Proposed TS Table 3.2-B Re Instrumentation That Initiates or Controls Core & Containment Cooling SysML20114B145 |
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Pilgrim |
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08/17/1992 |
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BOSTON EDISON CO. |
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Shared Package |
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ML20114B143 |
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References |
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NUDOCS 9208250099 |
Download: ML20114B145 (10) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20072T0521994-09-0606 September 1994 Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe ML20072S0501994-09-0606 September 1994 Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems ML20072S0081994-09-0606 September 1994 Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief ML20072S0861994-09-0606 September 1994 Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20069M3311994-06-0909 June 1994 Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe ML20067B7111994-02-0909 February 1994 Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993 Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059A9361993-10-19019 October 1993 Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993 Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint ML20046D0441993-08-0909 August 1993 Proposed Tech Specs,Proposing 24 Month Fuel Cycle ML20044G1331993-05-20020 May 1993 Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993 Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively 1999-06-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] |
Text
, - . . .
- v. ,
AITACHMENT B TO SEco LETTER 92- 101
- Revised-Technical Specification Pages L
l:
I' I-
.e n
i I
9208250099 920817 PDR ADOCK 05000293.-
P- .PDR-
PNPS- [
- TABLE 3.2-B (Cont'd) , .
i INSTRUMENTATION THAT INITIATES OR CONTROLS THE COEE AND CONTAINMENT COOLING SYSTEMS-
, Minimum.# of. ~
! Operable Instrument Channels Per Trio System-(l) Trip function Trio Level Setting - Remarks j t
2 High Drywell $2.5 p $~ 1. Initiates Core Spray; LPCI;-
Pressure HPCI. ,
- 2. In conjunction with low-Low' '
l
. Reactor Water Level, 120 sec;nd time delay and LPCI- '
t or tcre Spray ptimp running, ,
initiates Auto' Blowdown I (ADS).
- 3. Initiate < starting of Diesel i Generators !
- 4. Ir. conjunction with Reactor t low Preisure initiates !
ciosure of HPCI vicuum ;
breaker containment ;
isolation valves. '
i 1 Reactor Low Pressure 400 psig i 25 Permissive for Opening Core Soray and LPLI Admission valves. '
1 Reactor Low Pressure 5110 psig In conjunction with PCIS signal i permits closure of RHR (LPCI) injection valves. .
I Reactor Low Pressur 400 psig 25 In conjunction with Low-Low Reactor Water Level initiates Core Spray and LPCI.
2 Reactor Low Pressore 900 psig 25 Pre ents actuation of LPCI break detection circuit.
2 Reactor Low Pressure 100>P>50 psig Isolates PPCI and in l conjunction with High Drywell Pressure initiates closure of HPCI vacuum breaker containment isolation valves.
Amendment No. 42;-113- 48-
PNPS 3
.-TAGLE 3.2-B-(ccat'd) .
o-
-INSTRUMENTATION THAT INITIATES OR CONTROLS'THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of ~
. Operable Instrument
' Channels Pur Trio-System 11) Trio Function . Trip Level Settina Remarks
, 2 ,
Condensate Storage: Tank' .>18" above tank zero Provides' interlock to HPCI Low'Levei- pump suction valves 2: Suppression Chamber ~ $1'11" below torus High Level zero ,
1 RCIC Turbine Steam Line 5300% of rates steam t High Flow fl ow (2) i
- RCIC: Turbine' Compartment 5170 F 2 (2)
Wall- 3
- 2. ' Torus Cavity Exhaust '
5150 F (2) '
Duct '
0 '
2 RCIC Valve Station Area $200 F (2)
Wall' 4 (5) RCIC Steam Line Lo-Press 100>P>50 psig- (2) t 1 HPCI Turbine Steam Line $300!; of rated flow- (3)
High Flow t
2 HPCI Turbine Compartment 5170 F (3) l Exhaust Ducts 2 Torus Cavity Exhaust '190 - 200 F (3) -
Duct:
0 2 HPCI/RHR: Valve Station - $170 F (3)
Area' Exhaust Duct l
Amendment-No. 52 e v-
- NOTES
- FOR TABLE 3.2.8
- 1. Whenever any CSCS-subsystem'is required by Section'3.5 to be operable, there shall be two (Note.5) operable trip systems, i f the first column cannot be met for one of the trip systems, that: system shall be repaired or the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after this trip system is .made or found ~to- be inoperable.
