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MONTHYEARML0221802012002-08-0505 August 2002
Technical Specification Pages for Amendment 173 Inservice Testing Requirements in Technical Specifications
Project stage: Other
ML0221707692002-08-0505 August 2002
License Amendment 273, Deletes Section 3/4.2.6, Revises Section 4.2.7, Adds New Section 6.17 & Deletes Several Reporting Requirements in Section 6.9.3
Project stage: Approval
2002-08-05
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Category:Technical Specifications
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML23289A0122023-12-0606 December 2023
Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
ML23131A4242023-06-23023 June 2023
Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568
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
ML22033A3102022-03-0404 March 2022
Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements
ML21347A0382022-01-13013 January 2022
Issuance of Amendments to Revise Reactor Coolant Leakage Requirements
NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022
Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
ML21295A7342021-11-15015 November 2021
Issuance of Amendment No. 187 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-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
ML21033A5302021-04-0101 April 2021
Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems
ML21049A0062021-03-16016 March 2021
Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve
ML21077A0142021-03-16016 March 2021
License and Technical Specification Pages for Amendment No. 245, Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve
ML21013A0052021-02-0404 February 2021
Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
ML20332A1152021-01-29029 January 2021
Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components
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
ML19176A0862019-07-30030 July 2019
Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements
ML18344A4522019-01-11011 January 2019
Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks
NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018
Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.
ML18330A0952018-11-30030 November 2018
Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005
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
ML18032A1772018-03-0606 March 2018
Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232)
NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017
Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
ML17324B1782017-12-21021 December 2017
Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203)
ML17152A3202017-06-30030 June 2017
Issuance of Amendments Emergency Plans Emergency Action Level HU1.5
ML17055A4512017-03-0909 March 2017
Issuance of Amendment Partial Length Fuel Rod Burnup
ML16088A0532016-04-19019 April 2016
Issuance of Amendment License Amendment Request for Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
ML15352A1642016-03-17017 March 2016
Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel
NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016
Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual
ML15341A3362016-01-0505 January 2016
Issuance of Amendment Technical Specifications for Safety Limit Minimum Critical Power Ratio
NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015
Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....
ML15317A3072015-11-30030 November 2015
Issuance of Amendment Adoption of Technical Specification Task Force Traveler 425
ML15096A0762015-09-0202 September 2015
Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus
ML15223B2502015-08-14014 August 2015
and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150
ML15161A3802015-07-30030 July 2015
R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409)
ML15167A3152015-07-0808 July 2015
Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators
ML15110A0082015-05-26026 May 2015
Issuance of Amendment Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
ML15075A1592015-03-17017 March 2015
Correction Letter to Amendment No. 217 Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change (Tac No. MF1022)
ML15043A2702015-03-12012 March 2015
Issuance of Amendment Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change
ML14126A0032014-06-30030 June 2014
Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c)
ML14057A5542014-05-29029 May 2014
Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
ML1233803362012-11-21021 November 2012
License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
ML1133000472011-12-22022 December 2011
NMP2 EPU - Operating License and Technical Specification Pages
ML1133000412011-12-22022 December 2011
Cover Letter - Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Extended Power Uprate
ML11208C3952011-07-20020 July 2011
License Amendment Requests Pursuant to 10 CFR 50.90: Revisions to the Technical Specifications Design Features Sections to Reflect Transfer of a Portion of Nine Mile Point Nuclear Station Site Real Property
ML1018803332010-07-26026 July 2010
Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1
ML1008904222010-03-22022 March 2010
License Amendment Request Pursuant to 10 CFR 50.90: Revision to Containment Spray System Nozzle Surveillance Frequency
ML0926406812009-09-18018 September 2009
License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1
2024-09-20
[Table view] |
Text
rII:RGRIPTION PAGE SECTION flFSrCRIPTION PG 80 3.2.0 Reactor Coolant System Surveillance Requirements Limiting Condition for Operation 81 3.2.1 Reactor Vessel Heatup and Cooldown Rates 83 4.2.2 Minimum Reactor Vessel Temperature for 3.2.2 Minimum Reactor Vessel Temperature for Pressurization Pressurization 4.2.3 Coolant Chemistry 96 3.2.3 Coolant Chemistry 99 4.2.4 Coolant Activity 3.2.4 Coolant Activity 101 4.2.5 Leakage Rate 3.2.5 Leakage Rate 105 4.2.6 (Deleted) 3.2.6 (Deleted) 108 4.2.7 Isolation Valves 3.2.7 Isolation Valves 118 4.2.8 Safety Valves 3.2.8 Safety Valves 120 4.2.9 Solenoid-Actuated Pressure Relief Valves 3.2.9 Solenoid-Actuated Pressure Relief Valves 123 3.3.0 Primary Containment Surveillance Requirements Limiting Condition for Operation 4.3.1 Oxygen Concentration 124 3.3.1 Oxygen Concentration 127 4.3.2 Pressure and Suppression Chamber Water 3.3.2 Pressure and Suppression Chamber Water Temperature and Level Temperature and Level 131 4.3.3 Leakage Rate 3.3.3 Leakage Rate AMENDMENT NO. W 173
PAGE SECTION DESCRIPTION 370 6.10 Record Retention 371 6.11 Radiation Protection Program 371 6.12 High Radiation Area 373 6.13 Fire Protection Inspection 373 6.14 Systems Integrity 373 6.15 Iodine Monitoring 373 6.16 10 CFR 50 Appendix J Testing Program Plan 374 6.17 Inservice Testing Program 173 AMENDMENT NO.
