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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4511996-04-24024 April 1996 Proposed Tech Specs 3.11.B/4.11.B Re Crescent Area Ventilation ML20101H6741996-03-27027 March 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101H3821996-03-22022 March 1996 Proposed TS Table 3.2-2 Re Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20101F8411996-03-22022 March 1996 Proposed Tech Specs,Implementing BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20097A2271996-02-0101 February 1996 Proposed Tech Specs,Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2991996-01-25025 January 1996 Proposed Tech Specs Re EDGs Surveillance Testing ML20097J6691996-01-25025 January 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24- Month Operating Cycles ML20095F7091995-12-14014 December 1995 Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code ML20094R6981995-11-30030 November 1995 Proposed Tech Specs,Extending Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6641995-10-25025 October 1995 Proposed Tech Specs Extending Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5401995-09-15015 September 1995 Proposed Tech Specs Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6561995-07-21021 July 1995 Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] |
Text
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Attachment til -
REVISED TECilNICAL SPECIFICATION PAGES CORE AND CONTAINMENT COOLING SYSTEM INITIATION AND CONTROL INSTRUMENTATION (JPTS-96-002)
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1 I New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 9002200241 900206 PDR ADOCK 05000333 P PDR *
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JAFNPP a
a TABLE 3 2-2 .
CORE AND CONTAINRENT COOLING SYSTEM INITIATION AND CONTROt. INSTRURENTATION OPERABILITY REQUWtERENTS Minimum No. of Total Number of Operable instrument instrument Channels item Channels Per Provided by Design No. Trio System Trio Function Trio Level Settino for Both Trio Systems Remarks 1
e 2 Reactor Low-Low 2126.5 in. above TAF 4 (HPCI & RCIC) Initiates HPCI, RCIC, and (Notes 1,11) Water Level SGTS.
2 2 Reactor Low-Low- 218 in. above TAF 4 (Core Spray & RHR) Irutiates Core Spray, RHR (LPCI),
(Notes 2,3,11) Low Water Level and Emergency Diesel Generators.
4 (ADS) Initiates ADS (if not inhabited by ADS overnde switches), in conjuncbon with Coisini.tcry Low Level,120 second delay and RHR (LPCI) or Core Spray pump discharge pressure interlock.
3 2 Reactor High Water. 5 222.5 in. above TAF 2 (Note 16) Trips HPCI turbine.
(Notes 4,12) Level 4 2 Reactor High Water 5 222.5 in. above TAF 2 (Note 16) Closes RCIC steam supply (Notes 4,12) Level ' valve.
5 1 Reactor Low Level 2 0 in. above TAF 2 Prevents inadvertent (Notes 5,11) (inside shroud) Opci.i;cn of cont &sient spray dcring accident condition.
6 2 Containment High 1 < p < 2.7 psig 4 Prevents inadvertent operation (Notes 5,11) Pressure of ccirt.;rwwnt spray during acc; dent ccrid7 don.
l Amendment No. 19,40,67,Si,119,227, 66
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JAFNPP s
TABLE 3.2-2 (Contd) .
CORE AND CONTAINMENT COOLING SYSTEM INITIATION AND CONTROL NA flON OPERABILITY REQUIRFasFNTS Minimum No. of Total Number of Operable Instrument Instrument Channels item ChanneIs Per Provided by Design No. Trio System Trio Function Trio Level Settina for Both Trio Systems Remarks 7 1 Reactor Low Level > 177 in. above TAF 2 Confirmatory low water level for ADS actuation.
(Notes 3,11) 8 2 Drywell High < 2.7 psig 4 Initiates Core Spray, RHR (Notes 1, 2,11) Pressure (LPCI), HPCI and SGTS.
9 2' Reactor Low Pressure > 450 psig 4 Permits opening Core (Notes 6,11)
Spray and RHR (LPCI) injection valves.
10 1 Reactor Low Pressure 50 < p <- 75 psig 2 Permits closure of RHR (Notes 2,12)
(LPCI) injection valves while in shutdown cooling in conjunction with PCIS signal.
Core Spray Pump 11 i O.6 sec. 1 (Note 16) initiates starting of f 11 1 core spray pump.
(Notes 7,11) Start Timer (ea'ch loop) (each foop) 12 1 RHR (LPCI) Pump (Notes 7,11) Start Timer 1st Pump (A Loop) 1.0 + 0.5 (-) O sec. 1 (Note 16) Starts 1st Pump (A Loop) 1st Pump (B Loop) 1.0 + 0.5 (-) O sec. 1 (Note 16) Starts 1st Pump (B Loop) 2nd Pump (A Loop)- 6.0 t 0.5 sec. 1 (Note 16) Starts 2nd Pump (A Loop) l l 2nd Pump (B Loop) 6.0 0.5 sec. 1 (Note 16) Starts 2nd Pump (B Loop' Amendment No. 19,49,67,94,*19,227, 67
O JAFNPP 6 TABLE 3 2-2 (Confdl .
