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| s Attachment 1-'to i; | | s |
| NLS9100409 Page 4 of 4 l.
| | * -'to NLS9100409 i; |
| | Page 4 of 4 l. |
| REVISED TECHNICAL SPECIFICATIONS PAGES i.-. | | REVISED TECHNICAL SPECIFICATIONS PAGES i.-. |
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| ~ | | ~ |
| ?11C150334 911007 PDR.. ADOCK 05000298 P PDR 1
| | ?11C150334 911007 PDR.. ADOCK 05000298 P |
| | PDR 1 |
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| 4 COOPER NUCLEAR STATION TABLE 3.2.11 POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS | | 4 COOPER NUCLEAR STATION TABLE 3.2.11 POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS |
| * Minicm Number of Action Required Wen Instrument Operable Instru:nent Cmponent Cperability ID Number Ranne Channels Is ibt Assured j Instrument 1.00E-2 to I (Note 1) A Elevated Release Point (ERP) PJIP - RM - 3 B Monitor (liigh Range Noble 1.00E+5 pc/cc Gas) (Xe-133 Equivalent) 1 (Note 1) A Turbine Building Ventilation RMV-PJ1- 20B 1.00E-2 to 1.00E+5 pc/cc Exhaust Monitor (High Range Noble Gas) (Xc-133 Equivalent) 1.00E-2 to 1 (Note 1) A Radwaste/ Augmented Radwaste RMV-RM-30B Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) (Xe-133 | | * Minicm Number of Action Required Wen Instrument Operable Instru:nent Cmponent Cperability Instrument ID Number Ranne Channels Is ibt Assured j |
| ~ Equivalent) 1.0-1.0Et7 R/Hr. 2 (Note 1) A Primary Containtrent Gross RMA-RM-40A Radiation Monitor R&\-RM-40B 1.0-1.0E+7 R/Hr.
| | Elevated Release Point (ERP) |
| Primary Containment Hydrogen PC-AN-H-/0 21 0% to 30% 2 (Notes 1 and 2) B Concentration Analyzer PC- AN-H 2 /011 2 0% to 30% | | PJIP - RM - 3 B 1.00E-2 to I (Note 1) |
| * Note: Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Drpell Pressure. PC-PR-1A and 13. Suppression Cha..ber/ m Torus Water Level PC-LR-1A and 13 | | A Monitor (liigh Range Noble 1.00E+5 pc/cc (Xe-133 Gas) |
| | Equivalent) |
| | Turbine Building Ventilation RMV-PJ1-20B 1.00E-2 to 1 (Note 1) |
| | A Exhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) |
| | (Xc-133 Equivalent) |
| | Radwaste/ Augmented Radwaste RMV-RM-30B 1.00E-2 to 1 (Note 1) |
| | A Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) |
| | (Xe-133 Equivalent) |
| | ~ |
| | Primary Containtrent Gross RMA-RM-40A 1.0-1.0Et7 R/Hr. |
| | 2 (Note 1) |
| | A Radiation Monitor R&\\-RM-40B 1.0-1.0E+7 R/Hr. |
| | Primary Containment Hydrogen PC-AN-H-/0 1 0% to 30% |
| | 2 (Notes 1 and 2) |
| | B 2 |
| | Concentration Analyzer PC-AN-H /011 0% to 30% |
| | 2 2 |
| | * Note: |
| | Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Suppression Cha..ber/ Torus Water Level PC-LR-1A and 13 Drpell Pressure. PC-PR-1A and 13. |
| | m |
|
| |
|
| , - , . . , . _ ..._.-...._____._.__m _ . _ - .
| | ..._.-...._____._.__m |
| .v z .w .