- 2. Close isolatiori valves in RCIC subsystem.
- 3. Close isolation valves in HPCI subsystem.
- 4. Instrument set point corresponds to 77.26 inches of active fuel.
- 5. RCIC has only one trip system for those sensors.
.c:
s a
1; Amendment No. 108 53
= cr , m -
y q
'PNPS.
. ' TABLE ~4
.. 2 B-
- MINIMUM TEST AND CALIBRATION FREnUENCY FOR CSCS Instrument Channel Instrument' Functional' Test- . Calibration Frecuency
' . Instrument Check ,
- 1) Reactor Water. Level (1) (7) . ..(7) _Once/ day
- 2) Drywell Pressure '1)-(7) (7) Once/ day-3)'. Reactor Pressure (1) (7)' (7) .Once/ day
- 4) ' Auto Sequencing Timers NA Once/ operating cy-le None-
- 5) ADS-LPCI or CS Pump Disch.
' Pressure Interlock (1) Once/3 months None *
- 6) Start-up Transf. (4160V) ,
a' . . Loss of Voltage Relays Monthly Once/ operating cycle None ;
t
- b. Degraded Voltage Relays Monthly Once/ operating cycle None'
- 7) Trip System Bus Power-Monitors Once/ Operating cycle N/A Once/ day t
- 8) Recirculation System d/p -(l) Once/3 months Once/ day
- 9) Lore Spray'Sparger d/p NA .Once/ operating cycle Once/ day
- 10) Steam Line High Flow (HPCI&RCIC) (1) Once/3 months None 11') Steam Line High. Temp. (HPCI&RCIC) (1) Once/3 months None
- 12) Safeguards Area High Temp. (1)' ance/3 months. None L'
- 13) RCIC Steam Line-Low Pressure (1) Once/3 months None ;
- 14) HPCI Suction Tank Levels (1) Once/3 monas None 15 Emergency 4160V Buses A5 & A6 Monthly Once/ operating cycle None f Loss of Voltage Relays .g Amendment No.'421-61; 61 g 9 m -
n <u.u- ..w-r
ATTACliMENT C TO BEco LETTER 92- 101 Annotated Current Technical Specification Page.s 4
I 4
M itO)
.v~h) y ?: v (v- PNPS TABLE 3.2-B (Cont'd) EM INSTRUMENTATION THAT INITIATES _QR_ CON 1RQL1 TliE CO2 Minimum # of RellarAl Operable Instrument Trip _Eunition Irip_ Lev (LStLLLng Channeis_Pgr Trip _Syslgm_Lil 1. Initiatas Core Spray; LPCI; High Drywell Pressure 52.5 psig s HPCI.
2 2. In conjunction with Low-Low Reactor Hater Level, 120 second time delay and LPCI or Core Spray pump running, initlates Auto Blowdown (ADS)
- 3. Initiates starting of Diesci Generators. !
- 4. In conjunction with Reactor Low Pressure initiates closure of HPCI vacuum breater containment isolation va;ves.
Permissive for Opening Core 400 psig 25 Reactor Low Pressure Spray and LPCI Admission valves.
I In conjunction with PCIS signal 1110 psig permits closure of RHR (LPCI)
Reactor Low Pressure 1 injection valves.
In conjunction with I.ow -Low 400 psig 25 Reactor Low Pressure Reactor Hater Level initiates 1 Core Spray and LPCI.
25 Prevents actuation of LPCI break 909 psig detection circuit.
2 Reactor Low Pressure f Drywell 100>P>50 psig ja r conjunction with H ,nPressu.e initiates cl Reactor Low Pressure f 2 / HPCI vacuum breaker containment isolation valves.
[s 48
' ^Z'.sa id es A FC1 itn d h
-ReviTtonmfr" AmendmentNo.//, ,j iim%
' /* +
g- . . .
