|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 ML20132E6211996-12-17017 December 1996 Proposed Tech Specs 3/4.7.3 Re Component Cooling Water Sys ML20132B5111996-12-10010 December 1996 Proposed Tech Specs Re Groundwater Level Exceeding Current Maximum Water Level ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML20134H0051996-11-0606 November 1996 Proposed Tech Specs,Modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20134F8781996-09-0404 September 1996 Proposed Tech Specs Requiring Exemption from Certain Requirements of 10CFR50.44, Stds for Combustible Gas Control Sys in Light Water Cooled Power Reactors & 10CFR50.46, Acceptance Criteria for Eccs.. ML20107L3951996-04-25025 April 1996 Proposed Tech Specs,Providing Suppl Info Re Clarification of TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101Q0871996-04-0808 April 1996 Proposed Tech Specs Re EDG Allowed Outage Times ML20101F7971996-03-21021 March 1996 Proposed Tech Specs,Clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguards Area Ventilation Sys ML20097C0171996-01-31031 January 1996 Proposed Tech Specs,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy Portions of SRs Required During Shutdown ML20097J4341996-01-30030 January 1996 Proposed Tech Specs,Modifying Table 3.2-1 of TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9871996-01-23023 January 1996 Proposed Tech Specs,Permitting Use of 10CFR50,App J,Option B performance-based Containment Lrt ML20094N7921995-11-20020 November 1995 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0191995-10-25025 October 1995 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5921995-10-17017 October 1995 Proposed TS 4.4.5.1,Table 4.4-1,reducing from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6161995-10-17017 October 1995 Proposed Tech Specs,Allowing Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4231995-09-19019 September 1995 Proposed Tech Specs,Increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J3051995-09-19019 September 1995 Proposed Tech Specs,Revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2481995-09-0101 September 1995 Proposed Tech Specs,Allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087A1171995-07-26026 July 1995 Proposed Tech Specs,Increasing Pressurizer Safety Valve Lift Setpoint Tolerance as Well as Reduce Pressurizer High Pressure Rt Setpoint & Allowable Value ML20087A1311995-07-26026 July 1995 Proposed Tech Specs,Clarifying TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20087G3471995-03-30030 March 1995 Proposed Tech Specs Re Changes That Allow One of Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operationin Order to Refurbish Isolated Svc Water Headers 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20196K1971998-12-22022 December 1998 Rev 0 to NE-1176, North Anna Unit 1,Cycle 14 Startup Physics Tests Rept, Dec 1998 ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236U8891998-06-25025 June 1998 Rev 0 to NE-1163, North Anna Unit 2 Cycle 13 Startup Physics Tests Rept ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20203G5191997-12-29029 December 1997 Ultrasonic Exam Technique for Detection of Microbilogically Induced Corrosion in North Anna Stainless Steel Service Water Piping ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20198G5401997-08-31031 August 1997 Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997 ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 1999-08-04
[Table view] |
Text
.. _. - . . -.
TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION 2
INSTRUMENTATION IOCATION MINIMUM DETECTORS REQUIRED HEAT SMOKE
- 1. Reactor Containment
- a. Reactor Coolant Pumps 1/ pump *
- b. Residual Heat Removal Pump Area 3
- c. Cable Penetration Area 7 6
- d. Recirculation Air System 2
- 2. Control Room
- a. Under Floor - Loop 1 2 2
- b. Under' Floor - Loop 2 2
- c. Normal Air Supply # 1
- d. Emergency Air Supply 1
- e. Ceiling Area 10
- f. Return Air Duct 1
! 3. Primary Cable Vault and Tunnel 2 3
- 4. Service Building Cable Vault and Tunnel 5 4
- 5. Emergency Switchgear Rooms
- a. Emergency Air Supply 1
- b. Emergency Switchgear and Air Conditioning Rooms 7
- 6. Station Battery Room 1/ room
- 7. Diesel Generators 2/ room
- 8. Fuel Oil Pump House #
- a. Room 1 1 1 l
- b. Room 2 1 1
- c. Motor Control Center Room 1
- 9. Rod Control Equipment and Motor Control Center Room (Elevation 280.0) 2 i 10. Auxiliary Building f a. Charging Pump Cubicles 1/ cubicle
! b. Exhaust Duct (Northeast-Cubicles)# 1
- c. Exhaust Duct (South Central-Cubicles)# 1
- d. Exhaust Duct (Northwest-Cubicles)# 1 l NORTH ANNA - UNIT 1 3/4 3-53a e31013o107 831007 PDR ADOCK 05000338 P PDR
TABLE 3.3-11 (con't)
FIRE DETECTION INSTRUMENTATION INSTRUMENTATION LOCATION MINIMUM DETECTORS REQUIRED HEAT SMOKE Auxiliary Building (con't)
- e. General Area Elevation 244'# 1
- f. General Area Elevation 259'# 4
- g. General Area Elevation 274'# 14
- h. General Area Elevation 291'# 4
- 1. Charcoal Filters
- 1. Intake Sided 3/ room
- 2. Outlet Side # 3/ room
- 11. Service Water Pump House # 8
- 12. Auxiliary Service Water Pump House # 1
- 13. Auxiliary Feed Water Pump House
- a. Turbine Pump Room I
- b. Motor Pump Room 3
- 14. Quench Spray Pump House
- a. Main Floor 2
- b. Basement 4
- 15. Safeguards Area Ventilation
- a. System Exhaust Duct 1
- 16. Main Steam Valve House 1
- 17. Fuel Building # 10
- 18. Casing Cooling Pump House 1
- 19. Post Accident Hydrogen Recombiner Vault # 1
- 20. Fire Pump House # 1
- 21. Control Room Air Conditioning Chiller Room 1
- A RCP bearing or motor temperature may be substituted for an inoperable RCP heat detector provided the bearing or motor temperature (s) is monitored at least once per hour when the RCP is in operation.
- Common to Units 1 and 2.
NORTH ANNA - UNIT 1 3/4 3-53b
TABLE 3.7-7 FIRE HOSE STATIONS HOSE RACK IDENTIFICATION AB-H-1 AB-H-4 AB-H-6 AB-H-8 AB-H-12 AB-H-13 AB-H-15 AB-H-18A AB-H-19 AB-H-22 AB-H-24 AB-H-27 AB-H-29 AB-H-30 AB-H-32 AB-H-33 l
F-H-1 F-H-3 T-H-7 T-H-25 T-H-21 T-H-22D T-H-33 T-H-34 HP-H-5 BLR-H-2
- Dry standpipes in containment are considered rperable when normally isolated by valves 1-FP-274 and 1-FP-275.
NORTH ANNA - UNIT 1 3/4 7-83a
PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.14.6 The spray and/or sprinkler systems located in the following areas shall be OPERABLE:
- a. Auxiliary Building, Component Cooling Pump Area, Elev. 244'6" (common to Units 1 and 2).
- b. Auxiliary Building, Component Cooling Pump Area, El. 259'6" (common to Units 1 and 2.)
- c. Service Building Cable Vault, High Bay Area (manual system, open heads)
- d. Service Building Cable Tunnel, (manual system, closed head)
APPLICABILITY: All modes ACTIONS: 1 With a spray and/or sprinkler system inoperable establish a continuous fire watch and backup water fire suppression equipment in the unprotected area (s) within I hour, and
- a. In MODES 1, 2, 3, or 4 restore the system to OPERABLE status within 7 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. In MODES 5 or 6 restore the system to OPERABLE status within 7 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not ,
applicable.
SURVEILLANCE REQUIREMENTS 4.7.14.6 The spray and/or sprinkler systems shall be demonstrated to be OPERABLE:
- a. At least once per 92 days by cycling each testable valve through one complete cycle. Not applicable to the dry pipe systems in 3.7.14.6.c. and d.
NORTH ANNA - UNIT 1 3/4 7-83b
r SURVEILLANCE REQUIREMENTS
- b. At least once per 18 months:
- 1. By performing a system functional test which includes simulated automatic actuation of the system and verifying that the automatic valves in the flow path actuate to their correct positions.
- 2. By inspection of spray headers to verify their integrity.
