Letter Sequence Other |
|---|
|
|
MONTHYEARML0421103812004-07-16016 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
Project stage: Request
ML0434401142005-01-25025 January 2005
Amendment, Intermediate Range Monitor and Control Rod Withdrawal Block Instrumentation
Project stage: Acceptance Review
ML0502603892005-01-25025 January 2005
TS Pages for Nine Mile Point, Unit 1
Project stage: Other
2004-07-16
[Table View] |
|
|---|
Category:Technical Specifications
MONTHYEARML23289A0122023-12-0606 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
ML0919504152009-07-0202 July 2009
License Amendment Request to Remove Position Indication for Relief Valves and Safety Valves from Technical Specifications
ML0905605222009-02-11011 February 2009
Units, 1 & 2, License Amendment Request for Adoption of TSTF-511-A Rev. 0 Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.
2023-08-30
[Table view] |
Text
TABLE 4.6.2a (cont'd)
INSTRUMENTATION THAT INITIATES SCRAM Surveillance Requirement Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration (8) Shutdown Position of None Once during each major None Reactor Mode Switch refueling outage (9) Neutron Flux (a) IRM (i) Upscale Once per shift(f Once per week(9) Once per operating cycle(n) I (ii) Inoperative Once per shift(§) Once per week(9) Once per operating cycle(n) I (b) APRM (i) Upscale None Once per 3 months Once per week(m)
Once per 3 months~n) I (ii) Inoperative None Once per 3 months None (10) Turbine Stop Valve None Once per 3 months Once per operating cycle Closure (11) Generator Load None Once per 3 months Once per 3 months Rejection AMENDMENT NO. 442,453, 186 202
NOTES FOR TABLES 3.6.2a and 4.6.2a (a) May be bypassed when necessary for containment inerting.
(b) May be bypassed in the refuel and shutdown positions of the reactor mode switch with a keylock switch.
(c) May be bypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi, or for the purpose of performing reactor coolant system pressure testing and/or control rod scram time testing with the reactor mode switch in the refuel position.
(d) No more than one of the four IRM inputs to each trip system shall be bypassed.
(e) No more than two C or D level LPRM inputs to an APRM shall be bypassed and only four LPRM inputs to an APRM shall be bypassed in order for the APRM to be considered operable. No more than one of the four APRM inputs to each trip system shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed. A Traversing In-Core Probe (TIP) chamber may be used as a substitute APRM input if the TIP is positioned in close proximity to the failed LPRM it is replacing.
(f) Verify SRM/IRM channels overlap during startup after the mode switch has been placed in startup. Verify IRM/APRM channels overlap at least 1/2 decade during entry into startup from run (normal shutdown) if not performed within the previous 7 days.
(g) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before startup, if not performed within the previous 7 days. Not required to be performed during shutdown until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering startup from run.
(h) Each of the four isolation valves has two limit switches. Each limit switch provides input to one of two instrument channels in a single trip system.
(i) May be bypassed when reactor power level is below 45%.
(j) Trip upon loss of oil pressure to the acceleration relay.
(k) May be bypassed when placing the reactor mode switch In the SHUTDOWN position and all control rods are fully inserted.
(I) Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2a, the primary sensor will be calibrated and tested once per operating cycle.
(m) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when THERMAL POWER 2 25% of RATED THERMAL POWER. Adjust the APRM channel if the difference is greater than +2.0/-1.9% of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 2.1.2a shall not be included in determining the difference.
(n) Neutron detectors are excluded.
AMENDMENT NO. 442,4434,53, 468 186 203
TABLE 3.6.2g INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Limiting Condition for Operation Minimum No. of Operable Instrument Reactor Mode Switch Minimum No. Channels per Position in Which of Tripped or Operable Function Must Be Parameter Operable Trip Systems Trip System (I) Set Point Operable 0.
t3 4..
Co Cl)
(1) Deleted I (2) IRM
- a. Detector not in Startup Position 2 3(b) x x
- b. Inoperative 2 3(b) x x AMENDMENT NO. 442, 186 226
TABLE 3.6.2g (cont'd)
INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Limiting Condition for Operation Minimum No. of Operable Instrument Reactor Mode Switch Minimum No. Channels per Position In Which of Tripped or Operable Function Must Be Parameter Operable Trip Systems Trip System Set Point Operable C
13 0 _ - 0.
oM W-a) uz a)
CO .4-(4) Deleted (5) Refuel Platform and Hoists 2(f) I x (6) Mode Switch in Shutdown I 1 x (7) Mode Switch In Refuel I 1 x (Blocks withdrawal of more than I rod)
(8) Deleted I AMENDMENT NO. 44A 186 228 228
PAGE 229 DELETED I AMENDMENT NO. 442T 186 229
TABLE 4.6.2g INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Requirement Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration (1) Deleted I (2) IRM
- a. Detector not in N/A Once per week(g) N/A Startup Position
- b. Inoperative N/A Once per week(g) N/A C. Downscale N/A Once per week(g) Once per operating cycleU)
- d. Upscale N/A Once per week(g) Once per operating cycle0 )
(3) APF IM
- a. Inoperative None Once per 3 months None
- b. Upscale (Biased by None Once per 3 months Once per 3 monthso)
Recirculation Flow)
- c. Downscale None Once per 3 months Once per 3 monthso)
(4) Deleted AMENDMENT NO. 442, 186 230
TABLE 4.6.2g (cont'd)
INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Requirement Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration (5) Refuel Platform and (see 4.5.2)
Hoists (6) Mode Switch in Once during each major Shutdown refueling outage (7) Mode Switch in Once during each major Refuel (Blocks refueling outage withdrawal of more than 1 rod)
(8) Deleted I AMENDMENT NO. 442, 186 231
NOTES FOR TABLES 3.6.2g and 4.6.2g (a) Deleted (b) No more than one of the four IRM inputs to each instrument channel shall be bypassed. These signals may be bypassed when the APRMs are onscale.
(c) No more than one of the four APRM inputs to each instrument channel shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed. No more than two C or D level LPRM inputs to an APRM shall be bypassed and only four LPRM inputs to only one APRM shall be bypassed in order for the APRM to be considered operable. In the Run mode of operation, bypass of two chambers from one radial core location in any one APRM shall cause that APRM to be considered inoperative. A Travelling In-Core Probe (TIP) chamber may be used as a substitute APRM input if the TIP is positioned in close proximity to the failed LPRM it is replacing. If one APRM in a quadrant is bypassed and meets all requirements for operability with the exception of the requirement of at least one operable chamber at each radial location, it may be returned to service and the other APRM in that quadrant may be removed from service for test and/or calibration only if no control rod is withdrawn during the calibration and/or test.
(d) May be bypassed in the startup and refuel positions of the reactor mode switch when the IRMs are onscale.
(e) Deleted (f) One sensor provides input to each of two instrument channels. Each instrument channel is in a separate trip system.
(g) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before startup, if not performed within the previous 7 days. Not required to be performed during shutdown until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering startup from run.
(h) The actuation of either or both trip systems will result in a rod block.
(i) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the Trip System in the tripped condition, provided at least one other operable channel in the same Trip System is monitoring that Parameter.
(j) Neutron detectors are excluded.
AMENDMENT NO. 44227 186 232
PAGE 233 DELETED I AMENDMENT NO. 442, 186 233
