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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20138M5091997-02-13013 February 1997 Proposed Tech Specs Section 15.3.3. Re Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray ML20134L9791997-02-12012 February 1997 Proposed Tech Specs Re Relocation of Turbine Overspeed Protection ML20134A3661997-01-24024 January 1997 Proposed Tech Specs 15.5.4 Re Fuel Storage ML20134A3121997-01-21021 January 1997 Proposed Tech Specs 15.6.11, Radiation Protection Program ML20133N4021997-01-16016 January 1997 Proposed Tech Specs 15.3.2 Re Chemical & Volume Control Sys, 15.3.3 Re Emergency Core Cooling Sys,Auxiliary Cooling Systems,Air Recirculation Fan Coolers & Containment Spray & 15.3.8 Re Refueling ML20133N6321997-01-16016 January 1997 Proposed Tech Specs 15.1-6,15.2.2 Re Safety Limit,Reactor Coolant Sys Pressure,Ts 15.3.1-9,TS 15.3-10,TS 15.3.4-2 & TS 15.3.4-3 ML20133L1071997-01-13013 January 1997 Proposed Tech Specs 15.3.15 Re Overpressure Mitigating Sys & 15.3.1 Re Reactor Coolant Sys ML20133E5531997-01-0606 January 1997 Proposed Tech Specs 15.4.1, Operational Safety Review, Changing Ref Note 20 from TS 15.3.10.B to TS 15.3.10.E to Match TS Section Previously Containing Hot Channel Factor Limit ML20132F3471996-12-19019 December 1996 Proposed Tech Specs Improving Sections TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20132C3741996-12-12012 December 1996 Proposed Tech Specs Section 15.3.3 Re Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers & Containment Spray ML20135A8921996-12-0202 December 1996 Proposed Tech Specs 15.3.14 & 15.4.15 Re Fire Protection Sys ML20135A8431996-12-0202 December 1996 Proposed Tech Specs 15.3.10 Re Control Rod & Power Distribution Limits & 15.4.1 ML20129F2101996-09-30030 September 1996 Proposed Tech Specs Modify TS Section 15.3.3, Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers, & Containment Spray,To Incorporate Allowed Outage Times ML20129C0771996-09-19019 September 1996 Proposed Tech Specs Revising Section 15.3.15, Overpressure Mitigating Sys & Section 15.3.1, Rcs ML20117D2651996-08-22022 August 1996 Proposed Tech Specs Re Licensed Power Level for Plant ML20116N1341996-08-15015 August 1996 Proposed Tech Specs,Consisting of Suppl to Change Request 170,modifying TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20116G4891996-08-0505 August 1996 Proposed Tech Specs Modifying 15.2.3 & 15.5.3 of Change Request 188 & 15.2.1,15.2.3 & 15.3.1.G of Change Request 189 Supporting SEs ML20116D7471996-07-29029 July 1996 Proposed Tech Specs Re Health Physics Manager Qualifications for Plant ML20112F7341996-06-0404 June 1996 Proposed Tech Specs 15.2.3, Limiting Safety Sys Settings & Protective Instrumentation & 15.5.3, Design Features - Reactor ML20117K1991996-06-0404 June 1996 Proposed Tech Specs 15.2.1, Safety Limit,Reactor Core, 15.2.3, Limiting Safety Sys Settings,Protective Instrumentation & 15.3.1.G, Operational Limitations to Maintain Safety Margin for Unit 2 W/Replacement SGs ML20112E2441996-05-29029 May 1996 Proposed Tech Specs 15.1 Re definitions,15.3.6 Re Containment sys,15.4.4 Re Containment Tests & 15.6 Re Administrative Controls ML20108D1531996-04-29029 April 1996 Proposed Tech Specs Re Removal of Fire Protection Requirements ML20108A0011996-04-24024 April 1996 Proposed Tech Specs Section 15.7 RETS Re Removing Items Identified in GLs 89-01 & 95-10 as Being Procedural Details & Relocating Items to Appropriate Documents ML20149D9691996-03-20020 March 1996 Proposed Tech Specs,Providing Corrected Page to Bases for TS 15.3.1 ML20100L3891996-02-27027 February 1996 Proposed Tech Specs,Consisting of Change Request 186, Modifying TS Section 15.4.4, Containment Tests, Spec I.C.1 to State That Type a Tests Shall Be Conducted Per 10CFR50, App J Modified by Approved Exemptions 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] |
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l 's l TABLE OF CONT ENTS Section Iills Egge 15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Def'mitions 15.2.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3 1 15.3 Limiting Conditions for Operation 15.3.0 15.3.0 General Consideration 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.; Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 15.3.6 Containment System 15.3.6-1 15.3.7 Auxiliary Electrical System 15.3.7-1 15.3.8 Refueling 15.3.8-1 15.3.9 Efiluent Releases 15.3.9 1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In-Core Instrumentation 15.3.11-1 15.3.12 Control Room Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressor(Snubbers) 15.3.13-1 15.3.14 Fire Protection System 15.3.14-1 15.3.15 Low Temperaturs_ Overpressure Protection 5"::!ge.:!r.; System 15.3.15-1 15.3.16 Resctor Coolant System Pressure Isolation Valve 15.3.16-1 15.4 Surveillance Requirement 15.4.1 15.4.1 Operaticaal Safety Review 15.4.1-1 15.4.2 In-Service ir spection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 l 15.4.4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment
- Cooling system Tests 15.4.5-1 l 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 l
15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 15.4.9 Reactivity Anomalies 15.4.9-1 15.4.10 Operational Environmental Monitoring 15.4.10-1 15.4.11 Control Room Emergency Filtration 15.4.11-1 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 15.4.13 Shock Suppressors(Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane Lifting Devices 15.4.14-1 15.4.15 Fire Protection System 15.4.15-1 15.4.16 Reactor Coolant System Pressure isolation Valves !
