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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] |
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NPF-38-219 ATTACHMENT A EXISTING SPECIFICATIONS I
9907230128 990719
-PDR ADOCK 05000382 P PDR
' EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 2. A visual inspection of tne safety injecti<>n system sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trath racks, screens, etc.) show no evidence of structural distress or corrosion.
- 3. Verifying that a minimum total of 380 cubic feet of granular l trisodium phosphate dodecahydrate (T!P) is contained within the TSP storage baskets.
- 4. Verifying that when a representative sample of 13.07 i 0.03 grams of TSP from a TSP storage basket is submerged, without agitation, in 4 i 0.1 liters of 120 i 10*F water borated to 3011 1 30 ppe, the pH of the mixed solution is raised to greater than or equal to 7 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- e. At least once per 18 months, during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.
- 2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
- a. High pre'ssure safety injection pump.
- b. Low pressure safety injection pump.
- 3. Verifying that on a recirculation actuation test signal, the low pressure safety injection pumps stop, the safety injection system sump isolation valves open.
- f. By verifying that each of the following pumps required to be OPERABLE performs as indicated on recirculation flow when tested pursuant to Specification 4.0.5:
- 1. High pressure safety injection pump differential pressure greater than or equal to 142g psid.
- 2. Low pressure safety injection pump discharge pressure greater than or equal to 177 psig.
WATERFORD UNIT 3 3/4 5-5 AMENDMENT NO. 64,127,
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS .fContinued)
With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactmty condition of the reactor and the limited core cooling requirements.
The trisodium F-:+?:': dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is prowded to menemme the possibility of cormoion creciong of certain metal components during opersbon of the ECCS followng a LOCA. The TSP provides this protechon by dissolwng in the sump water and causing its final pH to be remed to greater than or equal to 7.0. The requirement to desolve a representatwo sample of TSP in a sample of water borated to be repc:::ns of post-LOCA sump condibons prowdes assurance that the stored TSP will dissolve in borated water at the postulated post-LOCA temperatures. A boron concentration of 3011 ppm boron is postulated to be representative of the highest post-LOCA i sump boron concentration. Post-LOCA sump pH will remain between 7.0 and 8.1 for the I maximum (3011 ppm) and mirumum (1504 ppm) boron concentrations calculated using the maximum and minimum post-LOCA sump volumes and conservatively assumed maximum and minimum source boron concentrabons.
With the excephon of systems in operation, the ECCS pumps are normally in a standby, nonoperstmg mode. As such, flow path piping has the potenbal to develop voids and pockets of entramed gases. Maintaming the piping from the ECCS pumps to the RCS full of water ensures that the system will perform property, inlochng its full capacity into the RCS upon demand. This will prevent water hammer, pump cavitabon, and pumping noncondensible gas (e.g., sir, rwtrogen, or hydrogen) into the reactor vessel following an SIAS or dunng SDC. The 31 day frequency takes into considersbon the gradual nature of gas accumulation in the ECCS piping and the adequacy of the procedural controls govemmg system operation.
The Surveillance Requirements gesed to ensure OPERABILITY of each component ensure that at a merumum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintamed. Surveillance Requirements for throttle valve position stops and flow balance testing prowde assurance that proper ECCS flows will be mamtsined in the event of a LOCA. Mantenance of proper flow resistance and pressure drop in the piping system to each ingschon point is necessary to: (1) prevent total pump flow fmm exceeding runout condstions when the system is in its meimum reestance configurshon, (2) prowde the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an ee=f*=hla level of total ECCS flow to all irjoction points equal to or above that assumed in the ECCS-LOCA analyses, i The requirement to verify the mirumum pump decharge pressure on recirculabon flow ensures that the pump performance curve has not degraded below that used to show that the pump exceeds the desagn flow condibon assumed in the safety analyse and is consstent with the requirements of ASME Sechon XI.
8 3/4 5 2 AMENDMENT NO. 1 0 .130,147 WATERFORD - UNIT 3
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NPF-38-219 ATTACHMENT B PROPOSED MARKED-UP SPECIFICATIONS l
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' EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE0UIREMENTS (Continued)
- 2. A visual inspection of the safety injection system sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
- 3. Verifying that a minimum total of 380 cubic feet of granular l trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
- 4. Verifying that when a representative sample of 13.07 i 0.03 grams of TSP from a TSP storage basket is submerged, without agitation, in 4 i 0.1 liters of 120 f 10*F water borated to 3011 i 30 ppe, the pH of the mixed solution is raised to greater than or equal to 7 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- e. At least once per 18 months, during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.
- 2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
- a. High pressure safety injection pump.
- b. Low pressure safety injection pump.
- 3. Verifying that on a recirculation actuation test signal, the low pressure safety injection pumps stop, the s;fety injection
' system sump isolation valves open.
- f. By verifying that each of the following pumps required to be OPERABLE performs as indicated on recirculation flow when tested pursuant to Specification 4.0.5:
- 1. High pressure safety injection pump differential pressure greater than or equal to 1429 psid.
.h%eDh n or q7al!o i 1
IG8 pdid, l
WATERFORD UNIT 3 3/4 5-5 AMENDMENT NO. 64,t27, 1
,. EMERGENCY CORE COOLING SYSTEMS ,
BASES ECCS SUBSYSTEMS (Continued)
With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure considershon on the basis of the stable reactivity condition of the reactor and the limited core cooling requrements. .
