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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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REACT 0htCOOLANTSYSTEM OVERPRES$URE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION
. 3,4.8.3 Lw temperature overpressure protection shall be provided by:
1 a.
- At least one of the following overpressure protection systems being OPERABLE
1.
Both OPERABLE Shutdown Cooling (SOC) System suction line relief valves (SI-406A and SI-406B) each with a lift setting of less than or equal to 430 psia aligned to the Reactor Coolant
- System, or, t
2.
The Reactor Coolant System depressurized with an RCS vent of
~
. greater than or equal to 5.6 square inches.
b.
Establishing less than 100 F AT between RCS and steam generator temperature or ensuring the pressurizer water volume is less than 900 cubic feet (62.5%), prior to starting any reactor coolant pump.
APPLICABILITY:
MODE 4 when the temperature of any RCS cold leg is less than or equal to 285 F#, MODE 5, and MODE 6 with the reactor vessel head on, ACT10N:
a.
4 With one Shutdown Cooling System suction line relief valve inoper-able, restore the inoperable valve to OPERABLE status within 7 days, or be in at least COLD SHUTDOWN and depressurize and vent the RCS within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
! b.
With no Shutdown Cooling System suction line relief valves OPERABLE and-
- capable of providing Reactor Coolant System overpressure protection, either
1.
i Restore at least one Shutdown Cooling System suction relief valve to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or
! 2.
Be in at least COLD SHUTDOWN and depressurize and vent the RCS within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
, c.
In the event either the Shutdown Cooling System suction relief valves (s) or the RCS vent (s) are used to mitigate an RCS pressure transient, a l- Special Report shall be prepared and submitted to the Commission pur-suant to Spec.ification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the Shutdown Cooling System suction relief valve (s) or RCS vent (s) on the transient ,
and any corrective action necessary to prevent recurrence.
d.
The provisions of Specification 3.0.4 are not applicable.
C260 F during inservice leak and hydrostatic testing with Reactor Coolant System
. temperature changes restricted in accordance with Specification 3.4.8.19 ATERFORD - UNIT 3 .
3/4 4-34 AMENDMENT N0. 5
- - <v
REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS 4.4.8.3.1 Each ShtJtdown Cooling System suction line relief valve shall be dsmonstrated OPEP.ABLE:
i a. By verifying that each valve in tne suction path between the Reactor l Coolant System and the shutdown cooling relief valve is key-locked open in the control room at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
- b. At least every 30 months when tested pursuant to Specification 4.0.5.
4.4.8.3.2 The RCS vent (s) and all valves in the vent path shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent (s) is being used for ovsrpressure protection.
- Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
WATERFORD - UNIT 3 3/4 4-35
i !
l REACTOR COOLANT SYSTEM
) BASES PRESSURE / TEMPERATURE LIMITS (Continued)
, The maximum RT for all Reactor Coolant System pressure-retaining NDT
{ materials, with the exception of the reactor pressure vessel, has been j determined to be 90*F. The Lowest Service Temperature limit line shown on i Figures 3.4-2 and 3.4-3 is based upon this RT since Article NB-2332 of NOT i Section III of the ASME Boiler and Pressure Vessel Code requires the Lowest
, Service Temperature to be RTNDT + 100'F for piping, pumps, and valves. Below this temperature, the system pressure must be limited to a maximum of 20% of
- the system's hydrostatic test pressure of 3125 psia (as corrected for elevation
{
and instrument error).
The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pres-i surizer is operated within the design criteria assumed for the fatigue analysis
] performed in accordance with the ASME Code requirements.
- The OPERABILITY of the shutdown cooling system relief valve or an RCS vent opening of greater than 5.6 square inches ensures that the RCS will be protecteo from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal 4
to 285 F. Each shutdown cooling system relief valve has adequate relieving
, capability to protect the RCS from overpressurization when the transient is i
either (1) the start of an idle RCP with the secondary water temperature of the steam generator lets than or equal to 100*F above the RCS cold leg tempera-
- tures or (2) inadvertent safety injection actuation with injection into a water-solid RCS. The limiting transient includes simultaneous, inadvertent operation of three HPSI pumps, three charging pumps, and all pressurizer backup heaters in operation. Since SIAS starts only two HPSI pumps, a-20%-
margin is realized.
The restrictions on starting a reactor coolant pump in MODES 4 and 5, with one or more RCS cold legs less than or equal to 285 F, are provided to prevent RCS pressure transients caused by energy additions from the secondary system which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS I
will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary' water temperature of each steam generator is less than 100 F above each of the l RCS cold leg temperatures. Maintaining the steam generator less than 100*F
}
above eacn of the Reactor Coolant System cold leg temperatures (even with the RCS filled solid) or maintaining a large surge volume in the pressurizer ensures that this transient is less severe than the limiting transient consi- ,
dered above.
i
' The automatic isolation setpoint of the shutdown cooling isolation valves is sufficiently high to preclude inaovertent isolation of the shutdown cooling relief valves during a pressure transient.