Leakage Tests 15.4.16-1 Unit 1 - Amendment No.-M 15-i ,
Sep w h 6 085 Unit 2 - Amendment NoA40 9609240007 960919 PDR ADOCK 05000266 P PDR
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- 5. Pressurizer Power-Operated Relief Valves (PORV) and PORY Block Valves If a unit is placed in the HOT SHUTDOWN condition in accordance with the requirements of Specificatinns a(1) through a(5) below, then the reactor coolant system temperature should be i maintained greater than S " r p: :r?--'S- '--- . _= fr S in:=!= p.-_ _::= 'm= ,
6f :f i- 9;;= 15.3.' ' 355'F. If cooldown to less than this temperature is required in order to ;
take action to restore the inoperable component (s) to service, then the requirements of Specification -
15.3.15 apply.
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- a. Two PORVs and their associated block valves shall be operable.
(1) If one or both PORVs are INOPERABLE due to seat leakage in excess of that allowed ,
in Specifications 15.3.1.D, within one hour either restore the PORVs to an operable status or close the associated block valves (s). If these conditions cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
'I (2) If one PORV is INOPERABLE due to causes other than excessive seat leakage, within
, 1 one hour either restore the PORV to OPERABLE status or close its associated block l L valve and remove power from the block valve. If the PORV cannot be restored to l
l' operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, place the unit in a HOT SHUTDOWN condition i within the next six hours.
(3) If both PORVs are TNOPERABLE due to causes other than excessive seat leakage, within one hour restore at least one PORV to OPERABLE status. If this e udition i
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1 cannot be met, close the associated block valves, remove power from the block valves i and place the unit in a HOT SHUTDOWN condition within the next six hours.
(4) If one block valve is inoperable, within one hour either restore the block valve to OPERABLE status or place the associated PORV in manual control. Restore the block valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If these conditions cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
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Unit I - Amendment 45 15.3.1-3 Septembw 20, !""
Unit 2 - Amendment 459 4
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- l 15.3.15 OVERPRESSURGM"!OATING LOW TEMPERATURE OVERPRESSURE PROTECTION l 1
SYSTEM OPEP).T!ONS l Apolicability Applies to operability of the low temperature overpressure protection (LTOP) r t!g::!ng system when the reactor coolant system temperature i: !:= i= 6: r tmer ::mp= ::= f= 6: in=r!= p==== :=: < 355'F.
Objective i
To specify functional requirements and limiting conditions for operation on the use of the pressurizer power
)
operated relief valves when used as part of the ;=p== = r::!g:i:g LTOP system and to specify further limiting conditions for operation when the reactor coolant system is operated : "h::: : p== = :b=Png /c!:m: i- *he p===!= at low temperatures.
Specification
! A. System Operability l 1. Except as specified in 15.3.15.A.2 below, the := p===!=:! n -4: gating LTOP system shall be operable whenever the reactor coolant system is not open to the atmosphere and the temperature is
!:= in: 1: r "=== p===!=:!: ::=pr:::= f= 6: in=re!= p==== :=:, = :p=!'ied in i Fign= !5.3.' ' < 355'F Operability requirements are:
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- a. Both pressurizer power operated relief valves operable at a setpoint of $425 psig.
- b. Both power operated relief valve block valves are open.
