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MONTHYEARML0203701252002-02-0101 February 2002
Technical Specifications Pages Amendment 264 Revising the TSs and Bases Related to Reactor Coolant Pump Flywheel Inspection Requirements and Reactor Coolant System Structural Integrity
Project stage: Other
ML0133704062002-02-0101 February 2002
Issuance of Amendment 264 Revising the Technical Specifications and Bases Related to Reactor Coolant Pump Flywheel Inspection Requirements and Reactor Coolant System Structural Integrity (Tac No. MB1818)
Project stage: Approval
2002-02-01
[Table View] |
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Category:Technical Specification
MONTHYEARML24030A7522024-01-30030 January 2024
Technical Specification Bases Pages
ML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
ML23013A2242023-01-13013 January 2023
Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure Temperature Limitation Figures
ML22095A1072022-07-11011 July 2022
Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD
ML22096A2212022-04-0606 April 2022
Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ML22032A2702022-01-28028 January 2022
Technical Specification Bases Pages
ML22032A2692022-01-28028 January 2022
Technical Specification Bases Pages
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Request for Enforcement Discretion from Technical Specification 3.5.2 ECCS Subsystems and Technical Specification 3.7.3 Reactor Plant Component Cooling Water System
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Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality .
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Attachment 2: MPS3 Technical Specification Bases Pages
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Attachment 1: MPS2 Technical Specification Bases Pages
ML20252A1912020-09-0404 September 2020
Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections
ML20224A4572020-08-11011 August 2020
Connecticut. Inc. Millstone Power Station Unit 3, Proposed License Amendment Request for a One-Time Extension of the Millstone Unit 3 Steam Generator Inspections
ML20063L8232020-03-0303 March 2020
License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20065K9762020-03-0303 March 2020
License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20063L2872020-02-26026 February 2020
Technical Specification Bases Pages
ML19304A2942019-10-22022 October 2019
Supplement to Proposed License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Componen
ML19109A1002019-04-11011 April 2019
Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.
ML19052A1612019-02-14014 February 2019
Changes to Technical Specification Bases
ML16257A5632016-09-19019 September 2016
Correction Letter to Amendment No. 327 - Technical Specification Changes for Spent Fuel Storage
ML16258A1442016-09-0101 September 2016
Administrative Correction to License Amendment 327, Technical Specification Changes to Spent Fuel Pool Storage
ML16061A0732016-02-23023 February 2016
Changes to Technical Specification Bases
ML16034A3582016-01-26026 January 2016
License Amendment Request, Spent Fuel Pool Heat Load Analysis
ML15342A0282015-12-0101 December 2015
Supplement to License Amendment Request to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML15246A1172015-08-31031 August 2015
Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program
ML15065A3342015-02-26026 February 2015
Changes to Technical Specification Bases
ML14188B1892014-06-30030 June 2014
License Amendment Request to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C.
ML14093A0272014-03-28028 March 2014
License Amendment Request for Administrative Changes and Corrections to the Technical Specifications
ML14093A0262014-03-28028 March 2014
License Amendment Request for Administrative Changes and Corrections to the Technical Specifications
ML14070A3462014-03-0606 March 2014
Changes to Technical Specification Bases
ML13281A8092013-10-0202 October 2013
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink
ML13281A8042013-10-0202 October 2013
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink
ML13198A2712013-06-27027 June 2013
Supplement to License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink.