| | .v z.w NOTES:FOR TABLE 3.2.H-Action:- |
| NOTES:FOR TABLE 3.2.H-Action:- | | 'A.- |
| ' With i the number of ' operable components less than required by the minimum
| | ' With i the number of ' operable components less than required by the minimum |
| 'A.-
| | . component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. parameter (s):within 72 hours, and: |
| . component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. parameter (s):within 72 hours, and:
| | 1)- |
| 1)- Either - res tore the inoperable : component (s)- to operable status within 7 days'of-the' event, or | | Either - res tore the inoperable : component (s)- to operable status within 7 days'of-the' event, or 2) |
| : 2) Prepare and-submit a Special Report to the Commission within 14' days
| | Prepare and-submit a Special Report to the Commission within 14' days |
| ' following ' the _ event outlining the action taken, the cause of: the inoperabilityL'and the plans. and schedule: for restoring - the system to operable _ status. #
| | ' following ' the _ event outlining the action taken, the cause of: the inoperabilityL'and the plans. and schedule: for restoring - the system to operable _ status. |
| B. The following -- actions will. be taken -l if the minimum number of operable instrument _ channels as required are not operable: | | B. |
| : 1) Vith th'e' number -of operable channels one less than- the minimum number of
| | The following -- actions will. be taken -l if the minimum number of operable instrument _ channels as required are not operable: |
| . operable ' channels - shown, l restore . the inoperable channel to operable status'within 30 days or be in at least hot shutdown within the next' 12 hours.
| | 1) |
| _2); -With no operable channels available ,. restore at.least one channel to . | | Vith th'e' number -of operable channels one less than-the minimum number of |
| operable status within 7 dayr or be in at least hot shutdown'within the next 12 hours. | | . operable ' channels - shown, l restore. the inoperable channel to operable status'within 30 days or be in at least hot shutdown within the next' 12 hours. |
| Notes: l- | | _2); |
| : 1. These instruments are required'to be' operable at all times except w'c.en the -
| | -With no operable channels available,. restore at.least one channel to operable status within 7 dayr or be in at least hot shutdown'within the next 12 hours. |
| ' reactor is in-cold shutdown or in the REFUEL mode during a refueling outage.
| | Notes: |
| 2,- With two channels operable, the normal. condition is with one analy::er. in the standby _ mode, | | l-1. |
| | These instruments are required'to be' operable at all times except w'c.en the - |
| | ' reactor is in-cold shutdown or in the REFUEL mode during a refueling outage. |
| | 2,- |
| | With two channels operable, the normal. condition is with one analy::er. in the standby _ mode, |
| ( | | ( |
| k (n | | k (n |
| l r | | l r |
| i- | | i- |
| -67b-l
| | -67b-l |
| ! _ - _._-.,,c_ . --
| | _._-.,,c_ |
|
| |
|
| ._ . ~ -
| | ~ |
| i;. , | | i;. |
| q-c; . .-- | | q-c; u |
| u | | ' COOPER NUCLEAR STATION TABLE 4. 2.11- |
| ' COOPER NUCLEAR STATION TABLE 4. 2.11-
| | : CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION |
| , : CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION
| | * Instrument: |
| * Instrument: LFunction- ' Calibration Instrument ID' Number' Test'Freauency' Frecuenev' Elevated Release Point l(ERP) | | LFunction- |
| . Monitor (High Range Noble' :RMP-RM-3B: .Once/ Month; 'Once/ Cycle:
| | ' Calibration Instrument ID' Number' Test'Freauency' Frecuenev' Elevated Release Point l(ERP) |
| | . Monitor (High Range Noble' |
| | :RMP-RM-3B: |
| | .Once/ Month; |
| | 'Once/ Cycle: |
| Gas) | | Gas) |
| , Turbine Building Ventilation RMV-RM-20B 'Once/ Month Once/Gycle' Exhaust Monitor' (High Range Noble Cas) '
| | Turbine Building Ventilation RMV-RM-20B |
| Radwaste/ Augmented Radwaste-' RMV-RM-30B. Once/ Month Once/ Cycle- | | 'Once/ Month Once/Gycle' Exhaust Monitor' (High Range Noble Cas) |
| ; Exhaust Monitor ~ ;
| | Radwaste/ Augmented Radwaste-' |
| (Iligh Range Noble Gas) ' | | RMV-RM-30B. |
| Primary Containment Gross RMA-RM-40A' 'Once/ Month -Once/ Cycle 7 Radiation Monitors ** RMA-RM-40B; l' | | Once/ Month Once/ Cycle-Exhaust Monitor ~ |
| Primary Containment Hydrogen .'PC-AN-H2 /0 2 1 Once/ Month 'Once/ Quarter' Concentration Analyzer PC-AN-H 2 2/0 II i | | (Iligh Range Noble Gas) |
| * Note: Other Post- Accident Monitoring Instrumentation calibration requirements are in Table 4.2..F-Drywell' Pressure, , | | Primary Containment Gross RMA-RM-40A' |
| i PC-PR-1A and 13, Suppression Chamber / Torus Water ' Level PC-IR-1A and 1B.
