|
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers ML20065K1931994-04-12012 April 1994 Proposed Tech Specs,Reflecting Removal of Definitions 1.0.Z.B.1 Through 5,change to LCO 3.21.B.1.a (Line 5) Re Ref to 10CFR20.106 & Change to Paragraphs 1,4,5 & 6 (Lines 6,3,8 & 2 Respectively) Re Ref to 10CFR20.106 ML20058N2321993-12-10010 December 1993 Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept ML20058N2881993-12-10010 December 1993 Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves ML20058M2591993-09-28028 September 1993 Proposed Tech Specs Modifying Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operation ML20056G5971993-08-31031 August 1993 Proposed TS Re Primary Containment Isolation Valve Tables ML20056G5821993-08-31031 August 1993 Proposed TS Re Primary & Secondary Containment Integrity ML20056G2341993-08-25025 August 1993 Proposed Tech Specs Bases Section to Reflect Operational & Design Changes Made to CNS Svc Water Sys During 1993 Refueling Outage ML20056F3331993-08-23023 August 1993 Proposed Tech Specs 6.0, Administrative Controls, Reflecting Creation of Mgt Position of Vice President - Nuclear ML20045D8991993-06-23023 June 1993 Proposed TS SR 4.9.A.2 Re Determination of Particulate Concentration Level of Diesel Fuel Oil Storage Tanks ML20045C0031993-06-14014 June 1993 Proposed Tech Specs Associated W/Dc Performance Criteria ML20045C8301993-06-14014 June 1993 Proposed Tech Specs Incorporating New Requirements of 10CFR20 ML20128L5561993-02-12012 February 1993 Proposed TS Table 4.2.D, Min Test & Calibr Frequencies for Radiation Monitoring Sys & TS Pages 81 & 84 Re Notes for Tables 4.2.A Through 4.2.F ML20128E6201993-02-0101 February 1993 Proposed Tech Specs Reflecting Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8331993-01-0505 January 1993 Proposed TS Pages 53,55,70 & 71,removing Bus 1A & 1B Low Voltage Auxiliary Relays ML20115F8531992-10-15015 October 1992 Proposed Tech Specs Page 48,reflecting Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3481992-10-0808 October 1992 Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee ML20104B2091992-09-0909 September 1992 Proposed TS 3.1.1 Re Reactor Protection Sys Instrumentation Requirements & TS Table 3.2.D Re Radiation Monitoring Sys That Initiate &/Or Isolate Sys ML20104A8691992-09-0202 September 1992 Proposed TS 3.9 & 4.9 Re Auxiliary Electrical Sys ML20099D4151992-07-28028 July 1992 Proposed TS 3.6 Re LCO for Primary Sys Boundary & 4.6 Re Surveillance Requirements for Primary Sys Boundary ML20113G8241992-05-0404 May 1992 Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08 ML20096D6111992-05-0404 May 1992 Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A8061992-02-25025 February 1992 Proposed Tech Specs Re Dc Power Sys 1999-06-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] |
Text
. .
GEMAC 916.75" - 400*
IN.
--- 848.75"- 332' 850' INSTRU 6 T TAP
- REACTCR 806- WATER LEVEL W10E RANGE
.d 750"-
722.25' VESSEL FLANGE 700"- ROSEMOUNT
/~ STEAM 692.56.,<- 340" NOZZLE f
RANGE 650"- 640O'{Ayfg LINE LI.92 ROSEMOUNT a YA R W AY GEMAC 6OO - (9 3) 577.56"/+2 25
. ) BARTON YARWAY A
+60" 1 -- - - - - - - . ---
- HPCI 8 :- + Eo"- - - + 60* 576.7f L + 60"
-559 25 (7) ' ylg 158 518) 42.5'(7)~ H1 ALARM 550',-_ 544.25(4)
REACTC71 27.5"(4) < W MM 529 2} (3) G,, 12 5 "(3) 544 25" (4)
LPSTRUMENT-3 0"--- 7g86~--.F-- --
O *-- - -- 0"- - 516.75" O*
500- ZERO LIS.101 L g.94
( 9 4}512.56" 160" 479.75(2) 37"( 2 ) (9 5)
(-FEEDWATN3 4 50"-
4 % O' EN} INITIATE RCIC, HPCI, TRIP REClRC. PUMPS 400"-
-371.25 (1) 145 5"(1)
TAF e 352.56.,-- O, 352.56,,
450"J--INI TIATE RH R , C. S., - - - .. 150" 366.75" 350". STA RT DIESEL 8 Jk LI,33 Mm8m d W B%u L%l@(931'.6")
313 5" 39' cj (9 5) IN STRU MENT 2/3 M CORE HECHT 30g. p RACK
( 25 5 8 25 6 )
PERMISSIW '.g I
250"- k l
l;i WATER LEVEL NOMENCLATURE f 20256" .g y 208.56,,
l 200"- LEVEL HEIGHT A80/E INSTRUMENT HT ABOVE f9 -$NE NOZZLE 178f 161.5" NO. WSSEL ZERO READING TAF l g,.C , __ .