ML13120A1582013-04-25025 April 2013
License Amendment Request to Revise Technical Specification 6.8.4.F for Peak Calculated Containment Internal Pressure
ML13079A2262013-03-0606 March 2013
Submittal of Changes to Technical Specification Bases
ML12362A0122012-12-17017 December 2012
License Amendment Request to Revise Surveillance Requirement 4.4.3.2 Reactor Coolant System Relief Valves
ML12081A1292012-03-0909 March 2012
Changes to Technical Specification Bases
ML12032A2242012-01-25025 January 2012
License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3
ML11193A2242011-07-0505 July 2011
License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages
ML1023904032010-08-19019 August 2010
Changes to Technical Specification Bases
ML0925806592009-09-0909 September 2009
Changes to Technical Specification Bases
ML0826104492008-09-0808 September 2008
Transmittal of Changes to Technical Specification Bases
ML0723303092007-08-15015 August 2007
Reactor Coolant System Leakage Detection Systems (Lbdcrs 07-MP2-012 and 07-MP3-032)
ML0720003962007-07-13013 July 2007
Attachment 4, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Mark-Up of Associated Technical Specifications Bases Pages
ML0715605312007-05-31031 May 2007
Tech Spec Pages for Amendment 299 Steam Generator Tube Integrity
ML0711002192007-04-12012 April 2007
Changes to Technical Specifications Bases
ML0708807052007-03-28028 March 2007
License Amendment Request (LBDCR 07-MP2-007) Re Containment Spray Nozzle Surveillance
ML0703101462007-01-30030 January 2007
Technical Specification, Pressurizer Water Level Limits
ML0700300722007-01-0202 January 2007
Supplement to Proposed Technical Specification Change (LBDCR 04-MP3-011) Auxiliary Feedwater System Allowed Outage Time
ML0630003212006-10-26026 October 2006
Changes to Technical Specifications Bases
2024-01-30
[Table view]
Category:Amendment
MONTHYEARML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
ML23013A2242023-01-13013 January 2023
Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure Temperature Limitation Figures
ML22095A1072022-07-11011 July 2022
Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD
ML22027A7362022-01-27027 January 2022
Request for Enforcement Discretion from Technical Specification 3.5.2 ECCS Subsystems and Technical Specification 3.7.3 Reactor Plant Component Cooling Water System
ML21294A3382021-10-21021 October 2021
Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality .
ML20252A1912020-09-0404 September 2020
Response to Request for Additional Information Regarding License Amendment Request for a One-Time Deferral of the Millstone Unit 3 Steam Generator Inspections
ML20224A4572020-08-11011 August 2020
Connecticut. Inc. Millstone Power Station Unit 3, Proposed License Amendment Request for a One-Time Extension of the Millstone Unit 3 Steam Generator Inspections
ML20063L8232020-03-0303 March 2020
License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML19304A2942019-10-22022 October 2019
Supplement to Proposed License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Componen
ML16257A5632016-09-19019 September 2016
Correction Letter to Amendment No. 327 - Technical Specification Changes for Spent Fuel Storage
ML15246A1172015-08-31031 August 2015
Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program
ML14093A0272014-03-28028 March 2014
License Amendment Request for Administrative Changes and Corrections to the Technical Specifications
ML14093A0262014-03-28028 March 2014
License Amendment Request for Administrative Changes and Corrections to the Technical Specifications
ML13281A8092013-10-0202 October 2013
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink
ML13281A8042013-10-0202 October 2013
Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink
ML13120A1582013-04-25025 April 2013
License Amendment Request to Revise Technical Specification 6.8.4.F for Peak Calculated Containment Internal Pressure
ML12362A0122012-12-17017 December 2012
License Amendment Request to Revise Surveillance Requirement 4.4.3.2 Reactor Coolant System Relief Valves
ML0715605312007-05-31031 May 2007
Tech Spec Pages for Amendment 299 Steam Generator Tube Integrity
ML0703101462007-01-30030 January 2007
Technical Specification, Pressurizer Water Level Limits
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Technical Specification Bases Pages
ML0506706622005-02-25025 February 2005
Administrative Changes in Technical Specifications
ML0326913862003-09-17017 September 2003
Amended TS Pages Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
ML0302805422003-01-16016 January 2003
Response to a Request for Additional Information, License Basis Document Change Request 2-1-02 Limiting Safety System Settings & Instrumentation
ML0221201682002-07-19019 July 2002
Application for Amendment to NPF-49 to Modify Technical Specification Requirements for Missed Surveillances in Specification 4.0.3 & Modify Associated Technical Specification Bases
ML0212901372002-05-0808 May 2002
Technical Specifications for Amendments Relocating Various Reactor Coolant System Technical Specifications to the Respective Unit'S Technical Requirements Manual
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Corrected TS Pages 3/4 3-39 & 3/4 3-41
ML0203701252002-02-0101 February 2002
Technical Specifications Pages Amendment 264 Revising the TSs and Bases Related to Reactor Coolant Pump Flywheel Inspection Requirements and Reactor Coolant System Structural Integrity
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Technical Specifications Pages for Amendment 263 Changes to TS Definitions for Core Alteration & Refueling Operations
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Issuance of Amendment Elimination of Requirements for Post-Accident Sampling
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TS Pages for Amendment 262 Elimination of Requirements for Post-Accident Sampling
ML0200702602002-01-0404 January 2002
Amendment 261 to TS Pages Emergency Diesel Generator Allowed Outage Time
ML18088A9471976-04-19019 April 1976
Proposed Revisions to Environmental Technical Specifications
ML17037B7791974-02-0707 February 1974
Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ...
