Proposed TS Bases 3/4.3.3.8 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Sys & 3/4.7.12 Re Fire Barrier PenetrationsML20098D672 |
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Sequoyah |
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Issue date: |
05/26/1992 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20098D670 |
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References |
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CON-TVA-SQN-TS-92-05, CON-TVA-SQN-TS-92-5 NUDOCS 9205290236 |
Download: ML20098D672 (11) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20113G2691996-09-20020 September 1996 Proposed Tech Specs Change 96-09, Clarification of Work Shift Durations for Overtime Limits ML20117J3391996-08-28028 August 1996 Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D1651996-08-22022 August 1996 Proposed Tech Specs of SQN Units 1 & 2,deleting Table 4.8.1, DG Reliability, & Revising Section 3.8.1 to Allow Once Per 18 month,7 Day AOT for EDGs ML20117D3121996-08-22022 August 1996 Proposed Tech Specs,Lowering Minimum TS ice-basket Weight of 1,155 Lbs to 1,071 Lbs.Reduced Overall Ice Weight from 2,245,320 Lbs to 2,082,024 Lbs ML20117D3141996-08-21021 August 1996 Proposed TS 3.7.1.3 Re Condensate Storage Tank ML20117D3341996-08-21021 August 1996 Proposed Tech Specs Re Deletion of Surveillance Requirement 4.8.1.1.1.b ML20112H0431996-06-0707 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N7071996-04-0404 April 1996 Proposed Tech Specs,Allowing Conversion from Westinghouse Fuel to Fuel Provided by Framatome Cogema Fuels ML20096B3761996-01-0404 January 1996 Proposed Tech Specs Extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20096C2481996-01-0303 January 1996 Proposed Tech Specs,Revising Bases Section 3/4.7.1.2 to Indicate Current Operational Functions of turbine-driven AFW Level Control Valves Modified During Unit 1 Cycle 7 Refueling Outage 1999-08-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] |
Text
us1-<--m--- A--- -----n-a- -ah- 4L4 Em a%k - + b-- 4 .E KA B M-M LsA-eWL1K-A-:- 4 4mA-= 4A-aan----A++LL W-a4 'k,-n==aemde ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) BASES CilANGE SEQUOYAll NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-92-05) i i
LIST OF AFFECTED PAGES Uni.L1 B3/4 3-4 B3/4 7-7 B3/4 7-8 Unit _2 B3/4 3-4 B3/4 7-7 l-I l
920S290236 920526 PDR ADOCK 05000327 P PDR
INSTRUMENTATION BASES 3/4.3.3.8 FIPE DETECTION INSTRUMENTATION OPERASILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to i safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of tne fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide deto: tion capability until the inoperable instrumentation is restored to OPERABILITY. I
_4. _
Th1= .recification is deleted.
3/4.3.3.10 EXPLOS7VE GAS MONITORING INSTRUMENTATION R152 This instrumentation ir.t.ludes provisions for monitoring the concentrations .-
of potentially explosive gas mixtures in the waste gas holdup system. The OPER- [ffic ~
ABILITY an'd use of this instrumentation is consistent with the requirements for ?
monitoring potentially explosive gas mixtures.
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I R153 SEQUOYAH - UNIT 1 B 3/4 3-4 Amendment No. 43, 148, 149 Revised 08/19/87 DEC 0 71990
PLANT SYSTEMS '
( BASES 4
SNUBBERS (Continueo)
) location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10- The R43 addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.7.10 SEALED SOURCE CONTAMINATION
, . n.
Q3 F' The ? haitations on removable contamination for sources requiring leak tast-1 .ng, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
'his limitation vill ensure that leakage from byproduct, source, and special -
auclear material sources will not exceed allowable intake values. Sealed sources are clauified into three groups according to thcir use, with surveil-lance
- hat grcup. requirements commensurate with the probability of damage to a source in Those sources which are frequently handled are required to be tested more often than those which are not. Secled sources which are continu-ausly er. closed within a st ' 21ded mechanism (i.e. , sealed sources within radia-
, tion monitoring or baron measu-ing devices) are cons 4dered to be stored and need not be t$sted unless they are removed from the shielded mechanism. p' 3/4.7.11 FIRE SUPPRESSION SYSTEMS e.- The 0?ERABILITY of the fir suppren ion systems e,.ures that acequate fire suppression capability is availab < to confine and extinquish fires
"' occaring located -in any portion of the facility where safety related equipmcnt is The #4 and/o/ m. Ors, CO ,2and fire hose stations.re suppression system consists of the water sy The col'ective capability of the fire upp dssion systems ' adequato to minimize potential damage to safety related equipment and ia a major element in the facility fire protection program.
t g
In the event that portions of the fire suppression u stems are inoperable, alternate backup fire fighting equipment is required to be made available in the,affected areas until the inoperable equipment is restored to service.
g When the inoperable fire fighti. , equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire righting than if the inoperable equipment is the primary means of fire suppression.