- 2. The requirements of 15.3.15.A.1 may be modified as specified below;
- a. With one PORV inoperable while reactor coolant system temperature is >200*F but !:= i=
$: r:"m n p===!=t!= ::mpr:::= f= i: in=r!= p==== :=:_<;355*E, either restore the inoperable PORV to operable status within 7 days, or depressurize and vent reactor coolant system within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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- b. With one PORV inoperable while reactor coolant system temperature is 5200'F, either i
restore the inoperable PORV 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 depressurize and vent the reactor coolant system 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 power operated relief valves inoperable while the reactor coolant system I l temperature i: !:= i= h: r:"m = p===!=:!= *:mpe=::= f= 'h: i .=ri= presswe
! lest < 355'F. the reactor coolant system must be depressurized and vented within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 3. If the reactor coolant system is vented per Specification 15.3.15.A.2.a b, or c, the pathway must be verified at least once every 31 days when it is provided by a non-isolable pathway or by a valve (s) that is locked, sealed, or otherwise secured in the open positica; otherwise, verify the pathway every !
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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l Unit 1 - Amendment No.4M 15.3.15-1 F:p::m b 30,199:
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- Unit 2 - Amendment No.4M i
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B. Ad'ditional Limitations
- 1. "S= 6: =:: :: = !=! y:!= !: :: p= ::i: :!==ph:= =d i:!:=p:=t = cf =: c: be*
==!= :: !=! y ::= =!d !:g: = C275"F When LTOP is reauired to be enabled by Soecification 15.3.15.A.1, no more than one high pressure safety injection pump shall be operable. He second l 1
high pressure safety injection pump shall be &==: =t:d endered inoperable whenever the temperature of one or both reactor coolant system cold legs is s27&*F- < 355'F by verifying that the l
motor circuit breakers have been removed from their electrical power supply circuits or by verifying
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that the discharge valves from the high pressure safety injection pumps to the reactor coolant system are shut and that power is removed from their operators.
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- 2. A reactor coolant pump shall not be started when the reactor coolant system temperature is bs-than !
6: r: ' r ::=p:=t = for 'h: !=:re!= p==== != < 355'f_unless:
- a. There is a pressure absorbing volume in the pressurizer or in the steam generator tubes or
- b. The secondary water temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system.
- 3. Only one reactor coolant numn shall be onerated when the reactor coolant system temnerature is
< 125'F.
Basis The Ov: p==rir!! :!!;;*ieg law Temnerature Overnressure Protection System consists of a dwerse i redundant means of relieving pressure during periods of water solid operation and when the Isattor coolant system l temperature i: 5:! n i: =!= p:--5:d te p -fem i: p:: rj ;y:!:r '=!: !=t < 355'F. His method of water relief utilizes the pressurizer power operated relief valves (PORV's). He PORV's are made operational for low j pressure relief by utilizing a dual setpoint where the low pressure circuit is energized and de-energized by the operator with a keylock switch depending on plant conditions. The logic required for the low pre.csure setpoint is in l addition to the existing PORV actuation logic and will not interfere with existing automatic or manual actuation of -
l l the PORV's. The OPERABILITY of the PORVs is determined on the basis of their being capable of automatically mitigating an overpressure event during low temperature operation. The LTOP setnoint of 425 nsig is valid through an inside surface neutron fluence of the limiting reactor vessel material ofless than or caual to 2.05 x 10%1Im3 (E > 1.0 Mevl l During plant cooldown prior to reducing reactor coolant system temperature b:! n 6: r: : tm !:=p:=tu=
r
- !! n' 5!: f= 'h: ! =r/i= p==== !=t to 355'F. the operator under administrative procedures shall place the 1
keylock switch in the " Low Pressure" position. This action enables the Low Temnerature Overpressure Protection
:!!;:!! g System. The redundant PORV channels shall remain enabled and operable while the O= p==== ;
t':!!g !!= LIQP_ system is required to be in operation.
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l Unit 1 - Amendment No.465 15J.15-2 c:p'=-b:: 30, ! 904 Unit 2 - Amendment No.469 l
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- l The reactor coolaat system is defined as vented if there is an opening in the reactor coolant system pressure boundary to atmosphere or the pressurizer relief tank that has an equivalent system pressure relieving capability as a l PORV, Some examples of such openings include an open or removed PORV, open steam generator or pressurizer manways, a removed pressurizer safety valve, and the top of the reactor vessel when the reactor vessel head has been unbolted or removed.
The mass input transient used to determine the PORV setpoint assumedg a worse case transient of a single high 1 pressure safety injection pump discharging to the reactor coolant system while the system is solid. Therefore, when S: ::::ter :::!::: g:!r !: !:= S:: 275*F LTOP is reauired to be enabled. only one high pressure safety injection ;
pump shall be operable at any time except when the reactor coolant system is open to the atmosphere.
The heat input transient used to determine the PORV setpoint assumes a temperature difference between the reactor coolant system and the steam generator of 50 F. Therefore, before starting a reactor coolant pump when the reactor !
coolant system is solid, the operator shallisnsure that the secondary temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system unless a pressure absorbing volume has been verified to i
exist in the pressurizer or steam generator tubes.
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d Unit 1 - Amendment No.445 15.3.15-3 Eg:=h 30,104 3
Unit 2 - Amendment No.459
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