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MONTHYEARML0426501462004-09-21021 September 2004 Draft Request for Additional Information Regarding a One-Time Integrated Leak Rate Test Interval Extension Project stage: Draft RAI ML0432804672004-11-10010 November 2004 Response to NRC Request for Additional Information on Plant Request for Amendment to Provide a one-time Integrated Leak Rate Test Interval Extension Project stage: Response to RAI ML0509004102005-03-30030 March 2005 Technical Specifications, Allows One-time Extension of Appendix J Type a Integrated Leakage Rate Test Interval Project stage: Other 2004-09-21
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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
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont)
Primary Containment Integrity Primary Containment Intearity
- 2. a. Primary containment integrity 2. a. The primary containment shall be maintained at all integrity shall be times when the reactor is demonstrated by performing critical or when the reactor Primary Containment Leak water temperature Is above Tests in accordance with 212 0 F and fuel is in the 10CFR50 Appendix J, Option reactor vessel except while B and Regulatory Guide performing "open vessel" 1.163 dated September physics test at power levels 1995*, with exemptions as not to exceed 5 Mw(t). approved by the NRC and exceptions as follows:
Primary containment Integrity means that the drywell and 1. The main steam line pressure suppression isolation valves shall be chamber are intact and that tested at a pressure Z23 all of the following conditions psig, and normalized to are satisfied: a value equivalent to Pa.
- 1. All manual containment 2. Personnel air lock door isolation valves on lines seals shall be tested at connected to the reactor a pressure >10 psig.
coolant system or Results shall be containment which are normalized to a value not required to be open equivalent to Pa during accident conditions 3. Leakage rate acceptance are closed. criteria are:
- 2. At least one door in each 1. Primary containment airlock is closed and overall leakage rate sealed. acceptance criterion is
- 3. All blind flanges and <11.0 La. During the manways are closed. first unit startup following testing in
- 4. All automatic primary accordance with the containment isolation Containment Leakage valves and all Instrument Rate Testing Program, line flow check valves are the leakage rate operable except as acceptance criteria specified in 3.7.A.2.b. are < 0.60 L0 for the Type B and Type C tests and < 0.75 La for the Type A tests.
- 2. Overall air lock leakage rate is < 0.05 L.awhen tested at
>Pa.
- 3. Door seals leakage rate Is < 0.01 La when pressurized to > 10 psig.
The definition of Surveillance Frequency is I not applicable to Leak Rate -rests.
Amendment No. 17, 113, 136, 1142, 167, 213 314.7-4 t
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) A. Primary Containment (Cont)
- 5. All containment isolation check 4. Combined main steam lines:
valves are operable or at least 46 scfh @ 23 psig.
one containment isolation valve where, in each line having an inoperable valve is secured in Pa = 45 psig the isolated position.** La = 1.0% by weight of the contained air
@ 45 psig for 24 hrs.
- 4. NEI 94-01-1995. Section 9.2.3: The first Type A test performed after the May 25, 1995 Type A test shall be performed no later than May 25, 2010.
Primary Containment Isolation Valves Primary Containment Isolation Valves
- 2. b. 1. The primary containment
- 2. b. In the event any automatic isolation valves surveillance Primary Containment Isolation shall be performed as follows:
Valve becomes inoperable, at least one containment isolation a. At least once per operating valve in each line having an cycle the operable primary inoperable valve shall be containment isolation valves deactivated in the isolated that are power operated and condition. (This requirement may automatically initiated shall be satisfied by deactivating the be tested for simulated inoperable valve in the isolated automatic initiation and condition. Deactivation means to closure times.
electrically or pneumatically b. Test primary containment disarm, or otherwise secure the isolation valves:
valve.)*
- 1. Verify power operated primary containment isolation valve operability as specified in 3.13.
- 2. Verify main steam isolation valve operability
- Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under as specified in 3.13.
ORC approved administrative controls.
- Check valve 30-CK-432 will be considered operable until reverse flow testing is performed no later than the 1998 maintenance outage.
Amendment No. 113, 136, 119, 160,167,1714,213 314.7-5
3/4.7 CONTAINMENT SYSTEMS (Cont)
A. Primary Containment (Cont) capability of the structure over its service lifetime. Additional margin to maintain the containment in the "as built' condition is achieved by establishing the allowable operational leak rate. The allowable operational leak rate is derived by multiplying the maximum allowable leak rate or the allowable test leak rate by 0.75 thereby providing a 25% margin to allow for leakage deterioration which may occur during
.he period between leak rate tests.
The primary containment leakage rate testing is based on the guidelines In Regulatory Guide 1.163 dated September 1995, NEI 94-01 Revision 0 dated July 25, 1995, and ANSI/ANS 56.8-1994. Specific acceptance criteria for as-found and as-left leakage rates, as well as methods of defining the leakage rates, are contained in the primary containment leakage rate testing program.
The primary containment leak rate test frequency is based on maintaining adequate assurance that the leak rate remains within the specification. The leak rate test frequency is in accordance with 10CFR50 App. J, Option B and Regulatory Guide 1.163 dated September 1995.
Type A, Type B, and Type C tests will be performed using the technical methods and techniques specified in ANSI/ANS 56.8 - 1994, or other alternative testing methods approved by the NRC.
A note is included in Surveillance 4.7.A.2.a stating that the definition of Surveillance Frequency is not applicable. The 25% allowable extension of surveillance intervals is already included in the primary containment leakage rate testing program; therefore, an additional 25% is not allowed.
The penetration and air purge piping leakage test frequency, along with the containment leak rate tests, is adequate to allow detection of leakage trends.
Whenever a bolted double-gasketed penetration is broken and remade, the space between the gaskets Is pressurized to determine that the seals are performing -
properly. It is expected that the majority of the leakage from valves, penetrations and seals would be Into the reactor building. However, it is possible that leakage into other parts of the facility could occur. Such leakage paths that may affect significantly the consequences of accidents are to be minimized. The personnel air lock is tested at 10 pslg, because the inboard door is not designed to shut .inthe opposite direction.
Primary Containment Isolation Valves Double isolation valves are provided on lines penetrating the primary containment and open to the free space of the containment. Closure of one of the valves In each line would be sufficient to maintain the Integrity of the pressure suppression system.
Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a loss of coolant accident.
Revision M Amendment No. 213 133/4.7-4