2023-06-16
[Table view] |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.2 SAFETY VALVES ............. . . . . . . . . . S....
3/4 4-2 3/4.4.3 RELIEF VALVES ............. . . . . . . . . . S....
3/4 4-3 3/4.4.4 PRESSURIZER .............. . . . . . . . . . S....
3/4 4-4 3/4.4.5 STEAM GENERATORS ....... . . . . . . . . . S....
3/4 4-5 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE . . . . . . . . . S....
3/4 4-8 Leakage Detection Systems . . . . . . . . . . . . 3/4 4-8 Reactor Coolant System Leakage . . . . . . . . . S....
3/4 4-9 3/4.4.7 CHEMISTRY ... ............. . . . . . . . . . S....
3/4 4-10 3/4.4.8 SPECIFIC ACTIVITY .......... . . . . . . . . . S....
3/4 4-13 3/4.4.9 PRESSURE/TEMPERATURE LIMITS S.... . . . . . . . . . 3/4 4-17 Reactor Coolant System .... S.... . . . . . . . . . 3/4 4-17 Pressurizer ......... S. . . . . . . . . . . . 3/4 4-21 Overpressure Protection Systems S.... . . . . . . . . . 3/4 4-21a 3/4.4.10 DELETED . . . . . . . . . . . S.... . . . . . . . . . 3/4 4-22 3/4.4.11 REACTOR COOLANT SYSTEM VENTS . S.... . . . . . . . . . 3/4 4-23 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS . ... S.... . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg Ž 300°F S.... . . . . . . . . . 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg< 300°F S.... . . . . . . . . . 3/4 5-7 3/4 5.4 REFUELING WATER STORAGE TANK S.... . . . . . . . . . 3/4 5-8 3/4 5.5 TRISODIUM PHOSPHATE (TSP) . . S.... . . . . . . . . . 3/4 5-9 MILLSTONE - UNIT 2 0713 VI Amendment No. 00, 7f, J0, 7P, W7, 264
INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION S. .. .. . B 3/4 4-1 3/4.4.2 SAFETY VALVES ........... S. . . .. . B 3/4 4-1 3/4.4.3 RELIEF VALVES ...... ............ S. . . .. . B 3/4 4-2 3/4.4.4 PRESSURIZER ............ S. . . .. . B 3/4 4-2a 3/4.4.5 STEAM GENERATORS .......... S. . . .. . B 3/4 4-2a 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE . . . S. . . .. . B 3/4 4-3 3/4.4.7 CHEMISTRY ............. S. . . .. . B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY .... ........... S. . . .. . B 3/4 4-4 3/4.4.9 PRESSURE/TEMPERATURE LIMITS...... S. . . .. . B 3/4 4-5 3/4.4.10 DELETED . . . . . . . . . . . . . . S. . . .. . B 3/4 4-7 I 3/4.4.11 REACTOR COOLANT SYSTEM VENTS .... S. . . .. . B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5. .1 SAFETY INJECTION TANKS ....... S. . . . . . .. . B 3/4 5-1 3/4.5 .2 and 3/4.5.3 ECCS SUBSYSTEMS ...... S. . . . . . .. . B 3/4 5-1 3/4.5. .4 REFUELING WATER STORAGE TANK (RWST) S. . . . . . .. . B 3/4 5-2 3/4.5. .5 TRISODIUM PHOSPHATE (TSP) ......... S. . . . . . .. . B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6. .1 PRIMARY CONTAINMENT ............. S. . . . . . .. . B 3/4 6-1 3/4.6. .2 DEPRESSURIZATION AND COOLING SYSTEMS S. . . . . . .. . B 3/4 6-3 3/4.6. .3 CONTAINMENT ISOLATION VALVES .... S. . . . . . .. . B 3/4 6-3 3/4.6. .4 COMBUSTIBLE GAS CONTROL .......... S. . . . . . .. . B 3/4 6-4 3/4.6. .5 SECONDARY CONTAINMENT ............ S. . . . . . .. . B 3/4 6-5 MILLSTONE - UNIT 2 XII Amendment No. fg, 99, 72, J90, 7J9, 0712 199, 7J7, 264
