Proposed Tech Specs Adding Four Smoke Detectors in Reactor Auxiliary Bldg & Clarifying Identifying Numbers of Three Containment Isolation ValvesML20125B249 |
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Waterford ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/06/1985 |
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From: |
LOUISIANA POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML20125B221 |
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References |
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NUDOCS 8506110358 |
Download: ML20125B249 (14) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217K9011999-10-18018 October 1999 Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20211F3701999-08-24024 August 1999 Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207 ML20211F5501999-08-24024 August 1999 Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220 ML20210M9681999-08-0404 August 1999 Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions ML20210M9861999-08-0404 August 1999 Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown ML20210H2371999-07-29029 July 1999 Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20209H3191999-07-15015 July 1999 Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves ML20210D1071999-07-15015 July 1999 Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20209D4091999-07-0707 July 1999 Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207 ML20195B1811999-05-20020 May 1999 Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12 ML20203C4891999-02-0505 February 1999 Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension ML20199E0861999-01-12012 January 1999 Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174 ML20199D9851999-01-12012 January 1999 Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel ML20198G2401998-12-23023 December 1998 Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20196D2181998-11-30030 November 1998 Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants ML20154E4171998-10-0606 October 1998 Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle ML20154E1141998-10-0101 October 1998 Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys ML20153D5771998-09-23023 September 1998 Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable ML20153B4441998-09-18018 September 1998 Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation ML20151W5971998-09-11011 September 1998 Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7921998-08-12012 August 1998 Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7361998-07-29029 July 1998 Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model ML20236H1501998-07-0202 July 1998 Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition ML20249C8321998-06-29029 June 1998 Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432 ML20249C7901998-06-29029 June 1998 Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls ML20249A3101998-06-12012 June 1998 Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls ML20248B7611998-05-28028 May 1998 Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys ML20247P2431998-05-21021 May 1998 Proposed Tech Specs Re Design Feature Suppl ML20217P8411998-05-0101 May 1998 Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal ML20217D5181998-03-25025 March 1998 Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8 ML20198R1251998-01-21021 January 1998 Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys ML20198R3081998-01-21021 January 1998 Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements ML20197C6431997-12-22022 December 1997 Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section ML20199A1101997-11-13013 November 1997 Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20199A0011997-11-13013 November 1997 Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21 ML20217G2421997-10-0707 October 1997 Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8141997-09-25025 September 1997 Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G7131997-07-0707 July 1997 Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3 ML20141D8551997-06-26026 June 1997 Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases ML20140B1671997-06-0303 June 1997 Proposed Tech Specs,Modifying Action Requirements for TS 3/4.3.2 for SI Sys Sump Recirculation Actuation Signal ML20148G6631997-06-0303 June 1997 Proposed Tech Specs,Requesting Minimum Required Level in Condensate Storage Pool Be Increased from 82% to 91% to Account for Vortexing & Instrumentation Measurement Uncertainties ML20141K1741997-05-24024 May 1997 Proposed Tech Specs 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1-1, Removing Cycle Dependent Boron Concentration ML20141K1951997-05-24024 May 1997 Proposed Tech Specs 3/4.7.4 Modifying Ultimate Heat Sink, Table 3.7-3,by Incorporating More Restrictive Dry Cooling Tower Fan Requirements & Changes Wet Cooling Tower Water Consumption in TS Bases ML20140H0831997-05-0606 May 1997 Proposed Tech Specs Modifying Wording of SR 4.5.2.j by Replacing Venting ECCS Pump Casings & Discharge Piping High Points, with Verifying ECCS Piping Is Full of Water ML20140C8881997-04-17017 April 1997 Proposed Tech Specs,Replacing Attachment to Waterford 3 Submittal W3F1-97-0067,dtd 970407,correcting Oversight ML20137T4051997-04-11011 April 1997 Proposed Tech Specs,Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20137T4541997-04-11011 April 1997 Proposed Tech Specs Making TS 3.6.2.2 & Surveillance Requirement 4.6.2.2 Consistent W/Containment Cooling Assumptions in Waterford 3 Containment Analysis 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217K9011999-10-18018 October 1999 Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20211F5501999-08-24024 August 1999 Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220 ML20211F3701999-08-24024 August 1999 Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207 ML20210M9681999-08-0404 August 1999 Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions ML20210M9861999-08-0404 