The surveillance requirements provide assur .ce that tha minimum OPERABILITY requirements of the fire suppression systems are met.
In the evect she fire suppression water system becomes inocerable, immediate corrective masurt3 mude be taken since this system provides the major fire suppressicc m bility of the plant. The recoirament for a twenty-four hour i report to tt.,
wommission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for tne conti.nued protection of the nuclear plant, f"/m p15C }
l SEQUOYAH - UNIT 1 June 20, 1985 R43 8 3/4 7-7 Amendment No. 39- {
PLANT SYSTEMS BASES 3/4.7.12 FIRE BARRIER PENETRATIONS
(
The functional integrity of the fire barrier penetrations ensures that fires will be portions ofconfined or adequately retarded from spreading to adjacent the facilitf. '
This design feature minimizes the possibility of a single and fire rapidly involving several areas of the facility prior to detection extinguishment.
The fire barrier penetrations are a pa.;sive element in the facility fire protection program and are subject to periodic inspections. I Fire barrier penetrations, including cable penetration barriers, fire !
doors and dampers are considered functional when the visually observed condi-tion is the same as the as-designed condition. For those fire barrier per.<.trations that are not in the as-designed condition, an evaluation shall be performad to show that the penetration. modificatior has not degraded the fire rating of the fire barrier l During periods af time when a barrier is not functional, either,1) a I continuous fire watch is required to be maintained in the viciaity of the ,
I affected barrier, or 2) the fire detectors on at least one side of the affected barrier must ce verified OPERABLE and a hourly fire watch patrol established, until the barrier is restored to functional status. i i
ud June 20, 1985 SEQUOYAH - JNIT 1. B 3/4 7-8 Amendment No. 39 R43
INSTRUMENTATInN BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability 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 u integral ele ~ ant in the overall facility fire protr ction program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frecuent fire patrols in the affected areas ic required to provide detection capability until the inoperable instrumentation
- h. restored to OPERABILITY. R35 g
3 .9 This Specification is deleted. R134 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATICN This instrumentation includes ;,ovisions for monitoring the concentrations of potentially explosive as mixtures in the waste gas holdup system. The OPERA- .
BILITY and 4Jse of thit instrumentation is consistent with the requirements for monitoring potentially explosive gas mixtures.
~
R134
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l SEQUOYAH - UNIT 2 8 3/4 3-4 Amendment Nos. 35, 46, 134
[li~ )~~)
PLANT SYSTEMS BASES 3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinquish fires occuring in any portion of the facility where safety related equipment is located. The fire suppression syrtem consists of the water system, spray and/or sprinklers, CO , and fire hose stations. The collective capability of thefiresuppressionkystemsisadequate.tominimizepotentialdamageto safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systemt are inoperable, alternate backup fire fighting equipr:ent is required to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.
s In the event the fire suppression water system becomes inoperable,- immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a 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.
tNSars 4.7.12 FIRE BARRIER PENETRATTONS The functional integrity of the fire barrier penetrations ensures that fires will ba ennfined or adequately retarded from spreading to adjacent portions ; e facility. This design feature minimizes the possibility of a single fir _ . acidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetrations are a passive element in the facility fire protection program and are subject to periodic inspections.
Fire barrier penetrations, including cable penetration ba, ciers, fire l doors and dampers are considered functional when the visually observed :codi-tion is the same as the as-designed conditir.,n. For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of th fire barrier penetration.
During periods of time wnen a barrier is not functional, either,1) a continuotts fire waten is required to be maintained in the vicinity of the affected barrier, or 2) the f' e detectors on at least one side of the .affected ba rier must be verified OPE: 'E and a hourly fira watch patrol established, n 'l the barrier is restored to functional status, (u l livgg72r.8 de 0 - UNIT 2 S 3/4 7-7 .
