|
|---|
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
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIMARY SYSTEM BOUNDARY (Cont) 4.6 PRIMARY SYSTEM BOUNDARY (Cont)
B. Coolant Chemistry B. Coolant Chemistry
- 1. The reactor coolant system radioactivity 1. a. A reactor coolant sample shall be concentration In water shall not exceed taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and 20 microcuries of total iodine per ml of analyzed for radioactivity content.
water.
- b. Isotopic analysis of a reactor coolant sample shall be made at least once per month.
l 2. If Specification 3.6.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in Hot Shutdown within 24 hrs. and Cold Shutdown 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. 14,139, 104 202 3/4.6-3
This page is intentionally left blank.
Revision 4A:, 202 B3/4.6-4
BASES:
3/4.6 PRIMARY SYSTEM BOUNDARY (Cont)
B. Coolant Chemistr (Cont)
The Iodine radioactivity will be monitored by reactor water sample analysis. The total iodine activity would not be expected to change over a period of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. In addition, the trend of the stack off-gas release rate, which is continuously monitored, is an indication of the trend of the iodine activity Inthe reactor coolant. Since the concentration of radioactivity in the reactor coolant is not continuously measured, coolant sampling would be ineffective as a means to rapidly detect gross fuel element failures. However, some capability to detect gross fuel element failures is inherent in the radiation monitors in the off-gas system and on the main steam lines.
Revision 477, 202 13314.6-5