C0RE AND CONTAINEENT COOLING SYSTEM INITIATION AND CCWTROL INSTRUGENTATION OPERABE lTY REQUWWFREFNTS Minimum No. of Total Number of Operable Instrument Instrument Channels item ' Channels Per Provded by Desgn No. Trio System Trio Function Trio Level Settino for Both Trio Systems Remarks 13 1 Auto Blowdown Timer 120 sec. i 5 sec. 2 initiates ADS (if not inhibited (Notes 8,11) ')y ADS ovenide switches).
14 4 RHR (LPCI) Pumr 125 psig i 20 psig 8 Permits ADS actuabon (Notes 8,11) Discharge Pressu'e Interlock 15 2 Core Spray Pump 100 psig i 10 psig 4 Permits ADS actuabon.
(Notes 8,11) Discharge Pressure Interlock 2 Condensate Storage 2 59.5 in. above 2 (Note 16) Transfers RCIC pump 16 (Notes 9,11) Tank Low Level tank t:ottom suction to suppiessiori
(= 15,600 gal. avail) chamber.
Condensate Storage z 59.5 in. above 2 (Note 16) Transfers HPCI pump 17 2 (Notes 9,11) Tank Low Level tank bottom suchon to suppression
(= 15,600 gal. avail) cf iriber.
2 Suppression Chamber s 6 in. above normal 2 (Note 16) Tunsters HPCI pump 18 (Notes 9,11) level suchon to suppression
~ High Level chamber.
Amendment No. #9, MS, 94,134,227, 68 i
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JAFNPP TABLE 3 2-2 (Contd) .
CORE AND CONTAINGENT COOUNG SYSTEM INITIATION AND CONTROL INSTRUENTATION OPERADIUTY REN Minimum No. of Total Number of Operable instrument Instrument Channels item Channels Per Provided by Design No. - Trio System Trio Function " Trio Level Settino for Both Trio Systems Remarks 19 (2 per 4kV bus) 4kV Emergency Bus 110.610.8 4 Insbates both 4kV Emergency l secondary volts Bus Undervoltage Timers.
(Note 10) Undervoltage Relay (Degraded Voltage) (Degraded Voltage LOCA and non-LOCA) (Note 14) 20 (1 par 4kV bus) 4kV Emergency Bus 8.6610.55 sec. 2 (Note 13)
(Note 10) Undervoltage Timer (Degraded Voltage LOCA) 21- (1 per 4kV bus) 4kV Emergency Bus 43 S i 2.8 sec. 2 (Note 13)
(Note 10) Undervoltage Timer (Degraded Voltage non-LOCA)
(2 per 4kV bus) 4kV Emergency Bus 8514.81 4 Insbates 4kV Emergency Bus 22 Undervoltage Relay secondary volts Undervoltage Loss of Voltage (Note 10)
(Loss of Voltage) Timer. (Note 15) 23 (1 per 4kV bus) 4kV Emwigwiicy Bus 2.5010.11 sec. 2 (Note 13)
(Note 10) Undervoltage Timer (Loss of Voltage) 285 to 335 psig 4 permits closure of recirculation 24 2 Reactor Low Pressure (Notes 6,11) pump Gschya valve.
Amendment No. 2, ??, is, Si, 227, 69
JAFNPP 4 TABLE' 3 2 CORE AND CONTAINEAENT COOLING SYSTERR INITIATKW AND -
CONTROL INSTRURIENTATION OPERABILITY REQUIRERENTS NOTES FOR TABLE 3.2-2
- 1. With one or more channels inoperable for HPCI and/cr RCIC:
A. Wi*hin one hour from discovery of loss of system initiation capability, declare the affected system inoperable, and B. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place channel in trip.
C. If required actions and associated completion times of actions A or B are not met, immediately declare the affected system inoperable.
- 2. With one or more channels inoperable for Core Spray and/or RHR:
A. Within one hour from discovery of loss of hitiation capability for feature (s) in both divisions, declare the supported features inoperable, and B. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place channel in trip.
C. If required actions and associated completion times of actions A or B are not met, immediately declare associated supported -
feature (s) inoperable.
- 3. With one or more channels inoperable for ADS, A. Within one hour from discovery of loss of ADS initiation capability in both trip systems, declare ADS inoperable, and E>. Within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of an inoperaute channel concurrent with HPCI or RClO inoperable, place channe; in trip, and C. Withia 8 days, place channel in trip.
D. If required actions and associated completion times of actions A, B, or C are not met, immediately declare ADS inoperable.
Amendment No. 3,48,227,233, 70
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JAFNPP TABLE 3 2-2 ,
B a
CORE AND CONTAINMENT COOLING SYSTEM INITIATION AND CON 3OL INSTRUMENTATION OPERABILITY REQUIREMENTS f
- 4. With one or more channels inoperable for HPCI and/or RCIC:
A. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore channel to operable status. k c
B. If required action and associated completion time o' action A is not met, immediately declare affected system inoperable. ]
- 5. With one or more channels inoperable for containment spray. h A. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place channel in trip.