. -. ~. -
., f .
. e
'TYPS l 3' TABLE 3 2.B . (Cont'd) .
INSTRUlmATION THAT INITIATES OR CONTROLS THr. CORE idD CONTAINMENT COOLITC SYSTD4S . . , i.
')3. M F.inicum # or i-
.fD Operable Instrument'
' Renarks.
Chant.els'Per Trip System (1) Trip runction Trip Level Setting t.
g 2 ' Condensate Storage Tank 218" above tank tero Provides interlock to HPCI pump.
.O Low Level
'2 Suppression Chacber & l'll" below torus zero -
High, Level
~
[-l 1 RCIC Turbine Shea:n Line 53005 or rated stes:s rlow '*
+ High Flow -
(2) -
'i 2 ECIC Tu-Sine Compartment Wall 6170*F . (2). 'f
.e
'2 Torus Cavity Exhaust Dact $150*F (2) l 8'
2 RCIC Valve Statien Area f200*F (2) p ym .
Is (3) BCIC Steam Line Lo-Press 100> P>50 psig (2) -
1 H NI W rbine Steem Line d 3C7f,or rated flew (32 High Flow 6
2 HPCI h rbit Compartment 5170*F (3)
Exhaust Ducts 2 . Torus Cavity Exhusat &>ct 190 - 2co F (3) t 2 : HNI/PER valve Station 6170*F (3)
' Area Exhaust Duct i - r-% -.r...,,
J-(
. @lfS FOR TABLE __3.2 3
. - 1.='Whenever any.CSCS subsystem is: required by Secti.on 3.5 to be operable.
-o ' ithere shall-be two (Note.5) operable trip systems. If the first column canrt be met for_ one'of the trip systems, that system shall- be repaired
-or tiie reactor shall be placed in the Cold Shutdown Condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sf after this trip system is made or found to be inoperable.
- 2. Close isolation valves in RCIC subsystem.
- 3. Close isolation valves in HPCI subsystem.
- 4. Instrument set point corresponds to 77,26 inches of active fuel.
(
- 5. RCICffdfifqd)u 3 ha n only one trip system tar these sensors.
L 4'
l.
2; f .~e W%
4-q.-
wi '
. MevTs tN8 53-A + u d me e f30 }ffl
,,:w 1,
[ ., ..
a J'
4 '
.FNPS - x TABLE 4.2.B- .
-; o HINIMUM TEST AND CALIBRATION FRE0t'ENCY FOR CSCS :
Instrument Channel- ~ Instrument Functional Test Calibration Frequency : Instrument Che'ck
- 1) . Reactor Hater. Level (1) (7) (7) Ontc/ day-
- 2) -Orywell-Pre.ssure (1) (7) -(7). Once/ day
- 3) - Reactor Pressure (1)-(7) (7) Once/ day
- 4) Auto. Sequencing Timers NA Once/ operating cycie None
' ADS - LPCI or CS Pump Disch.
5)
Pressure Interlock (1) Once/3 months None
- 6) .. Start-up Transf.'(4160V)
- a. Loss of Voltage Relays Monthly Once/ operating cycle None
- b. Degraded-Voltage Relays. Monthly once/ operating cycle None
- 7) Trip System Bus Power Monitors Once/operattag cycle N/A. Once/ day'
- 8) Recirculation System d/p (1) Once/3 months Once/ day..
- 9) Core Spray Sparger d/p. NA Once/ operating cycle Once/ day-
- 10) Steam Line High Flow OIPCI_& RCIC)' (1) Once/3 months None
- 11) Steam Line High Temp. (HPCI & RCIC) (1) Once/3 months None 12)' Safeguards Area High Temp. (1) Once/3 months None
- 13) @P'Cy appjRCIC Steam Line Low Pressure (1) Once/3 months None
- 14) HPCI Suction Tank' Levels (1) Once/3 months None
- 15) Emergency 4160V Buses A5 & A6 Monthly Once/ Operating Cycle None i
Loss of Voltage Relays i
Revision-103- 61 l}mmbnenf /Uof h, I, /f .
4