( in.) (in) 150 - NOZZLE g- (8) 575.25 !4.5 222.69 (7) 559.25 42.5 206.69 j (4) !44.25 27.5 191.69 100"- (3) 529.25 12.5 176 69 l
(2) 479.75 37 127.19 (1) 371.25 . f 4 5.5 18.69 50"-
O' .
E LE V ATION 917 '.~D
- v ESSEL BOTTOM FIGURE 2.1.1 8802110202 000202 REACTOR WATER LEVEL INDICATION CORRELATION l PDR ADOCK 05000298 10 P PDR l
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COOPER EUCLEAR STATION .!
TABLE 3.2.B (PAGE 1) ' *'l CIRCUITRY REQUIREMENTS CORE SPRAY SYSTEM Minimum Number of Action Required When.
Instrunent Operable Components Component Operdbility Instrument I.D. No. ' Setting Limit Per Trip System Is Not Assured!(1)
Reactor Low Water NBI-LIS-72 A, B, C, >-145.5 of Indicated 2 A-Level &D Level Reactor Low Pressure NBI-PS-52 A1, A2, <450 psig 2 A C1, & C2 iNBI-PIS-52 B&D *
, 4 I
Drywell liigh Pressure PC-PS-101, A, B, <2 psig - 2 A' C&D .
Core Spray Pump CS-PS-44, A & B 2 A Disch. Pressure CS-PS-37, A & B 100 < P < 165 psig t
o _ _
Core Spray _ Pump. CS-TDR-K16 ,
9<T<ll seconds 1 _ B . , _ _
[UI Time Delay A&B
~ '
Low Voltage Relay 27X1 - IF & 1G Loss of Voltage 1 ' B' lEmerg. Bus 27X2 - IF & 1G Aux. Bus Low 27X3 - lA & IB Loss of Voltage 1 B Voltage Relay Pump Discharge Line CM-PS-73, A & B >10 psig (3) D Low Pressure
')
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COOPER NUCLEAR STATION TABLE 3.2.B (PAGE 2)
RESIDUAL HEAT REMOVAL SYSTEM (LPCI MODE) CIRCUITRY REQUIREMENTS Minimum Number of Action Required When Instrument Operable Components Component Operability-Instrument I.D. No. Setting Limit Per Trip System (1) Is Not' Assured!. I' Drywell High Pressure PC-PS-101 A,B,C, & D $2 psig 2 A Reactor Low Water NBI-LIS-72, A,B,C. >-145.5" Indicated 2 A Level & D #1 Level Reactor Vessel Shroud ~NBI-LITS-73, A & B >-39 Indicated >
1 B Level Below Low ~)1 Level 4
! Level Trip Reactor Low Pressure RR-PS-128, A & B $75 psig 1 B Reactor Low Pressure NBI-PS-52A1,A2,C1&C2 $450 psig 1 A (Injection Valve NBI-PIS-52B & D >
f, _____ __ Permissive) _ _ _ _ _ , ,_ ._ _. _
t$
s Drywell Pressure PC-PS-119, A,B,C, $2 psig 2 A Containment Spray &D l RHR Pump Discharge RHR-PS-120, A,B,C,6D 100 $ P $ 165 psig 2 A RHR-PS-105, A,B,C,&D 100 < P $ 165 psig 2 A Reactor Low Pressure NBI-PS-52A & C 185 < P < 235 psig 1 A (Recire. Discharge NBI-PIS-52B'& D Permissive)
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COOPER NUCLEAR STATION-
.2 TABLE 3.2.B (PAGE 3)- -
RESIDUAL HEAT REMOVAL SYSTEM (LPCI. MODE) CIRCUITRY REQUIREMENTS /
- Minimum Number of . Action Required ,nRue,n ,
Instrument Operable Components Component Operability _
l Instrument I.D. No. Setting Limit Per Trip System (1) Is Not Assured l~ l' j RHR Pump Low Flow RHR-dPIS-125 A & B >2500 gpm 1 A. 4 Time Delays RHR-TDR-K45, lA&lB 4.25<Tf5.75 min. 1 A' RIIR Pump Start RHR-TDR-K75A & K70B 4.5fTf5.5 Sec.. 1 A Time Delay RilR-TDR-K75B & K70A 1 5 sec. 1 A RiiR lleat Exchanger RIIR-TDR-K93, A & B 1.83T12.2 min. 1 B Bypass T.D. -
f ,
I RilR Crosstie Valve RHR-LMS-8 Valve Not closed (3) E Position -
Bus IA Low Volt. 27 X 3/lA Loss of Voltage 1 B Aux. Relay Bus IB Low Volt. 27 X 3/1B Loss of Voltage 1 B g ,. Aux. Relay _.. , __ _ _ _ _ _ . _ _ .
