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MONTHYEARML20134J3111985-08-21021 August 1985 Proposed Tech Specs,Authorizing Use of factory-installed Dipstick Arrangement to Verify Halon Content in Each Tank & Performance of Visual & Tactile Insp of Nozzles as Alternative to Puff Test Project stage: Other ML20141E9291986-04-10010 April 1986 Safety Evaluation Supporting Amend 98 to License DPR-46 Project stage: Approval ML20141E8891986-04-10010 April 1986 Amend 98 to License DPR-46,revising Tech Specs to Reflect Addition of Halon Fire Suppression Sys & Fire Detectors in Station Svc Water Pump Room as Part of App R Fire Protection Program Project stage: Other ML20141E8751986-04-10010 April 1986 Forwards Amend 98 to License DPR-46 & Safety Evaluation. Amend Revises Tech Specs to Reflect Addition of Halon Fire Suppression Sys & Fire Detectors in Station Svc Water Pump Room as Part of App R Fire Protection Program Project stage: Approval 1985-08-21
[Table View] |
Proposed Tech Specs,Authorizing Use of factory-installed Dipstick Arrangement to Verify Halon Content in Each Tank & Performance of Visual & Tactile Insp of Nozzles as Alternative to Puff TestML20134J311 |
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Cooper |
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Issue date: |
08/21/1985 |
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From: |
NEBRASKA PUBLIC POWER DISTRICT |
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Shared Package |
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ML20134J292 |
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References |
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NUDOCS 8508290241 |
Download: ML20134J311 (3) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers ML20065K1931994-04-12012 April 1994 Proposed Tech Specs,Reflecting Removal of Definitions 1.0.Z.B.1 Through 5,change to LCO 3.21.B.1.a (Line 5) Re Ref to 10CFR20.106 & Change to Paragraphs 1,4,5 & 6 (Lines 6,3,8 & 2 Respectively) Re Ref to 10CFR20.106 ML20058N2321993-12-10010 December 1993 Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept ML20058N2881993-12-10010 December 1993 Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves ML20058M2591993-09-28028 September 1993 Proposed Tech Specs Modifying Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operation ML20056G5971993-08-31031 August 1993 Proposed TS Re Primary Containment Isolation Valve Tables ML20056G5821993-08-31031 August 1993 Proposed TS Re Primary & Secondary Containment Integrity ML20056G2341993-08-25025 August 1993 Proposed Tech Specs Bases Section to Reflect Operational & Design Changes Made to CNS Svc Water Sys During 1993 Refueling Outage ML20056F3331993-08-23023 August 1993 Proposed Tech Specs 6.0, Administrative Controls, Reflecting Creation of Mgt Position of Vice President - Nuclear ML20045D8991993-06-23023 June 1993 Proposed TS SR 4.9.A.2 Re Determination of Particulate Concentration Level of Diesel Fuel Oil Storage Tanks ML20045C0031993-06-14014 June 1993 Proposed Tech Specs Associated W/Dc Performance Criteria ML20045C8301993-06-14014 June 1993 Proposed Tech Specs Incorporating New Requirements of 10CFR20 ML20128L5561993-02-12012 February 1993 Proposed TS Table 4.2.D, Min Test & Calibr Frequencies for Radiation Monitoring Sys & TS Pages 81 & 84 Re Notes for Tables 4.2.A Through 4.2.F ML20128E6201993-02-0101 February 1993 Proposed Tech Specs Reflecting Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8331993-01-0505 January 1993 Proposed TS Pages 53,55,70 & 71,removing Bus 1A & 1B Low Voltage Auxiliary Relays ML20115F8531992-10-15015 October 1992 Proposed Tech Specs Page 48,reflecting Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3481992-10-0808 October 1992 Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee ML20104B2091992-09-0909 September 1992 Proposed TS 3.1.1 Re Reactor Protection Sys Instrumentation Requirements & TS Table 3.2.D Re Radiation Monitoring Sys That Initiate &/Or Isolate Sys ML20104A8691992-09-0202 September 1992 Proposed TS 3.9 & 4.9 Re Auxiliary Electrical Sys ML20099D4151992-07-28028 July 1992 Proposed TS 3.6 Re LCO for Primary Sys Boundary & 4.6 Re Surveillance Requirements for Primary Sys Boundary ML20113G8241992-05-0404 May 1992 Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08 ML20096D6111992-05-0404 May 1992 Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A8061992-02-25025 February 1992 Proposed Tech Specs Re Dc Power Sys 1999-06-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] |
Text
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i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.16 (cont'd) 4.16 (cont'd)
SPECIFICATIONS SPECIFICATIONS A. The Automatic Sprinkler Systems pro- A. The Automatic Sprinkler Systems pro-tecting the Cable Spreading Room, tecting the Cable Spreading Room, Cable Expansion Room, and Northeast Cable Expansion Room, and Northeast Corner - 903 Ft. Elev of Reactor Corner - 903 Ft. Elev. of Reactor Building shall be operable. Building shall be demonstarted to B. If the requirement of 3.16.A cannot be operable by:
be met, establish a continuous fire 1. At least once per 12 months by I watch with backup fire suppression cycling each testable valve in equipment for the unprotected area the flow path through at least within I hour; restore the system one complete cycle of full to OPERABLE status within 14 days travel.
