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Category:Technical Specification
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. ML22292A1312022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Technical Specification Bases, Rev. 69 RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls NMP2L2693, Technical Specification Bases, Rev. 572018-10-24024 October 2018 Technical Specification Bases, Rev. 57 NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML16309A4002016-10-24024 October 2016 Revision 47 to Technical Specification Bases, List of Effective Pages ML16309A4022016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B2.0, Safety Limits (Sls) ML16309A4032016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.0, Limiting Condition for Operation (LCO) Applicability ML16309A4012016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Table of Contents ML16309A4082016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.5, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System ML16309A4132016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.9, Refueling Operations ML16309A4052016-10-24024 October 2016 Revision 47 to Technical Specification Bases, Section B3.2, Power Distribution Limits ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance2016-03-18018 March 2016 License Amendment Request - Reactivity Anomalies Surveillance NMP2L2592, Supplemental Information Regarding TSTF-425 License Amendment Request2015-09-24024 September 2015 Supplemental Information Regarding TSTF-425 License Amendment Request NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) ML15089A2312015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP1L3010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-03-26026 March 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML12156A3632012-06-0101 June 2012 Emergency License Amendment Request Pursuant to 10 CFR 50.90: Revision of the Main Steam Isolation Valve Allowable Leakage Rate Limit ML11306A2982011-10-27027 October 2011 Submittal of Revision 22 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML11214A2142011-07-25025 July 2011 License Amendment Request, Extension of the Completion Time for Inoperable Diesel Generator - Response to NRC Request for Additional Information ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0931602572009-10-26026 October 2009 Submittal of Revision 21 to the Final Safety Analysis Report (Updated), 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases Changes, and Report Consistent with 10 CFR 54.37(b) ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0802501622008-01-24024 January 2008 Response to NRC Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No. 1, Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup ML0726401032007-09-19019 September 2007 License Amendment Request for Adoption of TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities. ML0721906052007-07-30030 July 2007 Application for Technical Specification Change TSTF-477, Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process ML0721205922007-07-23023 July 2007 Application for Technical Specification Improvement to Adopt TSTF-476, Revison 1, Improved BPWS Control Rod Insertion Process (NEDO-33091), Using the Consolidated Line Item Improvement ML0721205872007-07-23023 July 2007 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Rod Worth Minimizer Limiting Condition for Operation During Startup - Technical Specification Section 3.1.1.b ML0720504232007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0630406022006-10-19019 October 2006 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Control Rod System Surveillance Requirements - Technical Specification 4.1.1 2023-05-25
[Table view] Category:Amendment
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP2L2718, Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22019-12-12012 December 2019 Supplemental Information No.1 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22018-01-12012 January 2018 Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP1L3027, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)2015-05-12012 May 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) NMP2L2576, License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2015-03-23023 March 2015 License Amendment Request - Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP2L2563, License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change2014-11-17017 November 2014 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML1109602832011-03-30030 March 2011 License Amendment Request Pursuant to 10 CFR 50.90: Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage ... ML0935000902009-12-0909 December 2009 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery - Technical Specification 3.8.4, DC Sources - Operating ML0907802502009-03-0909 March 2009 Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0906403012009-03-0303 March 2009 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML0827502992008-09-29029 September 2008 Technical Specifications ML0720504742007-07-12012 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0707800592007-03-15015 March 2007 Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements ML0536202882005-12-16016 December 2005 License Amendment Request: Proposed Changes to Technical Specification 4.1.4 Regarding Core Spray Instrumentation ML0511100732005-04-19019 April 2005 Tech Spec Pages for Amendment 115 and 188 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510204002005-04-0101 April 2005 License Amendment