7Y Bus IF Low Volt. 27 X 1/lF Loss of Voltage 1 B-Aux. Relays 27 X 2/lF Loss of Voltage 1 B' Bus 1G Low Volt. 27 X 1/lG Loss of Voltage 1 B jAux. Relays 27 X 2/lC Loss of Voltage Pump Discharge Line CM-PS-266 >5 psig (3) D CM-PS-270 >15.psig (3) D Emergency Buses 27/1F-2, 27/lFA-2 3600 15% 2 .B Undervoltage Relays 27/lG-2, 27/lGB-2 8 second 12 sec. 2 B (degraded voltage) time delay 1 B' Emergency Buses Loss 27/lF-1, 27/lFA-1, 2900V-15%
of Voltage Relays 27/lG-1, 27/lGB-1, 5 second il sec.
27/ET-1, 27/ET-2 delay 1 B Emergency Buses Under- 27X7/lF, 27X7/lG, Voltage Relays Timers 10 second 12 sec. 1 -B. -
A 4
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COOPER NUCLEAR STATION ,
TABLE 4.2.B'(Page 1) !
CORE SPRAY SYSTEM TEST & CALIBRATION FREQUEECIES l
+
Instrument Item Item I.D. No. Functional Test Freq. Calibration Freq. Check-Instrument
- 1. Reactor Low Water Level NBI-LIS-72, A,B,C, & D Once/ Month (1) Once/3 Months Once/ Day
- 2. Reactor Low Pressure NBI-PS-52, A1,A2,C1, & C2 Once/ Month (1) Once/3 Months None NBI-PIS-52, B & D {.
- 3. Drywell High Pressure PC-PS-101, A,B,C, & D Once/ Month (1) Once/3 Months None
- 4. Core Spray Pump Disch. ' ' '
CS-PS-44 .A & B Once/ Month (1) Once/3 Months None Press. CS-PS-37, A & B once/ Month (1) Once/3 Months '
None I
- 5. Core Spray Pump Time Delay- CS-TDR - K16, A & B Once/ Month (1) Once/Oper. N5ne Cycle (4)
- 6. Emergency Bus Low Volt Relay 27XI - IF & IG Once/Oper. Cycle Once/5 Years None 27X2 - IF & 1G Once/Oper. CWele Once/5 Years None
- 7. Aux. Bus Low Voltage Relay 27X3 - 1A & IB Once/Oper. Cycle once/5 Years None 3, 8. Pump Disch. Line Low Press. .CM-PS-73, A&b Once/3 Months = Once/3 Months .None T c~
8 Logic (4) (6)
- 1. Logic Power Monitor Once/6 Months- N.A. N.A.
- 2. } Core Spray Initiation once/6 Months N.A. NjA.
- 3. Pump & Valve (Signal Override) Once/6 Months N.A. N/A.
Control n
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COOPER NUCLEAR STATION ,
TABLE 4.2.B-(Page 2)
RHR SYSTEM TEST & CALIBRATION FREQUENCIES Functional Instrument Item Item I.D. No. Test Freq. Calibration Freq. Check Instrumantation
- 1. Drywell High Pressure PC-PS-101, A, B, C & D Once/ Month.(1) Once/3 Months None
- 2. Reactor Vessel Shroud Level NBI-LITS-73, A & B #1 Once/ Month (1) Once/3 Months once/ Day
- 3. Reactor Low Pressure ~
~
RR-PS-128 A & B Once/ Month (1) Once/3 Months None 4.. Reactor Low Pressure NBI-PS-52 A1.A2,C1, & C2 Once/ Month (1) Once/3 Months None I
NBI-PIS-52 B & D
- 5. Drywell Press.-Containment PC-PS-119, A,B,C & D Once/ Month (1) Once/3 Months None Spray
- 6. RHR Pump Discharge Press. RHR-PS-120, A,B,C & D Once/ Month (1) Once/3 Months None
- 7. RHR Pump Discharge Press. RHR-PS-105, A,B,C & D Once/ Month (1) Once/3 Months None
- 8. RHR Pump Low Flow Switch RHR-dPIS-125 A & B Once/ Month (1) Once 3 Months None i< , _ _9._ RHR Pump Start Time Delay ___,_ _.RHR-TDR-K70, A & B. Once/ Month (1) Once/Oper. Cycle None _ _._ _
3Z 10. RHR Injection Valve Close T.D. RHR-TDR-K45 1A & IB Once/ Month (1) Once/Oper. Cycle None 8
- 11. RHR Pump Start Time Delay RHR-TDR-K75, A & B Once/ Month (1) Once/Oper. Cycle None
- 12. RHR Heat Exchanger Bypass T.D. RHR-TDR-K93, A & B Once/ Month (1) Once/Oper. Cycle None
- 13. RHR Cross Tie Valve Position RHR-LMS-2 Once/ Month (1) N.A.