August 1999 Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days ML20210H2371999-07-29029 July 1999 Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves ML20210D1071999-07-15015 July 1999 Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20209H3191999-07-15015 July 1999 Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY ML20209D4091999-07-0707 July 1999 Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207 ML20196E9971999-05-24024 May 1999 Rev 3 to NTP-203, Emergency Plan Training ML20195B1811999-05-20020 May 1999 Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12 ML20204H2591999-03-16016 March 1999 Rev 0 to STD-100-237, Procedure for Modification of RCS Pressure Boundary for Installation of Mechanical Nozzle Seal Assemblies (Mnsa) for Waterford Nuclear Generating Station Unit 3 ML20204H2511999-03-16016 March 1999 Rev 1 to C-NOME-EP-0189, Engineering Procedure for Installation of Mechanical Nozzle Seal Assemblies for Waterford 3 ML20203C4891999-02-0505 February 1999 Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension ML20199D9851999-01-12012 January 1999 Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel ML20199E0861999-01-12012 January 1999 Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174 ML20198G2401998-12-23023 December 1998 Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20196D2181998-11-30030 November 1998 Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants ML20154E4171998-10-0606 October 1998 Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle ML20154E1141998-10-0101 October 1998 Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys ML20153D5771998-09-23023 September 1998 Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable ML20153B4441998-09-18018 September 1998 Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation ML20151W5971998-09-11011 September 1998 Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7921998-08-12012 August 1998 Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7361998-07-29029 July 1998 Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model ML20236H1501998-07-0202 July 1998 Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition ML20249C8321998-06-29029 June 1998 Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432 ML20249C7901998-06-29029 June 1998 Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls ML20249A3101998-06-12012 June 1998 Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls ML20248B7611998-05-28028 May 1998 Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys ML20248H7871998-05-25025 May 1998 Rev 1 to Waterford Unit 3 Second Interval ISI Plan ML20247P2431998-05-21021 May 1998 Proposed Tech Specs Re Design Feature Suppl ML20217P8411998-05-0101 May 1998 Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal ML20217L9971998-04-30030 April 1998 Small Break LOCA ECCS Performance Analysis Using Abb/Ce Suppl 2 Model ML20217D5181998-03-25025 March 1998 Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8 ML20198R3081998-01-21021 January 1998 Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements ML20198R1251998-01-21021 January 1998 Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys ML20197C6431997-12-22022 December 1997 Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section ML20202C2911997-12-0101 December 1997 Rev 0 to Pump & Valve Inservice Test Plan for Second 10-Yr Interval. Page 23 of Incoming Submittal Not Included ML20199A0011997-11-13013 November 1997 Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21 ML20199A1101997-11-13013 November 1997 Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20217M0221997-10-28028 October 1997 Rev 8 to RW-001-210, Process Control Program ML20217H5931997-10-14014 October 1997 Revised Page of App B of FOL, Environ Protection Plan (Nonradiological) ML20217G2421997-10-0707 October 1997 Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8141997-09-25025 September 1997 Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G7131997-07-0707 July 1997 Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3 ML20141D8551997-06-26026 June 1997 Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases 1999-08-04
[Table view] |
Text
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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
- a. With any, but not more than one-half the total in any fire zone Function A fire detection instruments shown in Table 3.3-11 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment or annulus, then inspect that containment or annulus zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or for the containment, monitor air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
- b. With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the contain-ment or annulus, then inspect that containment or annulus zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or for the containment, monitor air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
- c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.3.3.8.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months. Circuits which are not accessible during plant opera-tion shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 montO .
WATERFORD - UNIT 3 J/4 i9 8506110358 850606 PDR ADOCK 05000382 P PDR
TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS ,
TOTAL NUMBER OF INSTRUMENTS
- ELEVATION HEAT FLAME SMOKE ZONE ROOM NAME/ NUMBER (ft) (x/y) (x/y) (x/y)
- 1. REACTOR AUXILIARY BUILDING (Continued)
RAB 25 Equip. Access Area /226 (wing area) +21 15/0 RAB 27A H&V Room /124 +7 0/6 RAB 278 Electrical Area and Health Physics +7 0/35 Offices /122 RAB 27C I&C Room /120 +7 0/2 RAB 270 Communicati,ons Equip. Room /123 +7 1/0 RAB 31 Corridors and Passageways -4 0/24 Corridors on eastside -4 0/21 RAB 32 Wing Area westside - Auxiliary Com- -35 32/0 ponent Cooling Water Pump "A"/B53 &
and Pipe Penetration Area /8100 -4 Wing Area Center /B53 and B100 -35 & 28/0
-4 Wing Area eastside-Component Cooling -35 31/0 Water Pump "B"/B53 and Pipe Penetration Area /B100 -4 !
