirement The manually operated valves actuating the fixed water spray system i
providing supplementary fire protection in the 480 volt switchgear room, auxiliary electric room, and congested cable areas shall be opened annually.
The flow path from the manual isolation valves to and including the spray nozzles shall be verified to be open annually.
Basis for Specification SR 5.10.6 7 Annual opening of the manually operated valves and verification of
(
available flow path is sufficient to demonstrate capability to operate if required.
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