B. if required action and associated completion time of action A is not met, immediately declare associated supported feature (s) incperable.
- 6. With one or more channels inoperable for injection pennissive and/or recirculation discharge valve permissive:
A. Within or'e hour from discovery of loss of initiation capability for feature (s) in both divisions, declare the supported features inoperable, and B. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore channel to operable status.
C. If required actions and associated completion times of actions A or B are not met, immediately declare associated supported feature (s) inoperable.
_5 t
Amendment No. 48, 67,106,120,-160, 227, 4 71
o JAFNPP '1 TABLE 3.2-2 .
CORE AND CXNIADOGNT COOLDG SYSTBi INITIATICE AE OCh6 INSTIDGINDLTICN OPERABILITY REQUIRBENTS
- 7. A. With one start timer inoperable, restore the timer to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. With two or more start timers inoperable, within one hour declare the associated ECCS subsystem (s) inoperable.
C. If the required actions and associated completion times of A and B cannot be met declare the associated ECCS subsystemis) inoperable.
- 8. With one or more channels inoperable for ADS:
A. Within one hour from discovery of loss of ADS initiation w bility a in bcih trip systems, declare ADS inoperable, and E. Within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of an inopuable channel concurrent with HPCI or RCIC inoperable, restore channel to operable -
status, and C. Within 8 days, restore channel to operable status.
D. If required actions and associated completion times of actions A, B, or C are not met, immediately declare ADS inoperable.
- 9. With one or more channels inoperable for HPCI and/or RCIC:
A. Within one hour from discovery of loss of system inita capability while suction for the affected system is aligned to the CST, declare the affected system inoperable, and B. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place channel in trip or align suction for the affected system to the suppression pool.
C. If required actions and associated completion times of actions A or B are not met, immediate!y declare the affected system inoperable.
Amendment No. 227, 71a
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'JAFNPP.
TABLE 3 2-2 ' .
CORE AND CONTANGENT COOLING SYSTEM BNTIATION AND CONTROL INSTpswsfTATION OPERABK.ITY REQUNIFRAFNTS
- 10. With one or more channels inoperable for 4kV Emergency Bus Undervoltage Trip Funcbons-l A. Within one hour, place channel in trip.
B. If required action and associated completion time of action A is not met, immediately declare the affected Emargency Diesel Generator System inoperable.
- 11. When a channel is placed in an inoperable status solely for performacce of required survedlances, entry into associated Limiting Conditions For C; eration and required actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Trip Funcbon or the redundant Trip Function man ins ECCS initiation capabdsty.
- 12. When a channel is placed in an inoperable status solely for' performance of required surveillances, entry into associated Limiting Conditions For Operation and required actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- 13. The 4kV Emergency Bus Undervoltage Timers (degraded voltage LOCA, degraded voltage non-LOCA, and loss-of-voltage) initiate the following: starts the Emergency Diesel-Generators; trips the normal / reserve tie breakers and trips all 4kV moto 'xeakers (in conjunction with 75 percent Emergency Diesel-Generator voltages); initiates h: psator breaker close permissive (in conjunction with 90 j
percent Emergency Diesel-Generator voltages) and; initiates sequential starting of vital loads in conjunction with low 4ow-low reactor water level or high drywell pressure.,
- 14. A secondary voltage of 110.6 volts corresponds to approximately 93% of 4160 volts on the bus.
- 15. A secondary voltage of 85 volts corresponds to approximately 71.5% of 4160 volts on the bus.
ll
- 16. Only one trip system.
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Amendment No.
71b
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JAFNPP ,
TABLE 4.2-2 CORE AND CONTAINMENT COOLING svSTEM INSTRUMENTATION TEST AND CALIBRATION REQUIREMENTS f
Instrument Functional Test Cahbration Frequency Instrument Check (Note 4)
Instrument Channel Q (Note 5) SA / R (Note 15) D
- 1) Reactor Water Level O Q NA
- 20) Drywell Pressure non-ATTS)
SA / R (Note 15) D 2b) Drywell Pressure (ATTS) Q (Note 5)
O Q NA
! 3a) Reactor Pressure (non-ATTS) D Reactor Pressure (ATTS) Q (Note 5) SA / R (Note 15) 3b)
NA R NA
- 4) Auto Sequencing Timers O O NA
- 5) ADS - LPCI or CS Pump Disch.
Q Q NA
- 6) HPCI & RCIC Suction Source Levels R R NA
- 7) 4kV Emergency Bus Under-Voltage (Loss-of-Voltage, Degraded Voltage LOCA and non-LOCA) Relays and Timers.
NOTE: See notes following Table 4.2-5; Amendment No. 2.99,199.181,201,217,227, 80
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