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MONTHYEARML0611402652006-04-10010 April 2006
Technical Specification Pages Re Revised Applicability for Containment Oxygen and Differential Pressure Limits
Project stage: Other
ML0531404332006-04-10010 April 2006
Issuance of Amendment Revised Applicability for Containment Oxygen and Differential Pressure Limits
Project stage: Approval
2006-04-10
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Category:Technical Specifications
MONTHYEARML20328A2972020-12-0101 December 2020
Amendment No. 253 - Non-Safeguards Version
ML19276C4202020-01-0202 January 2020
Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition
ML19235A0502019-08-27027 August 2019
Issuance of Amendment No. 249 Order Approving Direct Transfer of Renewed Facility Operating License and ISFSI General License and Conforming Amendment
ML17163A1812017-05-25025 May 2017
Supplemental to Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition
ML17053A4682017-02-14014 February 2017
Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition
ML16363A2662017-01-10010 January 2017
Correction to Amendment No. 234 Change in Technical Specification Measurement Frequency from 18 Months to 24 Months
ML16250A2232016-10-28028 October 2016
Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician
ML15114A0212015-05-0606 May 2015
Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request
ML14272A0702015-03-12012 March 2015
Issuance of Amendment 242 Re Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open Transient
ML14295A6852014-10-31031 October 2014
Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations
ML14259A3812014-09-11011 September 2014
Supplement to Proposed License Amendment Request to Modify Technical Specification 4.3.4, Heavy Loads to Facilitate Dry Storage Handling Operations
ML13108A2172013-04-0505 April 2013
Proposed License Amendment: Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open (PRFO) Transient Reported by General Electric Nuclear Energy in Accordance with 10 CFR 21.21(d)
CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012
Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications
ML12005A1982011-12-29029 December 2011
Cycle-Specific License Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowance to Allow Reactor Startup
ML0731004782007-11-0505 November 2007
Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements
ML0726101972007-09-18018 September 2007
Technical Specifications, Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers
ML0726102002007-05-17017 May 2007
Technical Specifications, Corrected Page II (Fixed Administrative Error)
ML0715605422007-04-25025 April 2007
Tech Spec Pages for Amendment 228 Single Control Rod Withdrawal Allowances
ML0714303052007-04-25025 April 2007
Technical Specifications, Limiting Conditions for Operation
ML0708603592007-03-26026 March 2007
Technical Specifications, Issuance of License Amendment 226 Adoption of Technical Specification Task Force (TSTF) Change TSTF-484 Use of TS 3.10.1 for Scram Time Testing Activities.
ML0708603392007-02-22022 February 2007
Technical Specifications, Modify the TSs to Extend the Use of the Current Pressure-Temperature Limits as Specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 Through the End of Operating Cycle 18
ML0702302932007-01-15015 January 2007
Proposed Change to Applicability of Pilgrim'S Pressure - Temperature Curves as Described in Technical Specification Figures 3.6.1, 3.6.2, and 3.6.3, Revision 1
ML0631303512006-11-0202 November 2006
Application for Technical Specification (TS) Change to Add LCO 3.0.8 on the Inoperability of Snubbers (and Adoption of TS Bases for LCO 3.0.8) Using the Consolidated Line Item Improvement Process (CLIIP)
ML0626405822006-09-20020 September 2006
Tech Spec Pages for Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions
ML0626202402006-09-14014 September 2006
Technical Specification Pages Re Relocation of Technical Specifications Structural Integrity Requirements to Final Safety Analysis Report
ML0624904892006-08-30030 August 2006
Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1,
ML0622800132006-08-0909 August 2006
Tech Spec Pages for Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities
ML0622301672006-08-0404 August 2006
Tech Spec Pages for Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature
ML0618704692006-06-30030 June 2006
Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems
ML0613000952006-05-0505 May 2006
Correction to Amendment No. 221 Revised Rod Worth Minimizer Bypass Allowances - Technical Specifications
ML0610702152006-04-13013 April 2006
Technical Specification Page, Deletes the Main Steam Isolation Valve Twice Per Week Partial Stroke Testing Surveillance Specified in Technical Specification 4.7.A.2.b.1.c
ML0610702042006-04-13013 April 2006
Technical Specification Page Re Revised Rod Worth Minimizer Bypass Allowances
ML0610908322006-04-12012 April 2006
Proposed License Amendment to Change Technical Specification 3.6.A.2, Pressure-Temperature Limit Curves
ML0610701672006-04-12012 April 2006
Tech Spec Pages for Amendment 219 Regarding Single Recirculation Loop Operation
ML0611402652006-04-10010 April 2006
Technical Specification Pages Re Revised Applicability for Containment Oxygen and Differential Pressure Limits
ML0524301522005-08-29029 August 2005
Technical Specification Pages Re Surveillance Frequency Improvements
ML0521400792005-07-29029 July 2005
Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Valves
ML0515204742005-05-24024 May 2005
Technical Specifications Amendment Request to Revise Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Applicability Requirements
ML0515204582005-05-24024 May 2005
Technical Specifications Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowances
ML0515204732005-05-24024 May 2005
Request for Amendment to the Technical Specifications to Delete Requirement Related to NRC Approval of Engineering Evaluation for Elevated Safety Relief Valve Discharge Pipe Temperature
ML0512200952005-04-28028 April 2005
Technical Specifications, Eliminates Secondary Containment Operability Requirements When Handling Sufficiently Decayed Irradiated Fuel or Performing Core Alterations
ML0510400322005-04-12012 April 2005
Technical Specifications, Revision to Surveillance Requirement Frequency for Containment and Suppression Pool Spray Headers and Nozzles
ML0509004102005-03-30030 March 2005
Technical Specifications, Allows One-time Extension of Appendix J Type a Integrated Leakage Rate Test Interval
ML0507601772005-03-16016 March 2005
Tech Spec Pages for Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements
ML0503800052005-02-0202 February 2005
Tech Spec Page for Amendment 210 Changes to Technical Specifications Table 3.2.C-1
ML0500701552005-01-0505 January 2005
Technical Specification Pages for Amendment No. 209 to License No. DPR-35
ML0423206092004-08-17017 August 2004
Technical Specifications, Issuance of Amendment Re.: Multiple Control Rod Removal, Limiting Condition for Operation 3/4.10.D
ML0420502772004-07-22022 July 2004
Tech Spec Pages for Amendment 206 Elimination of Requirements for Hydrogen Analyzers
ML0403307902004-01-30030 January 2004
License Amendment, Tech Spec Pages
ML0332100752003-11-14014 November 2003
Revised TS Page 5.0-7, Eliminating Requirements for Post-Accident Sampling System
2020-12-01
[Table view] |
Text
LIMTl-ING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7. !ONTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont)
- e. In order to continue reactor power d. Whenever there is indication of relief operation, the suppression chamber valve operation with the local pool bulk temperature must be temperature of the suppression pool reduced to <8b0 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. T-quencher reaching 2000 F or more, an external visual examination of the
- f. If the suppression pool bulk suppression chamber shall be temperature exceeds the limits of conducted before resuming power Specification 3.7.A.1.d, RCIC, HPCI operation.