Request Pursuant to 1O CFR 50.90: Request for Amendment to Extend Completion Time for Emergency Uninterruptible Power Supply Inverters ML0503304712005-01-24024 January 2005 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports ML0424003162004-08-17017 August 2004 Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration ML0421103812004-07-16016 July 2004 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a License-Controlled Document ML0403302112004-01-27027 January 2004 TS Amendment Pages for License No. NPF-069 ML0330305992003-10-27027 October 2003 TS Pages Amendment 183 ML0324608472003-08-15015 August 2003 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Reactor Pressure Vessel Pressure-Temperature Limits ML0233807302002-11-22022 November 2002 Facility Operating License DPR-63, License Amendment Request: Technical Specifications Section 6.0, Administrative Controls - Response to RA Information TAC No. MB2441 ML0229603382002-10-0707 October 2002 Application for Technical Specification Change Regarding Missed Surveillances Using the Consolidated Line Item Improvement Process ML0217101682002-06-0707 June 2002 Application for Technical Specification Improvement to Eliminate the Requirements for the Post Accident Sampling System Using the Consolidated Line Item Improvement Process ML0207305992002-03-13013 March 2002 Technical Specifications, Issuance of Amendment Safety Limit Minimum Critical Power Ratio (Tac No. MB3327) ML0206302682002-03-0101 March 2002 Technical Specifications for Amendment No. 103 ML0204301512002-02-11011 February 2002 Issuance of Amendment Ventilation Requirements During Irradiated Fuel Handling ML18018B0461978-03-22022 March 1978 Letter Transmitting an Application for Amendment to Appendix a of the Operating License ML17037C4331977-08-0808 August 1977 Letter Regarding Surveillance Requirements and Limiting Conditions for Operations and Requesting an Application for Amendment to the Operating License That Will Change the Technical Specifications ML17037C4131977-07-22022 July 1977 Letter Enclosing Application for Amendment to Operating License and Proposed Changes to Technical Specifications Concerning Changes in Management and Organization ML17037C4141977-07-18018 July 1977 Letter Enclosing an Application for Amendment to Operating License and Proposed Changes to the Technical Specifications to Provide for More Flexible Operation and Concerning Load Line Limit Analysis ML17037C4161977-07-14014 July 1977 Application for Amendment to Operating License and Proposed Change to Technical Specification Concerning the Emergency Cooling System ML17037C4181977-05-19019 May 1977 Letter Enclosing an Application to Amend Operating License and a Requested Change in the Technical Specifications Relating to Instrumentation Used to Monitor Drywell Suppression Chamber Differential Pressure and Suppression .. ML17037C4341977-03-0404 March 1977 Letter Regarding a Preliminary Review of the December 7, 1976 Request for Technical Specification Changes to Reactor Operating Limits After Reload for Cycle 5 Operation and Requesting Additional Information to Complete Review ML17037C4391976-09-30030 September 1976 Letter Requesting Submittal of an Application for License Amendment to Incorporate the Requirements of the Model Technical Specifications ML17037C4531976-01-19019 January 1976 Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications (Appendix a) to Clarify Cloride and Oxygen Levels ML17037C1771975-12-19019 December 1975 Letter Enclosing a Corrected Attachment to License Amendment No. 11 Change No. 27 to the Technical Specifications Provisional Operating License No. DPR-16 ML17037C1831975-11-0303 November 1975 Letter Regarding Application for Amendment to Technical Specifications and an Inadvertent Error Not Made on the Persons Listed in the Certificate of Service ML17037C4681975-09-23023 September 1975 Letter Regarding a Stress Assisted Corrosion Problem and an Enclosed Safety Evaluation by the Office of NRR - Supporting Amendment to License No. DPR-63 and Changes to the Technical Specifications Inoperable Control Rod .. ML17037C4541975-09-0808 September 1975 Letter Transmitting an Application for Amendment to Operating License and a Proposed Change to Technical Specifications Correcting Errors in a Submittal Made August 15, 1975 in Connection with Reload Cycle 5 2023-05-25
[Table view] |
Text
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREIVIENT LIMITING FOR OPERATION CONDITION SURVEILLANCE REQUIR~~~~~~~~~~~~~~~r~IENT~
- c. During leakage and hydrostatic testing, the In order to generate additional plant-specific reactor vessel temperature and pressure shall data, a capsule containing irradiated and satisfy the requirements of Figure 3.2.2.e, if the unirradiated material will be re-inserted at the B core is not critical. During reactor vessel heatup capsule location. Re-insertion capsules have and cooldown for the purpose of leakage and already been installed at the A and C locations.
hydrostatic testing, the reactor vessel A prime (') is used to indicate a re-insertion temperature and pressure shall satisfy the capsule. The withdrawal schedule for the re-requirements of Figures 3.2.2.a and 3.2.2.b for insertion capsules is as follows:
non-critical heatup and cooldown, respectively.
Fourth capsule (A') - 24 EFPY
- d. The reactor vessel head bolting studs shall not Fifth capsule (C') - 32 EFPY be under tension unless the temperature of the Sixth capsule (B') - 40 EFPY vessel head flange and the head are equal to or greater than 100oF.