RAB 33 S/D Cooling Heat Exchangers A&B/B20 -35 0/18 {
& B48 l RAB 34 Valve Operating Enclosure Bay Room -15.5 2/0 "A"/854 )
Valve Operating Enclosure Bay Room -15.5 4/0 "B" B55A RAB 35 Safety Injection Pump Room B/B16 -35 10/0 RAB 36 Safety Injection Pump Room A/815 -35 10/0 RAB 37 Motor-Driven Emergency Feedpump -35 0/1 "A"/B49A RAB 38 Motor-Driven Emergency Feedpump -35 1/0 "B"/B49B RAB 39 General Equipment Area /B5, 12, 13, -35 0/10
& 49 Corridors & General Equip. Areas /B5, -35 0/28 1, 2, 3, 4, 39, 40, 41, 42, 44 & 46 East Corridor & General Equip. Areas / -35 0/15 B17, 23 & 25 BA Make-up Tank "A"/B38 -35 4/0 BA Make-up Tank "B"/B53A -35 4/0 RAB 40 Diese1' Storage Tank "A"/B50 -35 3/0 RAB 41 Diesel Storage Tank "B"/B52 -35 3/0 WATERFORD - UNIT 3 3/4 3-52
e O
I l
ATTACHMENT B
/
TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS TOTAL NUMBER OF INSTRUMENTS
- ELEVATION HEAT FLAME SM0KE ZONE ROOM NAME/ NUMBER (ft) (x/y) (x/y) (x/y)
- 1. REACTOR AUXILIARY BUILDING (Continued)
RAB 25 Equip. Access Area /226 (wing area) +21 15/0 RAB 27A H&V Room /124 +7 0/6 RAB 278 Electrical Area and Health Physics +7 0/35 Offices /122 RAB 27C I&C Room /120 +7 0/6 RAB 27D Communications Equip. Room /123 +7 1/0 RAB 31 Corridors and Passageways -4 0/24 Corridors on eastside -4 0/21 RAB 32 Wing Area westside - Auxiliary Com- -35 32/0 ponent Cooling Water Pump "A"/B53 &
and Pipe Penetration Area /B100 -4 Wing Area Center /853 and B100 -35 & 28/0
-4 Wing Area eastside-Component Cooling -35 31/0 Water Pump "B"/B53-and Pipe Penetration Area /B100 -4 RAB 33 S/D Cooling Heat Exchangers A&B/820 -35 0/18
& B48 RAB 34 Valve Operating Enclosure Bay Room -15.5 2/0 "A"/854 Valve Operating Enclosure Bay Room -15.5 4/0 "B" B55A RAB 35 Safety Injection Pump Room B/816 -35 10/0 RAB 36 Safety Injection Pump Roorr. A/B15 -35 10/0 RAB 37 Motor-Driven Emergency Feedpump -35 0/1 "A"/B49A RAB 38 Motor-Driven Emergency Feedpump -35 1/0 "B"/849B RAB 39 General Equipment Area /B5, 12, 13, -35 0/10
& 49 Corridors & General Equip. Areas /B5, -35 0/28 1, 2, 3, 4, 39, 40, 41, 42, 44 & 46 East Corridor & General Equip. Areas / -35 0/15 B17, 23 & 25 BA Make-up Tank " A"/B38 -35 4/0 BA Make-up Tank "B"/B53A -35 4/0 RAB 40 Diesel Storage Tank "A"/B50 -35 3/0 RAB 41 Diesel Storage Tank "B"/B52 -35 3/0 I
WATERFORD - UNIT 3 3/4 3-52 l
_u - - - - ---- - - - _
9 8
I NPF-38-03 4
- ~
DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-38-03 This is -a request to: revise Table 3.6-2 " Containment Isolation Valves" of :
Technical' Specification 3.6.3 " Containment Isolation Valves" by. correcting the. identification numbers of three valves. ,
Existing Specification-See Attachment "A" r Proposed Specification-See Attachment "B" Description Table 3.6-2 lists those containment isolation valves required operable by Technical Specification 3.6.3. In listing the valves, two unique valve
. numbers are supplied for each. For instance..the manual / remote manual SIS from HPSI loop 1A valve associated with penetration 55 carries the number 2SI-V1550Al (SI 225A). The first number (2SI-V1550A1) is the unique identifier _ assigned by the Architect-Engineer while the second number in parentheses '(SI 225A) is the unique identifier assigned by LP&L.
