|
|---|
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
.
LD11 TING CONDITIONS FUR OPERATION SURVEILIANCE REQUIREMENTS 3.7.C (ccr.t'd.)
4.7.C (cont'd.)
a.
The reactor is subcritical and Speci-a.
A preoperational secondary contain=ent fication 3.3. A is cet.
capability test shall be conducted af ter isolating the reactor building and b.
The reactor water temperature is below placing either standby gas treatment 212 F and the reactor coolant system system filter train in operation.
Such is vented.
tests shall demonstrate the capability to maintain 1/4 inch of water vacuum c.
No activity is being performed which under calm wind (2< E< 5 mph) conditions can reduce the rhutdown margin below with a filter train flow rate of not that specified in Specification 3.3.A.
more than 100% of building volume per day.
(p= wind speed) d.
Irradiated fuel is not being handled in the secondary containment, b.
Additional tests shall be performed during the first operating cycle under e.
If seconda ry containment integrity an adequate nu=ber of dif ferent envir-cannot be maintained, restore onmental wind conditicas to enable secondary containment integrity valid extrapolation of the test results.
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or; c.
Secondary containment capability to a.
Be in at least not Shutdown maintain 1/4 inch of water vacuum within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and under calm wind (2< U< 5 mph) condition in cold shutdown within the with a filter train flow rate of not f ollowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
more than 100% of building volume per day, Shall be demonstrated at b.
Suspen3. irradiated fuel handling each refueling outage prior to operations in the secondary con-refueling.
tainment and all core alterations and activities which could reduce d.
After a secondary containment viola-the shutdown margin. The pro-tion is determined, the standby gas visions of Specification 1.0.J treatment system will be operated are not applicabic.
immediately after the affected zones are isolated from the remainder of the secondary containment to confirm its ability to maintain the remainder of the secondary containment at 1/4 inch of water negative pressure under calm wind conditions.
D.
Primary Containment Isolation Valves D.
Primary Containment Isolation Valves 1.
During reactor power operating condi-1.
The primary containment isolation tions, all isolation valves listed in valves surveillance shall be performed Table 3.7.1 and all instrument line as follows:
flow check valves shall be operable except as specified in 3.7.D.2.
a.
At least once per operating cycle the operable isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times.
A valve closure test and verification of closure time shall also be performed
~
prior to returning a valve to service after maintenance, repair or replacemen:
O 00
-166-
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D (cont'd.)
4.7.D (cont'd.)
work is performed on the valve er its associated actuator, control or power circuit.
b.
At least once per quarter:
(1) All normally open power operated isola-tion valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.
(2) With the reactor power less than 75%,
trip main steam isolation valves individually and verify closure time.
c.
At least once per week the main steam line power-operated isolation valves shall be exercised by partial closure and subsequent reopening.
d.
At least once per operating cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.
e.
The valve seals of the primary contain-1 ment and Suppression Chamber Purge and Vent valves shall be replaced at least once per 7 operating cycles.
2.
In the event any isolation valve 2.
Whenever an isolation valve listed in specified in Table 3.7.1 becomes Table 3.7.1 is inoperable, the position inoperable, reactor power operation of at least one other valve in each may continue provided at least one line having an inoperable valve shall valve in each line having an inop-be recorded daily.
erable valve shall be in the mode corresponding to the isolation condi-tion.
If the inoperable valve is not returned to the operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, tag the operable valve closed. Operation may then con-tinue until performance of the next required valve test specified in 4.7.D.l.a.
3.
If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be 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 />.
l I
i
-167-
.. -