14.} Low Voltage Relays 27 X 3/lA (7) None'
- 15. Low Voltage Relays 27 X 3/IB (7) None.
- 16. Low Voltage Relays E7 x 2/lF, 27 X 2/lG (7) None
- 17. Low Voltage Relays 27 X 1/lF, 27 X 1/lG (7) None
- 18. Pump Disch. Line Press. Low CM-PS-266, CM-PS-270 Once/3 Months once/3 Months None
- 19. Emergency buses Undervoltage 27/1F-2, 27/lFA-2, 27/1G-2, Once/ Month once/18 Months Once/12 hrs ,
Relays (Degraded Voltage) 27/lGB-2
- 20. Emergency Buses Loss of 27/lF-1, 27/lFA-1, 27/lG-1, once/ Month Once/18 Months Once/12 hrs Voltage Relays 27/lGB-1, 27/ET-1, 27/ET-2
- 21. Emergency Buses Undervoltage 27X7/lF, 27X7/lG Once/ Month Once/18 Months None Relays Timers
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u, COOPER NUCLEAR STATION TABLE 4.2.B (Page 4)
IIPCI TEST & CALIBRATION FREQUENCIES Functional Instrument Item Item I.D. No. Test Freq. Calibration Freq. Check l
- 1. Reactor Low Water Level NDI-LIS-72, A,B,C, & D, #3 Once/ Month (1) Once/3' Months .Once/ Day.
- 2. Reactor High Water Level NBI-LIS-101, (B & D #2) Once/ Month (1) Once/3 Months once/ Day
- 3. High Dryuell Pressure PC-PS-101 A, B, C, & D (7) (7) None
- 4. IIPCI Turbine liigh Exhaust IIPCI-PS-97 A & B Once/ Month (1) Once/3 Months None '
Press.
- 5. IIPCI Pump Low Suction Press. HPCI-PS-84-1 Once/ Month (1) Once/3 Months None
- 6. IIPCI Pump Low Discharge Flow HPCI-FS-78 Once/ Month (1) Once/3 Months None
- 7. IIPCI Low Steam Supply Press. IIPCI-PS-68, A,B,C, & D Once/ Month (1) Once/3 Months None 8.I IIPCI Steam Line liigh AP llPCI-dPIS-76 Once/ Month (1) Once/3 Months None llPCI-dPIS-77 Once/ Month (1) Once/3 Months None
- 9. HPCI Steam Line Space Iligh HPCI-TS-101, A,B,C, & D Once/ Month (1) Once/Oper. Cycle None Temp. 102, 103, 104, t !!PCI-TS-125, 126, 127, 128 RHR-TS-150,151,152,153,154,
. __._..._..._ 155,156,157,158,159,160,161 21 _ . _ _ _ 10. _ . _ _ _ Emergency Cond. Stg. Tk. Low HPCI-LS-74 A & B Once/ Month (1) Once/3 Months None
'Y Level IIPCI-LS-75 A & B Once/ Month (1) Once/3 Months None
- 11. Suppression Chamber liigh IIPCI-LS-91 A & B Once/ Month (1) Once/3 Months None Water Level
- 12. j IIPCI Gland Seai Cond. liotwell llPCI-LS-356 B Once/ Month (1) Once/3 Months None Level IIPCI-LS-356 A Once/ Month (1) Once/3 Months None
- 13. IIPCI Control 011 Pressure Low IIPCI-PS-2787-Il Once/ Month (1) Once/3 Months None itPCI-PS-2787-L Once/ Month (1) Once/3 Months None
- 14. Turbine Conlition Supr. Alarm IIPCI-TDR-K14 Once/ Month (1) Once/Oper. Cycle None Actuation Timer
- 15. Pump Disch. Line Low Press. CM-PS-268 Once/3 Months Once/3 Months None
- 16. I!PCI Turbine Stop Valve Mon. IIPCI-LMS-4 Once/ Month N.A. None
- 17. Sup. Chamber ilPCI Suction Viv. HPCI-LMS-2 Once/ Month N.A. None
- 18. HPCI Steam Line liigh AP HPCI-TDR-K33, once/ Month Once/Oper. Cycle None Actuation Timer llPCI-TDR-K43 Once/ Month once/Oper. Cycle None Logic (4)(6) x 1. Logic Bus Power Monitor Once/6 Months N.A.
U 2. IIPCI Initiation Once/6 Months N.A.
U 3. IIPCI Turbine Trip Once/6 Months N.A.
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