- 3. By inspection of each nozzle to verify no blockage.
- c. At least once per 3 years by an air flow test of the open head spray and/or sprinkler system.
NORTH ANNA - UNIT 1 3/4 7-83c
. i 6
4 ATTACHMENT 2 1
i I
i
r TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION INSTRUMENTATION LOCATION MINIMUM DETECTORS REQUIRED HEAT SM0KE
- 1. Reactor Containment
- a. Reactor Coolant Pumps 1/ pump *
- b. Residual Heat Removal Pump Area 3
- c. Cable Penetration Area 7 8
- d. Recirculation Air System 2
- 2. Control Room
- a. Under Floor - Loop 1 2 2
- b. Under Floor - Loop 2 2
- c. Normal Air Supply # 1
- d. Emergency Air Supply 1
- e. Ceiling Area 10
- f. Return Air Duct 1
- 3. Primary Cable Vault and Tunnel 2 3
- 4. Service Building Cable Vault and Tunnel 5 4
- 5. Emergency Switchgear Rooms
- a. Emergency Air Supply 1
- b. Emergency Switchgear and Air Conditioning Rooms 7
- 6. Station Battery Room 1/ room
- 7. Diesel Generators 2/ room
- 8. Fuel Oil Pump House #
- a. Room 1 1 1
- b. Room 2 1 1
- c. Motor Control Center Room 1
- 9. Rod Control Equipment and Motor Control Center Room (Elevation 280.0) 2
- 10. Auxiliary Building
- a. Charging Pump Cubicles 1/ cubicle
- b. Exhaust Duct (Northeast-Cubicles) # 1
- c. Exhaust Duct (South Central-Cubicles)# 1
- d. Exheust Duct (Northwest-Cubicles)# 1 NORTH ANNA - UNIT 2 3/4 3-50a
TABLE 3.3-11 (con't)
FIRE DETECTION INSTRUMENTATION INSTRUMENTATION LOCATION MINIMUM DETECTORS REQUIRED HEAT SM0KE Auxiliary Building (con't)
- e. General Area Elevation 244'# 1
- f. General Area Elevation 259'# 4
- g. General Area Elevation 274'# 14
- h. General Area Elevation 291'# 4
- 1. Charcoal Filters
- 1. Intake Side # 3/ room
- 2. Outlet Side # 3/ room
- 11. Service Water Pump House # 8
- 12. Auxiliary Service Water Pump House # 1
- 13. Auxiliary Feed Water Pump House
- a. Turbine Pump Room 1
- b. Motor Pump Room 3
- 14. Quench Spray Pump House
- a. Main Floor 2
- b. Basement 4
- 15. Safeguards Area Ventilation
- a. System Exhaust Duct 1
- 16. Main Steam Valve House 1
- 17. Fuel Building # 10
- 18. Casing Coolit.; Pump House 1
- 19. Post Accident Hydrogen Recombiner Vault # 1
- 20. Fire Pump House # 1
- 21. Control Room Air Conditioning Chiller Room 1
- A RCP bearing or motor temperature may be substituted for an inoperable RCP heat detector provided the bearing or motor temperature (s) is monitored at least once per hour when the RCP is in operation.
- Common to Units 1 and 2.
NORTH ANNA - UNIT 2 3/4 3-50b
TABLE 3.7-7 FIRE HOSE STATIONS HOSE RACK IDENTIFICATION AB-H-1 AB-H-4 AB-H-6 AB-H-8 AB-H-12 AB-H-13 AB-H-15 AB-H-18A AB-H-19 AB-H-22 AB-H-24 AB-H-27 AB-H-29 AB-H-30 AB-H-32 AB-H-33 l
! F-H-1 F-H-3 T-H-7 T-H-25 1 T-H-21
- T-H-22D i T-H-33 T-H-34 HP-H-5 BLR-H-2
- RC-H-5 l *RC-H-6 CT-H-1 ESW-H-1 I
- Dry standpipes in containment are considered operable when normally isolated i by valves 2-FP-81 and 2-FP-82.
l l'
i l
l NORTH ANNA - UNIT 2 3/4 7-69a l
l
PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.14.6 .The spray and/or sprinkler systems located in the following areas shall be OPERABLE:
- a. Auxiliary Building, Component. Cooling Pump Area, Elev. 244'6" (common to Units 1 and 2).