| | 'Once/ Month |
| -i
| | -Once/ Cycle 7 |
| - 5
| | Radiation Monitors ** |
| +
| | RMA-RM-40B; l' |
| ** CHANNEL CALIBRATION shall consist of an electronic ' calibration of the channel,. not . including.the.
| | Primary Containment Hydrogen |
| | .'PC-AN-H /0 1 Once/ Month |
| | 'Once/ Quarter' 2 2 Concentration Analyzer PC-AN-H /0 II 2 2 i |
| | * Note: |
| | Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2..F-Drywell' Pressure, i |
| | PC-PR-1A and 13, Suppression Chamber / Torus Water ' Level PC-IR-1A and 1B. |
| | -i 5 |
| | + |
| | ** CHANNEL CALIBRATION shall consist of an electronic ' calibration of the channel,. not. |
| | including.the. |
| detector, for range decades above 10.R/hr and a one point calibration check of the' detector below 10 R/hr with an installed or portable gamma source. | | detector, for range decades above 10.R/hr and a one point calibration check of the' detector below 10 R/hr with an installed or portable gamma source. |
| i i | | i h |
| _ _ . . . ~ -,. . - -_ -. _ . _ _ _ _ - _ =a}}
| | i |
| | ~ |
| | =a}} |
Proposed Tech Spec Table 3.2.H Re post-accident Monitoring Instrumentation Requirements & Table 4.2.H Re Calibr Frequency for post-accident Monitoring Instrumentation| ML20085D203 |
| Person / Time |
|---|
| Site: |
Cooper  |
|---|
| Issue date: |
10/07/1991 |
|---|
| From: |
NEBRASKA PUBLIC POWER DISTRICT |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20085D200 |
List: |
|---|
| References |
|---|
| NUDOCS 9110150334 |
| Download: ML20085D203 (4) |
|
|
|---|
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
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
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
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
ML20058N2881993-12-10010 December 1993
Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves
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
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
ML20035G7171993-04-23023 April 1993
Proposed,Deleted TS Section 3/4.5.H Re Engineered Safeguards Compartments Cooling
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
ML20096D6111992-05-0404 May 1992
Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions
ML20113G8241992-05-0404 May 1992
Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08
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
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
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
ML20086H7341995-07-14014 July 1995
Rev 7 to CNS Second Ten Yr Interval IST Program
ML20086K4421995-07-14014 July 1995
Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs
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
ML20098B0231995-06-12012 June 1995
Nuclear Power Group Phase 3 Performance Improvement Plan
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
ML20098B0201995-01-31031 January 1995
Rev 3 to Cooper Nuclear Station Startup & Power Ascension Plan
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
ML20098A9961994-08-25025 August 1994
Rev 0 to Cooper Nuclear Station Performance Improvement Plans Phase 1:Startup Planning Process
1999-06-08
[Table view] |
Text
{{#Wiki_filter:-
s
Page 4 of 4 l.