-The proposed change involves correcting typographical errors in three LP&L identifiers for manual / remote manual valves in Table 3.6-2. These changes are:
Penetration Existing Valve Proposed Number ' Number- Change 253 2CA-V600 (CVR'301B) 2CA-V600 (CVR 301A) 63 2SA-Vil4 (LRT 101) 2SA-Vll4 (LRT 109) 63 2SA-V604 '(LRT 102) 2SA-V604 (LRT 110)
Safety Analysis The proposed change described above shall be deemed to involve a-significant hazards-consideration if there is a positive finding'in any
- of the following areas:
- 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of any accident previously evaluated?
Response: NO-l The proposed change will place the correct LP&L valve number in Table 3.6-2 resulting in agreement between the Technical Specifica-1 tions and other plant documents. Therefore, the proposed change i
i !
I- !
l
i.
will.not involve-an increase ~in the probability or consequences of any accident previously evaluated.
- 12. .Will operation of the facility in accordance with this proposed change create .the possibility of a new or--different kind of accident from any accident previously evaluated?
Response: NO Substituting the correct valve numbers in Table 3.6-2 introduces
-no new perturbation to_the plant hardware or procedures. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any any accident previously evaluated.
- 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: NO
. Substituting the correct-valve numbers in Table 3.6-2 introduces no new perturbation to the plant hardware or procedures. Therefore, the proposed change will not involve a reduction in a margin of safety.-
The Commission has provided guidance concerning the application of standards for determining whether.a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards considerations. Example (i) relates to a purely administrative change to technical specifications, (i.e. a change to ~ achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature).
The purpose of the proposed change is to correct the identifying numbers for three containment isolation valves of Table 3.6-2 and bring the Technical Specification into conformance with other plant documents. Therefore, the proposed change is similar to example (1).
Safety and Significant Hazards Determination Based on the above Safety Analysis, it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10CFR50.91; and (2) there is a reasonable assurance that.the health and safety of the public will not be endangered by the ,tanosed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described-in the NRC Final Environmental Statement.
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F 6
O ATTACHMENT A
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:
- a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or
- d. Be in at least HOT STAN0BY within the next 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 />.
SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
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I l WATERFORD - UNIT 3 3/4 6-19
% TABLE 3.6-2 (Continued) b!' CONTAINMENT ISOLATION VALVES **'
E PENETRATION VALVE MAXIMUM NUMBER NUMBER FUNCTION ISOLATION TIME (Seconds)
E Z 6. Manual / Remote Manual (Continued) w 48 2HV-B190A (CAR 202A)* CARS Exhaust N.A.
51 2FS-V145A/B (FS405)* Refueling Cavity Purification Inlet N.A.
51 2FS-V144A/B (FS406)* Refueling Cavity Purification Inlet N.A.
53 2CA-V600 (CVR 301B)* Instrument H&V N.A.
w 55 2SI-V1550A1 (SI 225A)* SIS from HPSI Loop 1A N.A.
1 m 55 2SI-V1545B1 (SI 2258)* SIS from HPSI Loop 1A N.A.
E
56 2SI-V154082 (SI 2268)* SIS from HPSI Loop 18 N.A.
57 2SI-V1542A3 (SI 227A)* SIS from HPSI Loop 2A N.A.
57 2SI-V154783 (SI 227B)* SIS from HPSI Loop 2A N.A.
58 2SI-V1548A4 (SI 228A)* SIS from HPSI Loop 2B N.A.
58 2SI-V154484 (SI 2288)* SIS from HPSI Loop 28 N.A.