AMENDNENT NO. 142 164, 183 884
HEATUP - CORE NOT CRITICAL 1500 Minimum Temperature for Boltup:
100 0 F 1000 REACTOR PRESSURE (psig) 500 0
0 50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE ( 0F)
(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)
(instrument uncertainties have been included in this figure)
FIGURE 3.2.2.a MINIMUM BELTUNE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING HEATUP AND LOW-POWER PHYSICS TESTS (CORE NOT CRITICAL) (HEATING RATE*O 100°F/HR)
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF OPERATION AMENDMENT NO. 142, 164, 183 85
LIMIT FOR NON-CRITICAL OPERATION HEATUP AT UP TO 100OF/HR REACTOR VESSEL BELTLINE REACTOR PRESSURE (psig) DOWNCOMER WATER IN TOP DOME TEMPERATURE (OF) 0 100 298 100 298 102 298 107 298 112 298 117 298 122 298 127 298 132 300 137 304 142 311 147 319 152 329 157 340 162 354 167 369 172 387 177 406 182 406 182 429 187 454 192 483 197 515 202 547 207 582 212 622 217 665 222 713 227 767 232 840 238 840 238 895 242 969 247 1050 252 1140 257 (reactor vessel beltine downcomer water temperature is measured at recirculation loop suction)
(instrument uncertainties have been Included in this table)
TABLE 3.2.2.a MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEAT-UP (CORE NOT CRITICAL) (hEATING RATE
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF CORE OPERATION AMENDMENT NO. 1492 164, 183 86
COOLDOWN - CORE NOT CRITICAL 1500 Minimum Temperature for Boltup:
1000 F 1000 REACTOR PRESSURE (psig) 500 0
0 50 100 150 200 250 300 350 400 REACTOR VESSEL BELTUNE DOWNCOMER WATER TEMPERATURE (°F)
(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)
(instrument uncertainties have been included in this figure)
FIGURE 3.2.2.b MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING COOLDOWN AND LOW-POWER PHYSICS TESTS (CORE NOT CRITICAL) (COOLING RATE< I00°FIHR)
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF OPERATION AMENDMENT NO. 142, 16X, 183 87
LIMIT FOR NON-CRITICAL OPERATION COOLDOWN AT UP TO 1000FMI1R REACTOR VESSEL BELTLINE REACTOR PRESSURE (psig) DOWNCOMER WATER IN TOP DOME TEMPERATURE (0FF) 0 100 205 100 209 100 213 100 218 100 223 100 229 100 235 100 242 100 250 100 254 100 258 102 268 107 278 112 290 117 302 122 316 127 332 132 349 137 360 140 360 160 455 160 471 163 471 163 498 . 167 532 172 570 177 613 182 659 187 701 192 737 197 777 202 820 207 869 212 922 217 982 222 1047 227 1119 232 (reactor vessel beltline downcomer water temperature Is measured at recirculation loop suction)
(instrument uncertainties have been included in this table)
TABLE 3.2.2.b MINIMUM TEMPERATURE FOR PRESSURIZATION DURING COOLDOWN (CORE NOT CRITICAL) (COOLING RATE
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF CORE OPERATION AMENDIVENT NO. 142,4-64, 183 88
HEATUP - CORE CRITICAL 1500 Minimum Temperature for Boltup:
1000 REACTOR PRESSURE (psig)
Water Level Must 500 I Be in Range For Power Operation If Core Is Critical Below 2220 F 0
0 50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (fF)
(reactor vessel beltline downcomer water temperature is measured at recirculation loop suction)
(instrument uncertainties have been included in this figure)
FIGURE 3.2.2.c MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL) (HEATING RATE S 100-FIHR) FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF OPERATION AMENDMENT NO. 149, 164, 183 89
LIMIT FOR POWER OPERATION (CORE CRITICAL)
