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MONTHYEARML0301602692003-01-14014 January 2003
Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Technical Specifications, for Amendment 195, Page B3/4.6-11, Bases: 3/4.6 Primary System Boundary
Project stage: Other
ML0301500062003-01-14014 January 2003
License Amendment, Relocation of Shock Suppressors (Snubbers) Technical Specification Requirements to Updated Final Safety Analysis Report
Project stage: Other
2003-01-14
[Table View] |
Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Technical Specifications, for Amendment 195, Page B3/4.6-11, Bases: 3/4.6 Primary System Boundary| ML030160269 |
| Person / Time |
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| Site: |
Pilgrim |
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| Issue date: |
01/14/2003 |
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| From: |
Travis Tate
NRC/NRR/DLPM/LPD1 |
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| To: |
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| References |
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| TAC MB5682 |
| Download: ML030160269 (6) |
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Category:Technical Specifications
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Technical Specifications Proposed Change - Administrative Controls for Permanently Defueled Condition
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Technical Specifications, Corrected Page II (Fixed Administrative Error)
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Tech Spec Pages for Amendment 228 Single Control Rod Withdrawal Allowances
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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
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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
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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)
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Tech Spec Pages for Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions
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Technical Specification Pages Re Relocation of Technical Specifications Structural Integrity Requirements to Final Safety Analysis Report
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Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1,
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Tech Spec Pages for Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities
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Tech Spec Pages for Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature
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Technical Specifications Amendment Request to Revise the Surveillance Requirements for the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems
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Correction to Amendment No. 221 Revised Rod Worth Minimizer Bypass Allowances - Technical Specifications
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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
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Technical Specification Page Re Revised Rod Worth Minimizer Bypass Allowances
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Proposed License Amendment to Change Technical Specification 3.6.A.2, Pressure-Temperature Limit Curves
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Tech Spec Pages for Amendment 219 Regarding Single Recirculation Loop Operation
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Technical Specification Pages Re Revised Applicability for Containment Oxygen and Differential Pressure Limits
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Technical Specification Pages Re Surveillance Frequency Improvements
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Technical Specifications Amendment Request to Revise Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Applicability Requirements
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Technical Specifications Amendment Request for Rod Worth Minimizer (RWM) Bypass Allowances
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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
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Technical Specifications, Eliminates Secondary Containment Operability Requirements When Handling Sufficiently Decayed Irradiated Fuel or Performing Core Alterations
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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
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Revision Amendment No. 20, 60, *3, 151 195 3/4.6-9
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Revision Amendment No. 20, 60, 03,154 -195 3/4.6-10
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Revision Amendment No. 20, 40, 60, 151, 153 195 3/4.6-11
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Revision Amendment No. 20. 40, 60. 195 314.6-12
BASES:
3/4.6 PRIMARY SYSTEM BOUNDARY (Cont)
G. Structural Integrity The Pilgrim Nuclear Power Station Inservice Inspection Program conforms to the requirements of 1 OCFR50.55a(g). Where practical, the inspection of ASME Section XI Class 1, 2, and 3 components conforms to the edition and addenda of Section XI of the ASME Boiler and Pressure Vessel Code required by 10CFR50.55a(g). When implementation of an ASME Code required inspection has been determined to be impractical for PNPS, a request for relief from the inspection requirement is submitted to the NRC in accordance with 1 OCFR50.55a(g)(5)(iii).
Requests for relief from the ASME Code inspection requirements will be submitted to the NRC prior to the beginning of each 10 year inspection interval for which the inspection requirement is known to be impractical. Requests for relief from inspection requirements which are identified to be impractical during the course of the inspection interval will be reported to the NRC on an annual basis throughout the inspection interval.
Revision Amendment No. 19, 93,1- 195 B3/4.6-1 1
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Revision Amendment No. 20, 60, 93, 153 195 B3/4.6-12