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS ....... ..... ........................ ... 6-16 STARTUP REPORTS ............ .. .................... o.6-16 ANNUAL REPORTS ............... ........................ ... 6-17 ANNUAL RADIOLOGICAL REPORTS ..... ..................... ... 6-18 MONTHLY OPERATING REPORT ................................ ... 6-18 CORE OPERATING LIMITS REPORT .... ... ................. .. 6-18 6.9.2 SPECIAL REPORTS ........... ....................... 6-19 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM .... .... .............. 6-22 6.12 HIGH RADIATION AREA ........ ..... ...................... ... 6-22 6.13 SYSTEMS INTEGRITY ........... . ............................ 6-23 6.14 IODINE MONITORING ........ ....... ........................ 6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) .... ................. 6-24 6.16 RADIOACTIVE WASTE TREATMENT .......... .................. ... 6-24 6.17 SECONDARY WATER CHEMISTRY ........ .. .................... ... 6-25 6.18 PASS/SAMPLING AND ANALYSIS OF PLANT EFFLUENTS ... ......... .. 6-25 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM ..... ............ ... 6-26 6.20 RADIOACTIVE EFFLUENT CONTROLS PROGRAM ..... .............. o.6-26 6.21 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............. .. 6-27 6.22 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM ........... ... 6-28 MILLSTONE - UNIT 2 XVII Amendment No. 79, 79, 91, 99, IP, 0714 7 111 79, 0p, J9, Xpl, Ipp, jp, Igo, 264
I I This page intentionally left blank MILLSTONE 0715
- UNIT 2 3/4 4-22 Amendment No. 79, 7A7, 264
ADMINISTRATIVE CONTROLS
- b. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- c. Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.22 Reactor Coolant Pump Flywheel Inspection Report This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius, or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels at least once every 10 years.
MILLSTONE - UNIT 2 6-28 Amendment No. I ,
0716 264
REACTOR COOLANT SYSTEM BASES BASES These methods prevent inadvertent pump injections while allowing manual actions to rapidly restore the makeup capability if conditions require the use of additional charging or HPSI pumps for makeup in the event of a loss of RCS inventory or reduction in shutdown margin.
If a loss of RCS inventory or reduction in shutdown margin event occurs, the appropriate response will be to correct the situation by starting RCS makeup pumps. If the loss of inventory or shutdown margin is significant, this may necessitate the use of additional RCS makeup pumps that are being maintained not capable of injecting into the RCS in accordance with Technical Specification 3.4.9.3. The use of these additional pumps to restore RCS inventory or shutdown margin will require entry into the associated action statement. The action statement requires immediate action to comply with the specification. The restoration of RCS inventory or shutdown margin can be considered to be part of the immediate action to restore the additional RCS makeup pumps to a not capable of injecting status. While recovering RCS inventory or shutdown margin, RCS pressure will be maintained below the Appendix G limits. After RCS inventory or shutdown margin has been restored, the additional pumps should be immediately made not capable of injecting and the action statement exited.
An exception to Technical Specification 3.0.4 is specified for Technical Specification 3.4.9.3 to allow a plant cooldown to MODE 5 if one or both PORVs are inoperable. MODE 5 conditions may be necessary to repair the PORV(s).
3/4.4.10 DELETED I MILLSTONE - UNIT 2 B 3/4 4-7c Amendment No. 779, 779, ?P;, 264 0717
