Proposed Change 83-9 Revising Tech Spec 3/4.12 Re Fire ProtectionML20077R310 |
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Site: |
Pilgrim |
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Issue date: |
09/12/1983 |
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From: |
BOSTON EDISON CO. |
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To: |
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Shared Package |
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ML20077R178 |
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References |
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NUDOCS 8309160291 |
Download: ML20077R310 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20072T0521994-09-0606 September 1994 Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe ML20072S0501994-09-0606 September 1994 Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems ML20072S0081994-09-0606 September 1994 Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief ML20072S0861994-09-0606 September 1994 Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20069M3311994-06-0909 June 1994 Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe ML20067B7111994-02-0909 February 1994 Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993 Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059A9361993-10-19019 October 1993 Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993 Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint ML20046D0441993-08-0909 August 1993 Proposed Tech Specs,Proposing 24 Month Fuel Cycle ML20044G1331993-05-20020 May 1993 Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993 Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively 1999-06-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] |
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Attachment Proposed Technical Specification Change Proposed Change Reference is made to Pilgrim Nuclear Power Station, Unit #1 Technical Specifica-tions, Appendix A, Section 3.12, " Fire Protection."
Item 3.12.F The Limiting Condition for Operation, Surveillance Requirements, and Bases for Item 3.12.F are changed in their entirety. The existing Item 3.12.F is reproduced below. Refer to Pages 206e, 206e-1, and 206j in this Attachment for the proposed replacement of Item 3.12.F.
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS F. Penetration Fire Barrier F. Fire Barrier Penetration Fire Seals All fire barrier penetration fire seals protecting safety related 1. Penetration fire barriers areas shall be functional. shall be verified to be functional by a visual APPLICABILITY: At all times. inspection at least once per operating cycle and ACTION: subsequent to any instal-lation, modification, or With a penetration fire barrier maintenance, not functional, a continuous fire patrol shall be established on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (NOTE: In the case of the fire penetration barrier between the main steam tunnel and turbine building, substi-tute a "once per hour fire patrol" for the " continuous fire patrol").
(Bases appear on next page) .
8309160291 830912 PDR ADOCK 05000293 PDR p
Bases 3/4.12F 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 minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspection.
During periods of time when the seals are not functional, a continuous fire patrol is required to be maintained in the vicinity of the affected seal until the seal is restored to functional status.
The substitution of action statements from " continuous fire patrol" to "once per hour fire patrol" for the fire penetration barrier between the main steam tunnel and turbine building is based on:
(1) Only one fire barrier between the Turbine Building and reactor building is required. Thus, the steam tunnel can be included with either the RHR "A" Valve Room or Turbine Ruilding fire areas.
(2) The existing configuration (i.e. no door and an unrated blowout assembly) provides adequate fire separation and protection capabilities on the following bases:
(a) Combustible loadings in the areas of concern are very low. Tran-sient loadings are administratively controlled.
(b) The blowout panel is constructed of materials consistent with
" rated" fire barriers offering protection up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(c) A fire detection system exists in the RHR Valve Room and a fire suppression system exists in the Turbine Building.
Reason for Change The existing Technical Specifications address only fire barrier penetration seals.
The entire fire barrier system should be addressed in accordance with the logic presented in 10CFR50, Appendix R. This proposed change expands the scope of the Technical Specifications to more fully comply with 10CFR50, Appendix R. Specifi-cally, requirements for operability and surveillance of fire doors and dampers have been added. Appropriate action statements are specified if fire doors or dampers are not functional. These action statements are consistent with the BWR Standard Technical Specifications. The only exceptions are when High Radiatiori Areas (> 100 mr/hr) exist on both sides of a fire barrier. An hourly fire patrol for these situations seems justified based on ALARA concerns when weighed against the risk posed by a station fire.
Safety Considerations These changes do not present an unreviewed safety question as defined in 10CFR 50.59. They have been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.
Significant Hazards Considerations It has been determined that the amendment request involves no significant hazards consideration. Under the NRC's regulations in 10CFR50.92, this means that opera-tion of the pilgrim Nuclear Power Station in accordance with the proposed amend-ment would not (1) involve a significant increase in the probability or conse-quences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The NRC has provided guidance concerning the application of standards for deter-mining whether license amendments involve significant hazards considerations by providing certain examples (48 FR 14870). One example of an amendment that is considered not likely to involve a significant hazards consideration is "...(11)
A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications: for example a more strigent surveillance requirement..." This proposed change adds requirements for oper-ability and surveillance of fire doors and dampers.
Schedule of Change As stated in our letter of May 13, 1983, we expect the NRC to issue the seven submittals as a single amendment. This amendment will be effective upon our receipt of approval from NRC.
Fee Determination Pursuant to 10CFR170.12, Boston Edison Company proposes these changes as one seg-ment of the Fire Protection submittal, which, when taken as a whole will be classified as a Class III amendment. Accordingly, a check for $4000 will be transmitted with the final segment of this amendment request.