The tnsodium phosphate dodecahydrate (TSP) stored in desolvmg baskets located in the containment basement is provided to mammize the possitnlity of corrosen cracking of certain metal components dunng opersbon of the ECCS followmg a LOCA. The TSP provides this p,v;.;0en by dissolving in the sump water and causmg its final pH to be remed to greater than or i equal to 7.0. The requrement to dissolve a representabve sample of TSP in a sample of water borated to be rep. :::Ms of post-LOCA sump conditions provides assurance that the stored TSP will dissolve in borated water at the postulated post-LOCA temperatures. A boron )
concentration of 3011 ppm boron is postulated to be representabve of the highest post-LOCA sump boron conoontration Post-LOCA sump pH will remain between 7.0 and 8.1 for the maximum (3011 ppm) and minimum (1504 ppm) boron concentrabons calculated using the maximum and minimum post-LOCA sump volumes and conservabwely assumed maximum and minimum source boron concentrabons.
With the excephon of systems in operation, the ECCS pumps are normally in a standby, nonoperating mode. As such, flow path popmg has the potenbal to develop voids and pockets of entramed gases. Maintaining the (# ng i from the ECCS pumps to the RCS full of water ensures that the system will perform property, irischng its full capacity into the RCS upon demand. This will prevent water hammer, pump cavitaten, and pumping noncondensible gas (e.g., sir, nitrogen, or hydrogen) into the reactor vessel following an SlAS or dunng SDC. The 31 day frequency takes into consideration the gradual nature of gas accumulabon in the ECCS piping and the adequacy of the procedural controis govemmg systern opershon.
The Surveillance Requrements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumphons used in the safety analyses are met and that i subsystem OPERABILITY is mentamed. Surveillance Requrements for throttle vahre position j stops and flow belance testing provide assurance that proper ECCS flows wiu be mamtained in the event of a LOCA. Mactonance of proper flow reestance and pressure drop in the piping l system to each ingschon point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its maimum resetance conAguration, (2) provide the proper flow spilt between injechon points in accordance with the assumphons used in the ECCS-LOCA analyses, and (3) provide an =~=fe level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
SW eAa(
The requirement to venty the mirumum pump preesure on recrculation flow ensures that the pump performance curve has not dMbolow that used to show that the pump exceeds the design flow condinon assumed in the safety analyse and is consstent with
. the requrements of ASME Sechon XI.
WATERFORD - UNIT 3 B 3/4 5 2 AMENDMENT NO. 07.0^147
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NPF-38-219 ATTACHMENT C t
PROPOSED SPECIFICATION 1
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, s EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 2. A visual inspection of the safety injection system sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
- 3. Verifying that a minimum total of 380 cubic feet of granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
- 4. Verifying that when a representative sample of 13.07 i 0.03 grams of TSP from a TSP storage basket is submerged, without agitation, in 4 i 0.1 liters of 120 i 10 F water borated to 3011 i 30 ppm, the pH of the mixed solution is raised to greater than or equal to 7 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- e. At least once per 18 months, during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.
- 2. Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
- a. High pressure safety injection pump.
- b. Low pressure safety injection pump.
- 3. Verifying that on a recirculation actuation test signal, the low pressure safety injection pumps stop, the safety injection system sump isolation valves open.
- f. By verifying that each of the following pumps required to be OPERABLE performs as indicated on recirculation flow when tested pursuant to Specification 4.0.5:
- 1. High pressure safety injection pump differential pressure greater than or equal to 1429 psid.
- 2. Low pressure safety injection pump differential pressure greater than or equal to 168 psid.
WATERFORD - UNIT 3 3/4 5-5 AMENDMENT NO. 64,-4N I
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/ k EMERGENCY CORE COOLING SYSTEMS BASES EC. CS SUBSYSTEMS (Continued)
I With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
I The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain i metal components during operation of the ECCS following a LOCA. The TSP provides
) thisprotection by dissolving in the sump water and causing its final pH to be raiseo to greater '
l than or equal to 7.0. The requirement to dissolve a representative sample of TSP in a sample of l water borated to be representative of post-LOCA sump conditions provides assurance that the l stored TSP will dissolve in borated water at the postulated post-LOCA temperatures. A boron )
l concentration of 3011 ppm boron is postulated to be representative of the highest post-LOCA !
l sump boron concentration. Post LOCA sump pH will remain between 7.0 and 8.1 for the j maximum (3011 ppm) and minimum (1504 ppm) boron concentrations calculated using the maximum and minimum post-LOCA sump volumes and conservatively assumea maximum and minimum source boron concentrations.
With the exception of systerns in operation, the ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand. This will prevent water hammer, pump cavitation, and pumping noncondensible gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an SIAS or during SDC. The 31 day frequency takes into consideration the gradual nature of gas accumulation in the ECCS piping l and the adequacy of the procedural controls governing system operation.
l The Surveillance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance Requirements for throttle valve position l stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping l system to each injection point is necessary to: (1) prevent total pump flow from exceeding I runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
The requirement to ve ifv the minimum pump differential pressure on recirculation flow I ensures that the pump pea . .urve has not degraded below that used to show that the i pump exceeds the desigt ion assumed in the safety analysis and is consistent with i the requirements of ASME: *o 41.
WATERFORD - UNIT 3 B 3/4 5-2 AMENDMENT NO. +27,430,-147 l
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DOCURMENT DWID>R I
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i INSERTED BY DOCUMENT RECEIPT & PROCESSING Y i ,
NUD00S FORM 123
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