59 2SI-V1570 (SI344)* SIT Drain to RWSP N.A.
62 2FS-V165A/B (FS416) Refueling Cavity Drain N.A.
a
-m5{ TABLE 3.6-2 (Continued) 5 CONTAINMENT ISOLATION VALVES **
E PENETRATION VALVE MAXIMUM NUMBER NUMBER FUNCTION ISOLATION TIME (Seconds)
E Z 6. Manual / Remote Manual (Continued) ca 62 2FS-V164A/B (FS415) Refueling Cavity Drain N.A.
63 2SA-V114 (LRT101) ILRT Connection N.A.
63 2SA-V604 (LRT102) ILRT Connection N.A.
65 2SA-V609 (LRT202) ILRT Test Connection N.A.
, 65 2SA-V611 (LRT204)- ILRT Test Connection N.A.
as 65 2SA-V610 (LRT201) ILRT Test Connection N.A.
O N.A.
65 2SA-V612 (LRT203) ILRT Test Connection 65 2SA-V620 (LRT2011) ILRT Test Connection N.A.
65 2SA-V621 (LRT 2031) ILRT Test Connection N.A.
65 2CA-V601 (CVR 3018)* Instrument H&V N.A.
69 2SI-V1556 (SI 506A)* SI Hot Leg Injection N.A.
70 2SI-V1559 (SI 506B)* SI Hot Leg Injection N.A.
71 20W-V642 (CMU244)* Demineralized Water N.A.
a-ATTAGIMENT B
1
{ TABLE 3.6-2 (Continued) k CONTAINMENT ISOLATION VALVES **
E PENETRATION VALVE MAXIMUM
' FUNCTION ISOLATION TIME (Seconds)
NUMBER NUMBER E
Z 6. Manual / Remote. Manual (Continued) w 48 2HV-B190A (CAR 202A)* CARS Exhaust N.A.
51 2FS-V145A/B (FS405)* Refueling Cavity Purification Inlet N.A.
51 2FS-V144A/B (FS406)* Refueling Cavity Purification Inlet N.A.
53 2CA-V600 (CVR 301A)* Instrument H&V N.A.
w 55 2SI-V1550A1 (SI 225A)* SIS from HPSI Loop 1A N.A.
1 m 55 2SI-V154581 (SI 2258)* SIS from HPSI Loop 1A N.A.
E
56 2SI-V154082 (SI 226B)* SIS from HPSI Loop 1B N.A.
57 2SI-V1542A3 (SI 227A)* SIS from HPSI Loop 2A N.A.
57 2SI-V1547B3 (SI 227B)* SIS from HPSI Loop 2A N.A.
58 2SI-V1548A4 (SI 228A)* SIS from HPSI Loop 28 N.A.
58 2SI-V1544B4 (SI 2288)* SIS from HPSI Loop 2B N.A.
59 2SI-V1570 (SI344)* SIT Drain to RWSP N.A.
62 2FS-V165A/B (FS416) Refueling Cavity Drain N.A.
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{
m TABLE 3.6-2 (Continued)
CONTAINMENT ISOLATION VALVES **
PENETRATION VALVE MAXIMUM NUMBER NUMBER FUNCTION ISOLATION TIME (Seconds)
E
- 6. Manual / Remote Manual (Continued)
I 62 2FS-V164A/B (FS415) Refueling Cavity Drain N.A.
63 2SA-V114 (LRT109) ILRT Connection N.A.
l 63 2SA-V604 (LRT110) ILRT Connection N.A.
65 2SA-V609 (LRT202) ILRT Test Connection N.A.
65 25A-V611 (LRT204)- ILRT Test Connection N.A.
m 65 2SA-V610 (LRT201) ILRT Test Connection N.A.
l 65 2SA-V612 (LRT203) ILRT Test Connection N.A.
l 65 2SA-V620 (LRT2011) ILRT Test Connection N.A.
65 2SA-V621 (LRT 2031) ILRT Test Connection N.A.
65 2CA-V601 (CVR 301B)* Instrument H&V N.A.
69 2SI-V1556 (SI 506A)* SI Hot Leg Injection N.A.
70 2SI-V1559 (SI 506B)* SI Hot Leg Injection N.A.
71 20W-V642 (CMU244)* Demineralized Water N.A.
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