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS E. Fire Hose Stations E. Fire Hose Stations The interior fire hose stations Each interior fire hose station shall shown in Table 3.12-2 shall be be verified to the OPERABLE:
OPERABLE.
- 1. at least once per month by visual APPLICABILITY: inspection of the station to assure all equipment is available.
At all times when the equipment in the area protected by the fire 2. at least once per cycle by re-hose station is required to be moving the hose for inspection, operable, replacing degraded coupling gaskets, and re-racking.
ACTION:
- 3. at least once per 3 years by With a hose station inoperable, route an additional equivalent a. partially opening each hose capacity hose to the unprotected station valve to verify area from an OPERABLE hose station valve operability and no within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. blockage.
- b. by conducting a hydrostatic test of each hose
- 1) at a pressure 50 psig greater than the maximum available pressure at that hose station, or
- 2) annually at the applicable service test pressure as listed in Table 821 of the
" Standard for Core, Main-tenance and Use of Hose,"
NFPA No. 198-1972, or
- c. by replacing each hose with a new or used hose which has been hydrostatically tested in ac-cordance with the pressures specified in 4.12., E.3.b.
F. Fire Barrier System F. Fire Barrier Penetrations All fire barrier systems providing 1. Fire barrier penetration seals separation of redundant safe shut- Each fire barrier penetration seal down systems shall be functional. shall be verified to be functional l
by a visual inspection at least APPLICABILITY: once per operating cycle and'sub-At all times when the safe shut- sequent to any installation, mod-down systems are required to be ification or maintenance affecting l operable. the seal.
- 2. Fire Doors A TION- Each fire door shall be tested With one or more of the required once per cycle for operability fire barrier systems non-functional, of closure and latching mechanisms within one hour either establish a and for integrity.
l continuous fire watch patrol on 206e one side of l
sendment No. . .- -
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS the affected barrier or verify the 3. Fire Dampers OPERABILITY of an automatic fire Each fire damper shall be detection or suppression system on tested once per cycle for at least one side of the non- operability and integrity.
functional fire barrier and estab-lish an hourly fire watch patrol.
EXCEPTION: When the Fire Areas on A BOTH sides of the effected fire /F\
barrier are designated "HIGH RADIATION AREAS", an hourly fire watch patrol may be established (e.g. for ALARA considerations) in lieu of a continuous fire watch patrol.
G. Dry Chemical Systems G. Dry Chemical Systems The fixed dry chemical systems Each dry chemical shall be verified located in the following areas to be OPERABLE:
shall be OPERABLE: A. At least once per 6 months by
- 1. Diesel Generator Room ,,A,,.
checking all stored dry chemical
- 2. Diesel Generator Room B. containers by pressure and weight APPLICABILITY against the required minimums.
At all times when equipment in B. At least once per 18 months by:
the protected area is required to be operable. 1. Verifying the system actuates manually and automatically, ACTION: upon receipt of a simulated With a dry chemical system test signal, and inoperable, establish a con-tinuous fire patrol with 2. Performance of a flow test backup fire suppression through headers and nozzles equipment for the unprotected to assure no blockage.
areas within one hour; restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and the plans for restoring the system to OPERABLE status.
H. Yard Hydrants and Exterior Hose H. Yard Hydrants and Exterior Hose Houses Houses
- The yard hydrants and exterior Each hydrant shall be verified hose houses shown in Table OPERABLE
3.12-2 shall be OPERABLE.
- 1. At least once per month by a APPLICABILITY: At all times. visual inspection of the hose ,
ACTION: house to assure all equipment ~
With a yard hydrant inoperable, is available.
within one hour have a sufficient number of additional lengths of 2. At least twice per year (once 2-1/2" diameter hose located in in the fall and once in the an adjacent OPERABLE hydrant's spring) by inspecting each out-hose house to provide service I aoor fire hydrant.
to the area protected by the !
inoperable hydrant. i 3. At least once per year by per-forming surveillance requirements E.3.b or c.
Amendment No. g 206e-1
BASES 3/4.12F FIRE BARRIER SYSTEM The functional integrity of the fire barrier system ensure:., that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. A functional fire barrier system, is considered to be the barrier itself with all penetration seals, doors and dampers intact or operable. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier systems are a passive element in the facility fire protection program and are subject to periodic inspections.
Safe shutdown systems are those systems which must operate after a {
loss of offsite power and are required to achieve and maintain safe shutdown i (hot and cold shutdown) conditions. kll During periods of time when the barriers are not functional, either, j
- 1) a continuous fire watch patrol is required to be maintained in the ,
vicinity of the affected barrier, or 2) the automatic fire detection or l suppression system on at least one side of the affected barrier must be '
verified OPERABLE and an hourly fire watch patrol established until the ,
barrier is restored to functional status. A fire watch patrol is a compensatory measure to survey area (s) in which the active and/or passive fire detection, suppression or barrier system (s) are in a degraded mode and is utilized for .
detection and reporting of fires. I The surveillance requirements are considered to be adequate since they were determined using accepted industry .eference material as a basis applying good engineering judgement and station operating considerations. '
O