or prepare and submit a Special Report to the Commission within 2. At least once per 18 months:
the next 30 days' outlining the a) By performing a system action taken, the cause of the functional test which inoperability and the plans and includes simulated schedule for restoring the system automatic actuation of to OPERABLE status. the system, and ,
3.17 CARBON DIOXIDE AND H.ALON SYSTEMS 1) Verifying that the
. automatic valves in APPLICA8ILITY the flow path actu-Applies to the operational status of th'e ate to their correct s ns on a test High Pressure Carbon Dioxide Extinguishing ,
System protecting the Diesel Generator
- 2) Cycling each valve in Rooms and the Halon Suppression System the flow path that is protecting the Service Water Pump Room.
not testable during OBJECTIVE plant operation through at least one To assure continuous Automatic Fire Pro-taction for the Diesel Generator Rooms CU"E * * "Y"
b) By ins act n f the spray SPECIFICATIONS headers to verify their ,
A. The High Pressure Carbon Dioxide 1""*8' ICY
- Extinguishing System protecting 4.17 CARBON DIOXIDE AND HALON SYSTEMS the Diesel Generator Rooms shall APPLICABILITY be operable.
Applies to the operational status of the B. The Halon 1301 Fire Suppression ;
System protecting the Service High Pressure Carbon Dioxide Extinguishing Water Pump Room shall be operable System protecting the Diesel Generator t with at least one storage tank Rooms and the Halon Suppression System ,
charged to at least 95% of the protecting the Service Water Pump Room. j design quantity (650 lbs) and SPECIFICATIONS f 90% of full charge pressure.
A. The High Pressure Carbon Dioxide Extinguishing System protecting t the Diesel Generator Rooms shall be demonstrated operable by:
- 1. At least once per 6 months, the High Pressure Carbon Dioxide storage cylinders should be weighed.
8508290241 850821 PDR ADOCK 05000298 P PDR -216f-1
i l
l LIMITING CONDITIONS FOR OPERATION SUFVEILLANCE REQUIREMENTS 3,17 (cont'd) 4.17 (cont'd)
! C. If the requirement of 3.17.A and 2. At least once per 18 months by 3.17.B cannot be met: verifying the system valves, alarms, and associated venti-i 1. Establish a continuous fire watch with backup fire suppres- la n m t r interl sam i sion equipment for the unprotected dampers actuate to a simulated area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the aut matic and manual actuation i
system to OPERABLE status within 8kE""*
^ "'* " ""
(, Puff Test ) shall be made to 14 days or prepare and submit a Special Report to the Commission verify flow from each nozzle.
l
- within the next 30 days outlining B. The Halon 1301 Fire Suppression Sys-l the action taken, the cause of the tem protecting the Service Water inoperability and the plans and Pump Room shall be demonstrated schedule for restoring the operable
system to OPERABLE status.
- 1. At least once per six months by 3.18 FIRE HOSE STATIONS recording the quantity of Halon
! and the pressure of each Halon APPLICABILITY l storage tank.
Applies to the operational status of the Fire Hose Stations in the Control and 2. At least once per 18 months by Reactor Buildings. verifying the system valves, alarms, and associated venti-OBJECTIVE lation motor interlocks and To assure continuous manual fire fighting dampers actuate to a simulated capability provided by existing Fire Hose automatic and manal actuadon Stations. signal and by performing an in-spection to assure the nozzles SPECIFICATIONS . are unobstructed.
A. The Fire Hose Stations shown in 4.18 FIRE HOSE STATIONS Table.3.18 shall be operable.
APPLICABILITY B. If the requirement of 3.18.A cannot be met, route an additional hose to & a a sus of W the area protected by the inoperable Fire Hose Stations in the Control and Fire Hose Station from an operable Reactor Buildings. ,
Fire Hose Station of equivalent SPECIFICATIONS capacity within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
A. The Fire Hose Stations in the Control Building and Reactor Building shall be demonstrated to be operable by:
- 1. At least once per 31 days by:
a) Visual inspection to assure all required equipment is l at the station.
- 2. At least once per 18 months by:
a) Removing the hose for in-spection and re-racking, and l b) Replacement of all degraded gaskets in couplings.
- 3. At least once per 3 years by:
a) Partially opening each hose station valve to verify valve OPERABILITY and no
-216g- fl v blockage, and
r e, .a.
l 3.14-3.19/4.14-4.19 BASES 3.14/4.14 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate
- warning capability is available for the prompt detection of fires. This cap-l ability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is in-operable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service.
3.15-3.18/4.15-4.18 FIRE SUPPRESSION SYSTEMS THE OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO '
2 Halon 1301, and fire hose stations. The collective capability of the fire l suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. The Halon Fire Suppression System consists of two storage tanks, each exceeding the design capacity required for extinguishment of a fire in the service water pump room in accordance with the National Fire Codes. Each tank, containing 650 lbs of Halon 1301, can flood the Service Water Pump Room to a uniform concentration i
of 8 percent, exceeding the 3.5 percent level sufficient to extinguish a flame in the region.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.
In the event the fire suppression water system becomes inoperable, in-mediate corrective measures must be taken since this sytem provides the major fire suppression capability of the plant. The requirement for twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3.19/4.19 FIRE BARRIER PENETRATION SEALS The functional integrity of the fire barrier penetration seals ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature mir.imizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguish-ment. The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the seals are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected seal until the seal is restored to functional status.
Fire barrier penetration seals include cable penetration barriers, fire doors, and fire dampers.
-216m-
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