or ADS testing shall be terminated and suppression pool cooling shall e. A visual inspection of the suppression be initiated. chamber interior, including water line regions, shall be made at each major
- g. If the suppression pool bulk refueling outage.
temperature during reactor power operation exceeds 11 O0 F, the f. (Deleted) reactor shall be scrammed.
- g. Suppression chamber water level
- h. During reactor isolation conditions, shall be recorded at least once each the reactor pressure vessel shall be shift when the differential pressure is depressurized to less than 200 psig required.
at normal cool down rates if the pool bulk temperature reaches 120'F.
I i. (Deleted)
I j. (Deleted)
Amendment No. 4-S. 21' 4.
3/4.7-2
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 COIJTAINMENT SYSTEMS (CONT) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont)
- k. (Deleted)
I. (Deleted) mn.Suppression chamber water level shall be between -6 to -1 inches on torus level instrument which corresponds to a downcomer submergence of 3 feet to 3 feet 5 inches.
- n. The suppression chamber can be drained if the conditions as specified in Section 3.5.F.5 of this Technical Specification are adhered to.
Amendment No. 17, 113, 163, 200,218 314.7-3
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont)
- d. If a failure of one of the two installed position alarm systems occurs for one or more vacuum breakers, reactor operation may continue provided that a differential pressure decay rate test is initiated immediately and performed every 15 days thereafter until the failure is corrected. The test shall meet the requirements of Specification 3.7.A.4.b.
- 5. If the specifications of 3.7.A.1 thru 3.7.A.4 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I 6. Oxygen Concentration 6. Oxygen Concentration I
- a. The primary containment The primary containment o)ygen atmosphere shall be reduced to concentration shall be measured and less than 4% oxygen by volume recorded at least twice weekly with nitrogen gas while in RUN MODE during the time period:
- i. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power is greater than 15%
rated thermal power following startup, to ii. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing thermal power to less than 15% rated thermal power prior to the next scheduled shutdown, except as specified in 3.7.A.6.b.
- b. If the specifications of 3.7.A.6.a above cannot be met, and the primary containment oxygen concentration cannot be restored to less than 4% oxygen by volume within the subsequent 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, reactor thermal power shall be less than 15%
rated thermal power within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Amendment No. 87,-1-^ , 218 314.7-9
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont)
- 7. Containment AtmosDhere Dilution 7. Containment Atmosohere Dilution
- a. Within the 24-hour period after a. The post-LOCA containment placing the reactor in the Run Mode atmosphere dilution system shall be the Post - LOCA Containment functionally tested once per operating Atmosphere Dilution System must cycle.
be operable and capable of supplying nitrogen to the containment for atmosphere dilution. If this specification cannot be met, the system must be restored to an operable condition within 30 days or the reactor must be at least in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. Within the 24-hour period after b. The level in the liquid N2 storage tank placing the reactor in the Run shall be recorded weekly.
Mode, the Nitrogen Storage Tank
- c. Not used.
shall contain a minimum of 1500 gallons of liquid N2. If this d. Once per month each manual or specification cannot be met the power operated valve in the CAD minimum volume will be restored system flow path not locked, sealed within 30 days or the reactor must or otherwise secured in position shall be in at least Hot Shutdown within be observed and recorded to be in its 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. correct position.
- 8. Drvwell and Suopression Chamber 8. Drywell and Sumroression Chamber Differential Pressure Differential Pressure
- a. Differential pressure between the a. The pressure differential between drywell and suppression chamber the drywell and suppression shall be maintained at equal to or chamber shall be recorded at least greater than 1.17 psid, while in once each shift when the differential RUN MODE during the time period: pressure is required.
- i. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power is greater than 15%
rated thermal power following startup, to ii. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing thermal power to less than 15% rated thermal power prior to the next scheduled shutdown, except as specified in 3.7.A.8.b and c.
Amendment No. 5, 206, 218 3/4.7-1 0
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont) to. The differential pressure may be reduced to less than 1.17 psid for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for maintenance activities on the differential pressure control system and during required operability testing of the HPCI system, the relief valves, the RCIC system and the drywell-suppression chamber vacuum breakers.
- c. If the specifications of 3.7.A.8.a and b above cannot be met, and the differential pressure cannot be restored within the subsequent 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, reactor thermal power shall be less than 15% rated thermal power within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendmeit No. 65, 206, 21 /
3/4.7-1 Oa