1HSIRLA All hourly fire watch patrols require that a trained individual be in the specified area at intervals of 60 minutes with a margin of 15 minutes.
m
.- - .~. . . . - -.. . . -. .- - . . - - . ~ .- -- . .
clhSERT B
,Al' hourly fire watch patrols require that a trained individual be h the
- specified area at intervals of 60 minutes with a margin of 15 minutes.
A continuous fire watch requires that a trained individual be in the specified area at all times, that-the specified area contain no ir pediment to restrict. the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a. margin of 5 minutes.
A specified area for a continuous fire watch is one or more locations, which are easily accessible to each other and can be patrolled wJthin
, 15 minutes. Easy access is defined as: no locked doors or inoperable card reader, no C-Zone entry required, or no hazards that will interfere with the continuous fire watch activity being performed within the ,
15-minute period.
p i
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. , . . . . ~ . .-, . .- . -~ .- - . . . . - . _ . - _ - - - . - .- . . ~. -,
I ENCLOSURE 2 PROPOSEL TECIINICAL SPECIFICATION (TS) BASES CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 1
--DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-T3-92-05)
DESCRIPTION AND JUSTIFICATION FOR REVISION OF TS BASES FOR FIRE WATCHES I ..
e 5
4 7
1 4
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- - - . - _ ~ , . . . .. . . . _ . . .. . . - _ _ , , , _ .
- . - - . ._ - - . - - - . . _ _ _ _ - . - . . . ~ . _ - - - - - . . . - . ._ ,
, . Desnrjation of Change TVA proposes to modify the Sequoyah Nuclear Plant (SQN) Units 1 and 2 technical specifications (TSs) bases to revise TS Bases 3/4.3.3.8, " Fire Detection Instrumentation," 3/4.7.11. " Fire Suppression Systems," and 3/4.7.12, " Fire Barrier Penetrations." The changes provide clarification and interpretation for both hourly and continuous fire watches.
The following wording is proposed to be added to TS Bases 3/4.3.3.8:
All hourly fire wntch patrols require that a trained individual oe in the specified area at intervals of 60 minutes with a margin of 15 minutes.
The following wording is proposed to be added to TS Bases 3/4.7.11 and 3/4.7.12:
All hourly fire watch patrols require that a trained individual be in the specified area- at intervals of 60 minutos with a margin of 15 minutes.
A continuous fire watch requirer + hat a trained individual be in the specified area at all times, that the specified area centains no impediment tc restrict the movements of the continuous fire watch, and that each compartment within the specified area is patrolled at least once every 15 minutes with a margin of 5 minutes.
A specified area for a continuous fire watch is one or more locations, whits are easily accessible to each other and can be patrolled within 15 minutes. Easy access is defined ;as: no locked doors or inoperable card reader, no step-off pads, or no hazards that will interfere with the continuous fire watch activity being performed within the 15-minute period.
- Reaann for Change The TSs do not currently provide an interpretation of the terms " hourly" or " continuous" fire watches; the addition of the proposed discussion to the TS bases will allow all personnel to have a common-interpretation of l these terms.
The proposed change will aid in the reduction of fire-watches not believed to be necessary for the prompt detection of fires and will clarify the requi ements for meeting the time frequencies of the watches. Adding this information to the bases will reduce the fire watch btrden at SQN by allowing a single continuous fire watch to cover more than one impairment at a time, i,lualification for thange It is desirable to quantify the limits associated with the hourly patrol requirements and provide tolerances. Defining an hourly fire watch-
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frequency as 60-minute intervals with a 15-minute margin provides
-reasonable administrative flexibility and is consistent with other TS surveillance frequencies that allow margins of 25 percent.
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The current TS wording infers.a separate stationary, continuous-firewatch is needed for each compartment or area outside immediate visual range.
It. is believed that prompt detectior of fires can be achieved by a-continuous fire watch monitoring multiple impairments in a given fire area, provided movement is not restricted by locked doors, contamination zones, etc.,'and the impairments are checked no less than every 15 minutes.with a 5-minute margin.
These changas are considered to provide reasonable administrative flexibility and reduce the overall firewatch burden while maintaining an acceptable level of detection. The proposed changes are not considered to change the intent of the TSs and are similar to the wording contained in the corresponding D. C. Cook 1;uclear Plant technical specification bases.
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