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MONTHYEARML0435601512004-12-14014 December 2004 Technical Specifications Amendment Request to Revise Actions for Scram Discharge Volume (SDV) Vent and Drain Valves Consistent with Technical Specifications Task Force (TSTF) Change Traveler, TSTF-404 Project stage: Other ML0518702572005-07-29029 July 2005 License Amendment 216 Revised Action for Scram Discharge Volume Vent and Drain Valves Project stage: Approval ML0521400792005-07-29029 July 2005 Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Valves Project stage: Other 2004-12-14
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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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TABLE OF CONTENTS 1.0 DEFINITIONS 1-1 2.0 SAFETY LIMITS 2-1 2.1 Safety Limits 2-1 2.2 Safety Limit Violation 2-1 BASES B2-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITION FOR OPERATION 4.0 3/4.0-1 (LCO) APPLICABILITY 3.1 REACTOR PROTECTION SYSTEM 4.1 3/4.1-1 BASES B3/4.1 -1 3.2 PROTECTIVE INSTRUMENTATION 4.2 3/4.2-1 A. Primary Containment Isolation Functions A 3/4.2-1 B. Core and Containment Cooling Systems B 3/4.2-1 C. Control Rod Block Actuation C 3/4.2-2 D. Radiation Monitoring Systems D 3/4.2-2 E. Drywell Leak Detection E 3/4.2-3 F. Surveillance Information Readouts F 314.2-3 G. Recirculation Pump Trip/ Alternate Rod Insertion G 3/4.2-4 H. Drywell Temperature H 3/4.2-5 BASES 83/4.2-1 3.3 REACTIVITY CONTROL 4.3 3/4.3-1 A. Reactivity Margin - Core Loading A 3/4.3-1 B. Control Rod Operability B 3/4.3-2 C. Scram Insertion Times C 3/4.3-7 D. Control Rod Accumulators D 3/4.3-8 E. Reactivity Anomalies E 3/4.3-10 F. Rod Worth Minimizer (RWM) F 3/4.3-11 G. Scram Discharge Volume (SDV) G 3/4.3-12 H. Rod Pattern Control H 3/4.3-13 BASES 63/4.3-1 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 3/4.4-1 BASES B3/4.4-1 3.5 CORE AND CONTAINMENT COOLING 4.5 3/4.5-1 SYSTEMS A. Core Spray and LPCI Systems A 3/4.5-1 B. Containment Cooling System B 3/4.5-3 C. HPCI System C 3/4.5-7 D. Reactor Core Isolation Cooling (RCIC) System D 3/4.5-8 E. Automatic Depressurization System (ADS) E 3/4.5-9 F. Minimum Low Pressure Cooling and Diesel F Generator Availability 3/4.5-10 G. (Deleted) G 3/4.5-11 H. Maintenance of Filled Discharge Pipe H 3/4.5-12 BASES ' B3/4.5-1 Amendment 486,203, 216
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)
I G. Scram Discharge Volume (SDV) G. Scram Discharge Volume (SDV) I LCO 3.3.G SR 4.3.G.1 The scram discharge volume drain & vent Verify scram discharge volume drain valves shall be OPERABLE. and vent valves open at least once per month.
APPLICABILITY:
SR 4.3.G.2 RUN and STARTUP MODES; REFUEL MODE when the reactor Test scram discharge volume drain and vessel head is fully tensioned. vent valves as specified in 4.13. These valves may be closed intermittently for ACTIONS: testing under administrative control.
- ------ - NOTE --------------- SR 4.3.G.3 ACTIONS may be applied independently to each vent or drain line. During each REFUELING INTERVAL verify the scram discharge volume drain A. With one or more SDV vent or drain and vent valves.
lines with one valve inoperable, isolate* the associated line within 7 a. Close within 30 seconds after days. receipt of a reactor scram signal.
B. One or more SDV vent or drain lines AND with both valves inoperable, isolate*
the associated line within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. b. Open when the scram is reset.
C. Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(*) An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.
3/4.3-1 2 Amendment No. 186, 216
Scram Discharge Volume Vent and Drain Valves B 3/4.3.G B 3/4.3 REACTIVITY CONTROL BASES LCO The OPERABILITY of all SDV vent and drain valves ensures that the SDV vent and drain valves will close during a scram to contain reactor water discharged to the SDV piping. Since the vent and drain lines are provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to open on a scram reset to ensure that a path is available for the SDV piping to drain freely at other times.
APPLICABILITY In the RUN and STARTUP MODES, scram may be required; therefore, the SDV vent and drain valves must be OPERABLE. In the HOT SHUTDOWN and COLD SHUTDOWN MODES, control rods are not able to be withdrawn since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate requirements for control rod OPERABILITY during these conditions.
CTS 3/4.10, "CORE ALTERATIONS", provides requirements to ensure that core reactivity is within the capability of the control rods and to prevent criticality during refueling conditions.
ACTIONS The ACTIONS are modified by a Note indicating that the ACTIONS may be independently applied for each SDV vent and drain line. This is acceptable, since the ACTIONS for each condition provide appropriate compensatory actions for each inoperable SDV line.
Complying with the ACTIONS may allow for continued operation, and subsequent inoperable SDV lines are governed by subsequent ACTION entry.
When a line is isolated, the potential for an inadvertent scram due to high SDV level is increased. During these periods, Footnote
- allows for the line to be unisolated under administrative control. This allows any accumulated water in the line to be drained, to preclude a reactor scram on SDV high level. This is acceptable since the administrative controls ensure the valve can be closed quickly, by a dedicated operator, if a scram occurs with the valve open.
A When one SDV vent or drain valve is inoperable in one or more lines, the associated line must be isolated to contain the reactor coolant during a scram. The 7 day Completion Time is reasonable, given the level of redundancy in the lines and the low probability of a scram occurring while the valve(s) are inoperable and the line is not isolated.
(continued)
Revision 214-2, 216 B 3/4.3-34
Scram Discharge Volume Vent and Drain Valves B 3/4.3.G B 3/4.3 REACTIVITY CONTROL BASES ACTIONS (continued) The SDV is still isolable since the redundant valve in the affected line is OPERABLE. During these periods, the single failure criterion may not be preserved, and a higher risk exists to allow reactor water out of the primary system during a scram.
B If both valves in a line are inoperable, the line must be isolated to contain the reactor coolant during a scram. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time to isolate the line is based on the low probability of a scram occurring while the line is not isolated and unlikelihood of significant CRD seal leakage.
C If any Required Action and associated Completion Time is not met, the plant must be brought to a condition in which the LCO does not apply. To achieve this status, the plant must be brought to at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach HOT SHUTDOWN from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 4.3.G.1 and SR 4.3.G.2 REQUIREMENTS During normal operation, the SDV vent and drain valves should be in the open position (except when performing SR 4.3.G.2) to allow for drainage of the SDV piping. Verifying that each valve is in the open position (SR 4.3.G.1) ensures that the SDV vent and drain valves will perform their intended functions during normal operation. This SR does not require any testing or valve manipulation; rather, it involves verification that the valves are in the correct position.
The 31 day frequency is based on engineering judgment and is consistent with the procedural controls governing valve operation, which ensure correct valve positions.
Revision 24-2, 216 B 3/4.3-34a