HEATUP AT UP TO 100°FIHR REACTOR VESSEL BELTLINE REACTOR PRESSURE (psig) DOWNCOMER WATER IN TOP DOME TEMPERATURE (Xf) 0 100 298 100 298 172 300 177 304 182 311 187 319 192 329 197 340 202 354 207 360 212 360 217 360 222 a 406 222 a 429 227 454 232 483 237 515 242 547 247 582 252 622 257 665 262 713 267 767 272 840 278 840 278 895 282 969 287 1050 292 1140 297 (reactor vessel beltline downcomer water temperature Is measured at recirculation loop suction)
("water level must be in range for power operation if core Is critical below 2220 F)
(instrument uncertainties have been Induded in this table)
TABLE 3.2.2.c MINIMUM TEMPERATURE FOR PRESSURIZATION DURING HEATUP (CORE CRITICAL) (HEATING RATE
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF CORE OPERATION AMENDMENT NO. 142 , 164, 183 90
COOLDOWN - CORE CRITICAL 1500 S
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_. a. a ... .. a 0 ---- ---
0 50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE (fF)
(reactor vessel beitline downcomer water temperature is measured at recirculation loop suction)
(instrument uncertainties have been included in this figure)
FIGURE 3.2.2.d MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING CORE OPERATION (CORE CRITICAL) (COOLING RATE-100°FIHR) FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF OPERATION AMENDMENT NO. 142, 164, 183 91
LIMIT FOR POWER OPERATION (CORE CRITICAL)
COOLING AT UP TO 1000 F/HR REACTOR VESSEL BELTLINE REACTOR PRESSURE (psig) DOWNCOMER WATER IN TOP DOME TEMPERATURE (fF) 0 100 205 100 209 102 213 107 218 112 223 117 229 122 235 127 242 132 250 137 254 140 258 142 268 147 278 152 290 157 302 162 316 167 332 172 349 177 360 180 360 200 360 203 a 471 203 a 498 207 532 212 570 217 613 222 659 227 701 232 737 237 777 242 820 247 869 252 922 257 982 262 1047 267 1119 272 1199 277 (reactor vessel beldine downcomer water temperature is measured at recirculation loop suction)
(water level must be In range for power operation If core Is critical below 203 0 F)
(instrument uncertainties have been Induded In this table)
TABLE 3.2.2.d MANIMUM TEMPERATURE FOR PRESSURIZATION DURING COOLDOWN (CORE CRITICAL) (COOLING RATE
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF CORE OPERATION AMENDMENT NO. 142, 1-64, 183 92
LEAK/HYDRO TEST - CORE NOT CRITICAL 1500 * ~~ . . . . C
. . . . I .
. . . . I . .
. . . . I . .
. . . . I . .
. . . . I . . Minimum Temperature
. I .
C1
. . for Boltup:
100 0 F
. . . .. . . C q.... .
. . . C1 . .
1000 .
. . . C8 . .
. . . .. . . C
. . . C. . . C
- C C C C C..................
. I I .
PRESSURE (psig)
. . C . . .
. . Ci . . .
. . C. C 500 . . e . C 0
0 50 100 150 200 250 300 350 400 REACTOR VESSEL BELTLINE DOWNCOMER WATER TEMPERATURE ( 0F)
(reactor vessel beltline downcomer water temperature Is measured at recirculation loop suction)
(instrument uncertainties have been Included In this figure)
FIGURE 3.2.2.e MINIMUM BELTLINE DOWNCOMER WATER TEMPERATURE FOR PRESSURIZATION DURING IN-SERVICE HYDROSTATIC TESTING AND LEAK TESTING (CORE NOT CRITICAL) FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF OPERATION AMENDIMENT NO. 142, 164, 183 93
LIMIT FOR IN-SERVICE TEST (CORE NOT CRITICAL, FUEL IN VESSEL)
REACTOR VESSEL BELTLINE REACTOR PRESSURE (psig) DOWNCOMER WATER IN TOP DOME TEMPERATURE (OF) 0 100 360 100 360 130 688 130 704 135 722 140 742 145 764 150 788 155 815 160 844 165 877 170 913 175 953 180 997 185 1046 190 1100 195 1160 200 (reactor vessel beltline downcomer water temperature Is measured at recirculation loop suction)
(instrument uncertainties have been Included in this table)
TABLE 3.2.2.e MINIMUM TEMPERATURE FOR PRESSURIZATION DURING LEAKIHYDROSTATIC TESTING (CORE NOT CRITICAL)
FOR UP TO 28 EFFECTIVE FULL POWER YEARS OF CORE OPERATION AMENDMENT NO. 442, 164, 183 94
Pages 94a Through 94d Deleted I AMENDMENT NO. l64, 183 94a