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TAC:MD8556, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR (Approved, Closed) |
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Category:Technical Specifications
MONTHYEARML23095A3762023-04-0505 April 2023 Enclosure 4: Technical Requirements Manual (TRM) Revision 109 ML22196A0612022-08-23023 August 2022 Issuance of Amendment No. 352 Adoption of 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22166A4302022-07-15015 July 2022 Issuance of Amendment No. 351 Removal of Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V JAFP-21-0022, Technical Requirements Manual Specifications - Redacted2022-03-29029 March 2022 Technical Requirements Manual Specifications - Redacted ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21131A1272021-08-0909 August 2021 Issuance of Amendment No. 343 Modifications to Technical Specification 3.6.1.3, Primary Containment Isolation Valves (Pcivs) ML21166A3662021-06-17017 June 2021 Correction to Amendment No. 342 Issued June 14, 2021, One Time Extension to Technical Specifications 3.5.1, 3.6.1.9, and 3.6.4.1 Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21162A0422021-06-14014 June 2021 Issuance of Amendment No. 342, One Time Extension of Completion Times to Support Residual Heat Removal Pump Motor Replacement (Emergency Circumstances) ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20140A0702020-07-21021 July 2020 Issuance of Amendment No. 338 Application of Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML20094G9032020-06-0202 June 2020 Issuance of Amendment No. 335 Adoption of TSTF-372, Addition of LCO 3.0.8, 'Inoperability of Snubbers' RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML20024C6612020-03-0202 March 2020 Issuance of Amendment No. 332 Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line Item Improvement Process ML19301C5552019-10-28028 October 2019 Technical Specification Bases B.3.3.5.2 and B3.3.6.1 Provided by Licensee to Support a 10/28/2019 Public Meeting to Discuss Draft Response to Request for Supplemental Information to Revise Allowable Value for RWCU System Primary Containment ML19277D5522019-10-0404 October 2019 Draft James A. FitzPatrick Nuclear Power Plant - Emergency License Amendment Request - One Time Extension to the TS 3.8.1 Action A.3 Completion Time for an Inoperable Offsite Source ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18214A7062018-09-19019 September 2018 Issuance of Amendment No. 322, Revise Technical Specification 2.1.1, Reactor Core Sls, to Change Cycle 24 Safety Limit Minimum Critical Power Ratio Numeric Values RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement JAFP-16-0142, Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 22016-09-19019 September 2016 Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 2 JAFP-16-0077, Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 12016-06-0303 June 2016 Response to Request for Additional Information (RAI) Regarding Revision to Technical Specification (TS) Administrative Controls for Staffing and Training Upon Permanent Cessation of Operation (CAC No. MF7280) - Supplement 1 ML16062A3882016-04-0606 April 2016 Issuance of Amendment No. 311 Cyber Security Plan Implementation Schedule ML15014A2772015-02-0909 February 2015 Issuance of Amendment Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit ML14202A3722014-12-0101 December 2014 Issuance of Amendment 308 License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 ML14086A1522014-07-16016 July 2014 Issuance of Amendment Change to Renewed Facility Operating License Condition 2.T JAFP-14-0047, Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio2014-05-0101 May 2014 Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio ML14085A4462014-04-14014 April 2014 Issuance of Amendment Revision to the Definition of Shut Down Margin, by Adopting the Nuclear Regulatory Commission Approved Technical Specification Task Force (TSTF) Standard Technical Specification (STS) 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 ML1134308512012-02-14014 February 2012 License Amendment, Issuance of Amendment Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal2011-04-0606 April 2011 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal ML1024604012010-09-27027 September 2010 ME3786, Letter - Issuance of Amendment to Renewed FOL SLMCPR JAFP-09-0132, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves2009-11-23023 November 2009 Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves JAFP-09-0131, Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record2009-11-23023 November 2009 Application for Amendment to Modify Technical Specifications Section 5.5.7, Inservice Testing Program, to Reference the Current Code of Record JAFP-09-0070, Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time2009-06-0404 June 2009 Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time ML0915507232009-06-0303 June 2009 Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time - (Draft) ML0828203902008-10-0303 October 2008 Technical Specification Relocation of Pressure and Temperature Curves to the Pressure and Temperature Limits Report Consistent with TSTF-419-A ML0810102422008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications JAFP-08-0034, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A2008-04-22022 April 2008 Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A JAFP-08-0006, Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-3742008-01-22022 January 2008 Application for Amendment to Technical Specifications Regarding Diesel Fuel Oil, Lube Oil, and Starting Air Consistent with TSTF-501 and Diesel Fuel Oil Testing Program Consistent with TSTF-374 ML0800804572008-01-0303 January 2008 Technical Specifications, Issuance of Amendment Technical Specifications Regarding Control Room Envelope Habitability, Consistent with Technical Specification Task Force-448 JAFP-07-0124, Revision to Application for Technical Specifications (TS) Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP)2007-11-0101 November 2007 Revision to Application for Technical Specifications (TS) Change Based on TSTF-477, Add Action Statement for Two Inoperable Control Room Air Conditioning Subsystems, Using the Consolidated Line Item Improvement Process (CLIIP) JAFP-07-0098, Supplement to Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-08-13013 August 2007 Supplement to Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 JAFP-07-0088, James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 32007-07-17017 July 2007 James A. FitzPatrick, Application for Amendment to Technical Specifications Regarding Control Room Envelope Habitability, Consistent with TSTF-448 Revision 3 ML0717601272007-06-21021 June 2007 Technical Specifications (Ts), Revised TS 3.10.1, Inservice Leak and Hydrostatic Testing Operation, Consistent with Technical Specification Task Force-484 ML0714303022007-05-17017 May 2007 Technical Specifications, Allow Additional Startup and Operating Flexibility and an Expanded Operating Domain JAFP-07-0023, Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-4842007-02-15015 February 2007 Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-484 ML0625802332006-09-14014 September 2006 Tech Spec Pages for Amendment 286 Technical Specifications on DC Electrical System Requirements 2023-04-05
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-3 (4) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is SUbject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement NO.1 dated February 1, 1973; the SER Supplement NO.2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),80 (dated May 22,1984),134 (dated July 19,1989),135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16,1992),177 (dated February 10,1992),186 (dated February 19,1993),190 (dated June 29,1993),191 (dated July 7,1993),
206 (dated February 28,1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 SUbject to the following provision:
Amendment No. 292 Renewed License No. DPR 59
Definitions 1.1 1.1 Definitions (continued)
LINEAR HEATGENERATION The LHGR shall be the heat generation rate per unit RATE (lHGR) length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power that RATIO (MCPR) exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MODE A MODE shall correspond to anyone inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolttenslonlng specified in Table 1.1-1 with fuel in the reactor vessel.
OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem. division, component. or device to perform its specified safety function(s) are also capable of performing their related support function(s).
PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (pTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
(continued)
JAFNPP 1.1-4 Amendment 2q2
RCS PIT Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (PIT) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. - - - - - NOTE - - - - - - A.1 Restore parameter(s) to 30 minutes Required Action A.2 shall within limits.
be completed if this Condition is entered. ANQ
A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Requirements of the LCO acceptable for not met in MODE 1,2, or 3. continued operation.
B. Required Action and B.l Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 4. 36. hours (continued)
JAFNPP 3.4.9-1 Amendment 2q2
RCS PIT limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 ------------NOTE-----------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
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Verify: 30 minutes
- a. RCS pressure and RCS temperature are within the limits specified In the curves in the PTLR as applicable; and
- b. RCS temperature change averaged over a one hour period is:
- 1. 5: 100°F when the RCS pressure and RCS temperature are on or to the right of curve C in the PTLR as applicable, during inservice leak and hydrostatic testing;
- 2. s 20°F when the RCS pressure and RCS temperature are to the left of curve C In the PTLR as applicable, during inservice leak and hydrostatic testing; and
- 3. 5: 100°F during other heatup and cooldown operations.
(continued)
JAFNPP 3.4.9-3 Amendment 292
RCS PIT Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within Once within the criticality limits specified in the PTLR. 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3 - - - - - - - - NOTES-----------
- 1. Only required to be met in MODES 1, 2, 3, and 4 during reclrcutatlon pump startup.
- 2. Not required to be performed if SR 3.4.9.4 is satisfied.
Verify the difference between the bottom head coolant Once within temperature and the reactor pressure vessel (RPV) 15 minutes prior to coolant temperature is within the limits specified in each startup of a the PTLR. recirculation pump SR 3.4.9.4 - - - - - - - - NOTES - - - - - - - - - -
- 1. Only required to be met in MODES 1, 2,3, and 4 during recirculation pump startup.
- 2. Not required to be met if SR 3.4.9.3 is satisfied.
Verify the active recircUlation pump flow exceeds 40%
of rated pump flow or the active recirculation pump Once within has been operating below 40% rated flow for a period 15 minutes prior to no longer than 30 minutes..
Ieach startup of a reclrculatlon pump (continued)
JAFNPP 3.4.9-4 Amendment 292
RCS PfT limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.5 - - - - - - - - - - NOTES - - - - - - - - - - Once within Only required to be met in MODES 1. 2. 3. and 4 15 minutes prior during recirculation pump startup. to each startup of a recirculation pump Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.
SR 3.4.9.6 -----------NorrS-----------
Only required to be performed when tensioning the reactor vessel head bolting studs.
Verify, when the reactor vessel head bolting studs are 30 Minutes under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
SR 3.4.9.7 - - - - - - - - - - NOTES - - - - - - - - - - -
Not required to be performed until 30 minutes after RCS temperature s 80°F with any reactor vessel head bolting stud tensioned.
Verify, when the reactor vessel head bolting studs are 30 minutes under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
(continued)
JAFNPP 3.4.9-5 Amendment 292
RCS PjT Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.8 - - - - - - - -- -- NOTES-----------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature s 100°F with any reactor vessel head bolting stud tensioned.
Verify, when the reactor vessel head bolting studs are 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
JAFNPP 3.4.9-6 Amendment ~2
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1, 'Post Accident Monitoring (PAM) Instrumentation,* a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Reactor Coolant System (RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
i) Limiting Conditions for Operation Section 3.4.9 "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.9 "RCS Pressure and Temperature (PIT) Limits"
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
i) SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors" ii) SIA Calculation 0800846.301, "2" Instrument Nozzle Stress Analysis"
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
JAFNPP 5.6-3 Amendment No. 292