- b. Auxiliary Building, Component Cooling Pulp Area, El. 259'6" a
(common to Units 1 and 2.)
- c. Service Building Cable Vault, High Bay Area (manual system, open heads)
- d. Service Building Cable Tunnel, (manual system, closed head)
APPLICABILITY: All modes ACTIONS:
With a spray and/or sprinkler system inoperable establish a continuous fire watch and backup water fire suppression equipment in the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and j a. In MODES 1, 2, 3, or 4 restore the system to OPERABLE status
' within 7 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. In MODES 5 or 6 restore the system to OPERABLE status within 7 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not .
Applicable.
SURVEILLANCE REQUIREMENTS .
4.7.14.6 The spray and/or sprinkler systems shall be demonstrated to be OPERABLE:
- a. At least once per 92 days by cycling each testable valve through one complete cycle. Not applicable to the dry pipe systems in 3.7.14.6.c. and d.
NORTH ANNA - UNIT 2 3/4 7-69b
4 SURVEILLANCE REQUIREMENTS
- b. At least once per 18 months:
- 1. By performing a system functional test which includes simulated automatic actuation of the system and verifying that the automatic valves in the flow path actuate to their correct positions.
- 2. By inspection of spray headers to verify their integrity.
- 3. By inspection of each nozzle to verify no blockage.
- c. At least once per 3 years by an air flow test of the open head spray and/or sprinkler system.
4 i
NORTH ANNA - UNIT 2 3/4 7-69c
1 .
I c5 e
A' 2 ATTACHMENT 3
=,
4
,.s*
DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGES The Nuclear Regulatory Commission's " Safety Evaluation Report Fire Protection Program, North Anna 1 & 2", dated February',1979, requires the installation of additional fire protection systems in certain safety-related areas of the station. These systems have been installed by design change DC 78-68. The systems increase the protection provided to safety-related systems from the hazard of fire.
The purpose of the Technical Specification change is to update the existing Technical Specifications to reflect the new fire protection systems. These 1 changes are as follows:
I. FIRE DETECTORS In order to provide early warning of a fire additional smoke and fire detectors were installed throughout the station. Placement of the detectors were made after a study of the configuration of the area so that maximum protection could be realized. The additional detectors serve to increase the safety of the station and does not adversely affect plant safety or increase the possibility of an accident.
II. FIRE PROTECTION STANDPIPES To provide additional fire protection water supplies, fire hose stand-pipes and hose racks were added in the following areac:
(a) Auxiliary Building - Wet fire hose standpipe.
(b) Emergency Switchgear - Units 1 & 2 - Dry fire hose standpipe.
(c) Cable Tray Spreading Room - Wet fire hose standpipe.
(d) Reactor Containment - Units 1 & 2 - Dry standpipe system.
The addition of the above standpipes serve to increase plant protection due to a fire. The standpipes located in safety-related areas were l mounted to withstand a seismic event. Dry standpipes were installed where water could damage safety-related equipment. Therefore installa-tion of this equipment does not increase the possibility of an accident.
t o
SP9/SWB/las:UI
. . . . . . . . . . . _ _ . - . _ - . - . .~
III. SPRINKLER SYSTEM In order to provide additional fire protection, sprinkler systems were installed in the following safety-related areas.
(a) Auxiliary Building Component Cooling Pump Area, Elev. 244'6" (common to Units 1 and 2).
(b) Auxiliary Building Component Cooling Pump Area, Elev. 259'6" (common to Units 1 and 2).
(c) Service Bailding Cable Vault, High Bay Area (manual system, open heads).
(d) Service Building Cable Tunnel, (manual system, closed head).
The addition of the above sprinkler systems serve to increase plant protection due to a fire. The sprinkler systems located in safety-related areas were mounted to withstand a seismic event. Dry systems were installed where water could damage safety-related equipment. There-fore, installation of this equipment does not increase the possibility of an accident.
SP9/SWB/ Ins:U2
_