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TAC:MC6760, Control Rod SCRAM Time Testing, Clarify Requirement for EDG Start Signal on RPV Level - LOW, LOW, LOW During RPV Cavity FLOOD-UP, Eliminate DG LOCA-START SRS While in S/D When No ECCS is Required, Fuel Movement with Inoperable Refueling Equipment Interlocks (Approved, Closed) |
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Category:Technical Specifications
MONTHYEARML23264A8052023-10-11011 October 2023
Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023
License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks
NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021
Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program
ML20314A2352020-12-0202 December 2020
Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process
ML19238A0072019-10-30030 October 2019
Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
ML18218A4832018-09-0606 September 2018
Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio
ML18137A2102018-05-10010 May 2018
License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio
NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016
Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML15343A3012016-01-22022 January 2016
Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML16021A3222016-01-12012 January 2016
Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML15216A2592015-08-27027 August 2015
Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water
ML15168A1712015-07-14014 July 2015
Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications
ML15135A0052015-05-29029 May 2015
Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS)
NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015
License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
ML14055A0232014-04-29029 April 2014
Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants
ML13191A1052013-09-12012 September 2013
Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report
ML13085A0962013-03-29029 March 2013
Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements
ML12157A2062012-05-30030 May 2012
License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio
ML1136302582012-01-31031 January 2012
Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011
Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves
NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011
License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
ML1101002912011-01-0505 January 2011
Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves
NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009
Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
ML0906207232009-02-26026 February 2009
Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment
ML0815402852008-06-30030 June 2008
Technical Specifications, Measurement Uncertainty Recapture Power Uprate
ML0812202892008-05-12012 May 2008
Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448
NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008
Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007
Corrected Technical Specification Pages
NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007
License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve
ML0630405382006-10-31031 October 2006
Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J
ML0629602942006-10-23023 October 2006
Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities
ML0627700902006-10-0303 October 2006
Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval
ML0625003012006-09-0606 September 2006
Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335
ML0624900372006-09-0505 September 2006
Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566
NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006
License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation
ML0612403772006-05-0303 May 2006
Correction to Amendment No. 218, Technical Specification Page 3.1-12
ML0612304692006-05-0202 May 2006
Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves
ML0611802442006-04-27027 April 2006
Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation
ML0611001622006-04-18018 April 2006
Corrected Technical Specification Page 3.9-1 Re Refueling Operations
NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006
Corrected Technical Specification Page from Amendment No. 218
ML0609004412006-03-30030 March 2006
Technical Specification Pages, Change Request for Various Sections
ML0628404572006-03-10010 March 2006
Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions
NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006
License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program
NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006
License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval
NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006
Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process
ML0602002922006-01-16016 January 2006
Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences
NLS2005102, License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification2005-12-30030 December 2005
License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification
ML0601104792005-12-16016 December 2005
Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation
ML0535000852005-12-15015 December 2005
1 TS Page - Cooper Nuclear Station. Issuance of Amd. 214 Unit Staff Qualifications (Tac. MC7346)
NLS2005051, Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation2005-08-0101 August 2005
Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
2023-09-06
[Table view] |
Text
Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 10 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and b. No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
APPLICABILITY:
MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION TIME A. Requirements of the LCO A.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not met.SURVEILLANCE REQUIREMENTS
NOTE--------------------------
.During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after> 800 psig. each reactor shutdown> 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 200 days control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in> 800 psig. MODE 1 Cooper 3.1 -12 Amendment No. 218 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure.
OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure > 800 psig. fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Cooper 3.1 -1 3 Amendment No. 218 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 1. Core Spray System a. Reactor Vessel Water Level -Low Low Low (Level 1)b. Drywell Pressure-High c. Reactor Pressure-Low (Injection Permissive)
- d. Core Spray Pump Discharge Flow -Low (Bypass)e. Core Spray Pump Start-Time Delay Relay 2. Low Pressure Coolant Injection (LPCI) System 1,2,3.4 (a), 5 (a)1.2.3 1,2,3 4 (a) 5 (a)4(a) s5(a)4(a), 5(a)4 (b)4 (b)4 4 1 per pump 1 per pump B B C-B E C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5> -113 inches< 1.84 psig> 291 psig and< 436 psig> 291 psig and c 436 psig>1370 gpm> 9 seconds and< 11 seconds a. Reactor Vessel Water Level -Low Low Low (Level 1)1.2.3, 4 (a) 5 (a)4 8 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5> -113 inches (continued)(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS -Shutdown.(b) Also required to initiate the associated diesel generator (DG).I Cooper 3.3-37 Amendment 218 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 2. LPCI System (continued)
- b. Drywell Pressure -High 1,2,3 4 B SR 3.3.5.1.2
< 1.84 psig SR 3.3.5.1.4 SR 3.3.5.1.5 c. Reactor Pressure -Low 1,2,3 4 C SR 3.3.5.1.2
> 291 psig (Injection Permissive)
SR 3.3.5.1.4 and SR 3.3.5.1.5
< 436 psig 4 (a), 5 (a) 4 B SR 3.3.5.1.2
> 291 psig SR 3.3.5.1.4 and SR 3.3.5.1.5
< 436 psig d. Reactor Pressure -Low 1 (c).2 (c), 4 C SR 3.3.5.1.2
> 199 psig (Recirculation Discharge SR 3.3.5.1.4 and Valve Permissive) 3 (c) SR 3.3.5.1.5
<221 psig e. Reactor Vessel Shroud 1.2.3 2 8 SR 3.3.5.1.1
>-193.19 Level -Level 0 SR 3.3.5.1.2 inches SR 3.3.5.1.4 SR 3.3.5.1.5 f. Low Pressure Coolant 1.2.3, 1 per pump C SR 3.3.5.1.2 Injection Pump Start -SR 3.3.5.1.4 Time Delay Relay 4 (a). 5 (a) SR 3.3.5.1.5 Pumps BC> 4.5 seconds and< 5.5 seconds Pumps AD< 0.5 second (continued)(a)(c)When associated ECCS subsystems) are required to be OPERABLE per LCO 3.5.2, ECCS -Shutdown.With associated recirculation pump discharge valve open.Cooper 3.3-38 Amendment 218 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 2. LPCI System (continued)
- 9. Low Pressure 1.2,3. 1 per E SR 3.3.5.1.2
> 2107 gpm Coolant Injection Pump subsystem SR 3.3.5.1.4 Discharge Flow -Low 4 (a). 5 (a) SR 3.3.5.1.5 (Bypass)3. High Pressure Coolant Injection (HPCI) System a. ReactorVesselWater 1, 4 B SR 3.3.5.1.1
>-42 inches Level -Low Low SR 3.3.5.1.2 (Level 2) 2 (d) 3 (d) SR 3.3.5.1.4 SR 3.3.5.1.5 b. Drywell Pressure -High 1, 4 B SR 3.3.5.1.2
<1.84 psig SR 3.3.5.1.4 2 (d) 3 (d) SR 3.3.5.1.5 c. ReactorVesselWater 1, 2 C SR 3.3.5.1.1
<54inches Level -High (Level 8) d d SR 3.3.5.1.2 2 (d), 3 d) SR 3.3.5.1.4 SR 3.3.5.1.5 d. Emergency Condensate 1, 2 D SR 3.3.5.1.2
> 23inches Storage Tank (ECST) SR 3.3.5.1.3 Level -Low 2 (d), 3 (d) SR 3.3.5.1.5 e. Suppression Pool Water 1, 2 D SR 3.3.5.1.2
< 4 inches Level -High SR 3.3.5.1.4 2 (d) 3 (d) SR 3.3.5.1.5 (continued)(a) When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS -Shutdown.(d) With reactor steam dome pressure > 150 psig.Cooper 3.3-39 Amendment 218 AC Sources -Shutdown 3.8.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG B.1 Suspend CORE Immediately inoperable.
ALTERATIONS.
AND B.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.
AND B.3 Initiate action to suspend OPDRVs.Immediately AND B.4 Initiate action to restore required DG to OPERABLE status. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ----NOTES-1. The following SRs are not required to be performed:
SR 3.8.1.3, and SR 3.8.1.9 through SR 3.8.1.11.2. SR 3.8.1.11 is considered to be met without the ECCS initiation signals OPERABLE when the ECCS initiation signals are not required to be OPERABLE per Table 3.3.5.1-1.
For AC sources required to be OPERABLE the In accordance SRs of Specification 3.8.1, except with applicable SR 3.8.1.8, are applicable.
SRs I Cooper 3.8-1 2 Amendment No. 21 8 Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 APPLICABILITY:
The refueling equipment interlocks associated with the reactor mode switch refuel position shall be OPERABLE.During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in the refuel position.ACTIONS CONDITION REQUIRED ACTION COMPLETION A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable.
associated with the inoperable interlocks(s).
OR A.2.1 Insert a control rod Immediately withdrawal block AND A.2.2 Verify all control rods Immediately are fully inserted I I I I I I I I I Cooper 3.9-1 Amendment No. 218