REVISED TECHNICAL SPECIFICATIONS PAGES i.-.
l l
~
?11C150334 911007 PDR.. ADOCK 05000298 P
PDR 1
4 COOPER NUCLEAR STATION TABLE 3.2.11 POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS
- Minicm Number of Action Required Wen Instrument Operable Instru:nent Cmponent Cperability Instrument ID Number Ranne Channels Is ibt Assured j
Elevated Release Point (ERP)
PJIP - RM - 3 B 1.00E-2 to I (Note 1)
A Monitor (liigh Range Noble 1.00E+5 pc/cc (Xe-133 Gas)
Equivalent)
Turbine Building Ventilation RMV-PJ1-20B 1.00E-2 to 1 (Note 1)
A Exhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas)
(Xc-133 Equivalent)
Radwaste/ Augmented Radwaste RMV-RM-30B 1.00E-2 to 1 (Note 1)
A Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas)
(Xe-133 Equivalent)
~
Primary Containtrent Gross RMA-RM-40A 1.0-1.0Et7 R/Hr.
2 (Note 1)
A Radiation Monitor R&\\-RM-40B 1.0-1.0E+7 R/Hr.
Primary Containment Hydrogen PC-AN-H-/0 1 0% to 30%
2 (Notes 1 and 2)
B 2
Concentration Analyzer PC-AN-H /011 0% to 30%
2 2
Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Suppression Cha..ber/ Torus Water Level PC-LR-1A and 13 Drpell Pressure. PC-PR-1A and 13.
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.v z.w NOTES:FOR TABLE 3.2.H-Action:-
'A.-
' With i the number of ' operable components less than required by the minimum
. component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. parameter (s):within 72 hours, and:
1)-
Either - res tore the inoperable : component (s)- to operable status within 7 days'of-the' event, or 2)
Prepare and-submit a Special Report to the Commission within 14' days
' following ' the _ event outlining the action taken, the cause of: the inoperabilityL'and the plans. and schedule: for restoring - the system to operable _ status.
B.
The following -- actions will. be taken -l if the minimum number of operable instrument _ channels as required are not operable:
1)
Vith th'e' number -of operable channels one less than-the minimum number of
. operable ' channels - shown, l restore. the inoperable channel to operable status'within 30 days or be in at least hot shutdown within the next' 12 hours.
_2);
-With no operable channels available,. restore at.least one channel to operable status within 7 dayr or be in at least hot shutdown'within the next 12 hours.
Notes:
l-1.
These instruments are required'to be' operable at all times except w'c.en the -
' reactor is in-cold shutdown or in the REFUEL mode during a refueling outage.
2,-
With two channels operable, the normal. condition is with one analy::er. in the standby _ mode,
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' COOPER NUCLEAR STATION TABLE 4. 2.11-
- CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION
LFunction-
' Calibration Instrument ID' Number' Test'Freauency' Frecuenev' Elevated Release Point l(ERP)
. Monitor (High Range Noble'
- RMP-RM-3B:
.Once/ Month;
'Once/ Cycle:
Gas)
Turbine Building Ventilation RMV-RM-20B
'Once/ Month Once/Gycle' Exhaust Monitor' (High Range Noble Cas)
Radwaste/ Augmented Radwaste-'
RMV-RM-30B.
Once/ Month Once/ Cycle-Exhaust Monitor ~
(Iligh Range Noble Gas)
Primary Containment Gross RMA-RM-40A'
'Once/ Month
-Once/ Cycle 7
Radiation Monitors **
RMA-RM-40B; l'
Primary Containment Hydrogen
.'PC-AN-H /0 1 Once/ Month
'Once/ Quarter' 2 2 Concentration Analyzer PC-AN-H /0 II 2 2 i
Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2..F-Drywell' Pressure, i
PC-PR-1A and 13, Suppression Chamber / Torus Water ' Level PC-IR-1A and 1B.
-i 5
+
- CHANNEL CALIBRATION shall consist of an electronic ' calibration of the channel,. not.
including.the.
detector, for range decades above 10.R/hr and a one point calibration check of the' detector below 10 R/hr with an installed or portable gamma source.
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