(Deleted) 105 AMENDMENT NO. W 173
(Deleted)
AMENDMENT NO. W 173
SURVEILLANCE REQUIREMENT i mriMit-z rOniunITION FOR OPERATION SRELAC EURMN 4.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES 3.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applcability:
Applicability:
Applies to the periodic testing requirement for the Applies to the operating status of the system of reactor coolant system isolation valves.
isolation valves on lines connected to the reactor coolant system.
Obiective:
Objective:
To assure the capability of the reactor coolant system To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear event of a rupture of a line connected to the nuclear steam supply system.
steam supply system.
Specification:
Specification:
The reactor coolant system isolation valves
- a. During power operating conditions whenever the reactor head is on, all reactor coolant system surveillance shall be performed as indicated below.
isolation valves on lines connected to the reactor
- a. At least once per operating cycle the operable coolant system shall be operable except as automatically initiated power-operated isolation specified in "b" below.
valves shall be tested for automatic initiation and closure times.
- b. In the event any isolation valve becomes inoperable the system shall be considered
- b. Additional surveillances shall be performed as operable provided at least one valve in each line required by Specification 6.1 7.
having an inoperable valve is in the mode corresponding to the isolated condition, except as noted in Specification 3.1.1.e.
i', W, 173 108 AMENDMENT NO.
6.9.3 Special Reports Office within the time period specified for each Special reports shall be submitted in accordance with 10 CFR 50.4 Regional pursuant to the requirements of the applicable report. These reports shall be submitted covering the activities identified below reference specification:
4.2.2(b) (12 months).
- a. Reactor Vessel Material Surveillance Specimen Examination, Specification
- b. (Deleted)
- c. (Deleted)
- d. (Deleted)
- e. (Deleted)
- f. (Deleted) months).
- g. Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three (30 days from the end of the affected
- h. Calculate Dose from Liquid Effluent in Excess of Limits, Specification 3.6.1 5.a(2)(b) calendar quarter).
3.6.1 5.b(2)(b) (30 days from the end of
- i. Calculate Air Dose from Noble Gases Effluent in Excess of Limits, Specification the affected calendar quarter).
greater than eight days in Excess of Limits,
- j. Calculate Dose from 1-131, H-3 and Radioactive Particulates with half lives calendar quarter).
Specification 3.6.15.b(3)(b) (30 days from the end of the affected 3.6.15.d (30 days from the end of
- k. Calculated Doses from Uranium Fuel Cycle Source in Excess of Limits, Specification the affected calendar year).
(30 days from the event).
I. Inoperable Gaseous Radwaste Treatment System, Specification 3.6.1 6.b of plant effluents) in an environmental
- m. Environmental Radiological Reports. With the level of radioactivity (as the result over any calendar quarter, in lieu of a sampling medium exceeding the reporting level of Table 6.9.3-1, when averaged (30) days from the end of the calendar quarter Licensee Event Report, prepare and submit to the Commission within thirty define the corrective action to be taken.
a special report identifying the cause(s) for exceeding the limits, and 368 AMENDMENT NO. W, 173
criteria is less than 0.6 La, calculated
- 4. The combined Local Leak Rate Test (Type B & C Tests including airlocks) acceptance is required.
on a minimum pathway basis, at all times when containment integrity specified in the 10 CFR 50 Appendix J Testing The provisions of Specification 4.0.1 do not apply to the test frequencies Program Plan.
6.17 Inservice Testing Program A, B, and C pumps and valves.
This program provides controls for inservice testing of Quality Group performed in accordance with requirements for
- a. Inservice testing of Quality Group A, B, and C pumps and valves shall be 3 components specified in Section Xl of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and to the applicable provisions of 10CFR50.55a; applicable ASME Boiler and Pressure Vessel Code Edition and Addenda, subject testing frequencies for performing inservice
- b. The provisions of Specification 4.0.1 are applicable to the normal and accelerated testing activities; to supersede the requirements of any Technical
- c. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed Specification.
374 AMENDMENT NO 4-1, 173