5 WATERFORD - UNIT 3 B 3/4 4-10 r
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j REACTOR COOLANT SYSTEM i OVERPRESSURE PROTECTION SYSTEMS LIMI. TING CONDITION FOR OPER ATION _
3.4.8.3 Two Shutdown Cooling (SDC) System suction line relief valves (SI-40GA and SI-40GB) shall be OPERABLE with a lif t setting of less than or equal to 430 psia.
APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 285'F', MODE 5, and MODE G when the head is on the reactor vessel and the RCS is not vented through a 5.6 square inch or larger vent.
ACTION:
- a. With one SDC System suction line relief valve inoperable in MODE 4, restore the inoperable valve to OPERABLE status within 7 days, or depressurize and vent the RCS through at least a 5.G square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
- b. With one SDC System suction line relief valve inoperable in MODES 5 or G, either (1) restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and venting of the RCS through at least a 5.6 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
- c. With both SDC System suction line relief valves inoperable, complete depressurization and venting of the RCS through at least a 5.6 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
- d. In the event either the SDC System suction line relief valve (s) or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification G.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the SDC System suction line relief valve (s) or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence,
- e. The provisions of Specification 3.0.4 are not applicable.
260 F during inservice leak and hydrostatic testing with Reactor Coolant System temperature changes restricted in accordance with Specification 3.4.8.lg.
ItEACTOlt COOLANT SYSTEM Sl!ItYEI1 2LANJCE_ld;Qlli11EMENTS __ _
4.4.S.3.1 Each SDC System suction line relief valve shall be demonstrated Ol' Ell AllLE:
- a. by verifying in the control room at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that each valve in the suction path between the IlCS and the SDC relief valve is open,
- b. At least every 30 months when tested pursuant to Specification 4.0.5.
4.4.8.3.2 With the ItCS vented per ACTIONS a, b, or c, the ItCS vent (s) and all valves in the vent path shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />".
Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
REACTOR COOLANT SYSTEM BASES l
PRESSUREA EMPERATURE LIMITS (Continued)
The maximum RT for all Reactor Coolant System pressure-retaining NOT materials, with the exception of the reactor pressure vessel, has been determined to be 90*F. The Lowest Service Temperature limit line shown on Figuru 3.4-2 and 3.4-3 is based upon this RTNDT since Article NB-2332 of Section III of the ASME Boiler and Pressure Vessel Code requires the Lowest Service Temperature to be RTNOT + 100*F for piping, pumps, and valves. Below this temperature, the system pressure must be limited to a maximum of 20% of the system's hydrostatic test pressure of 3125 psia (as corrected for elevation and instrument error).
The limitations imposed on the pressurizer heatup ano cooldown rates and spray water temperature dif ferential are provided to assure that the pres-surizer is operated within the design criteria assumed for the fatigue analysis performeo in accordance with the ASME Code requirements, The OPERABILITY of the shutdown cooling system relief valve or an RCS vent ooening of greater than 5.6 square inches ensures that the RCS will be protectec from pressure transients which could exceed the limits of Appendix G to 285'c.
to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal Each shutdown cooling system relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 100*F above the RCS cold leg tempera-tures or (2) inaavertent safety injection actuation with injection into a water solid RCS. The limiting transient includes simultaneous, inadvertent operation of three HPSI pumps, three charging pumps, and all pressurizer backuo heaters in operation.
margin is realized. Since SIAS starts only two HPSI pumps, a 20% _ _
c lord locps [(lccl In MODE)
The restrictions on starting a reactor coolant pump in MODES 4 and*S, A with one or more RCS cold legs less than or equal to 285'F, are provideddo .
nDO:
prevei.t system vnich RCScouldpressureexceed thetransients caused limits of Appendix G to 10byCFR energy Part 50.additions from the N se The RCS n will be protected against overpressure transients and will not exceed the , )
limits of Appendix G by restricting starting of the RCPs to when tne secondary Qvc4ic6c,c water temperature of each steam generator is less than 100*F above each of the g '3 g '
RCS cold leg temperatures. Maintaining the steam generator less than 100 F ;
above each of the Reactor Coolant System cold leg temperatures'(even with the j RCS filled solid) or maintaining a large surge volume in the pressurizer ensures dered above.
that this transient is less severe than the limiting transient consi-The automatic isolation setpoint of the shutdown cooling isolation valves is sufficiently high to preclude inadvartent isolation of the shutdown cooling relief valves during a pressure transient.
WAT F ORD - UNIT 3 8 3/4 4-10 l