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MONTHYEARML17250A8702017-09-0707 September 2017 MNGP TSTF-542 Draft Variations Project stage: Draft Other ML17250A8712017-09-0707 September 2017 MNGP TSTF-542 TS Draft Markups Project stage: Draft Other ML17270A0072017-09-29029 September 2017 Summary of Teleconference with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control Project stage: Meeting 2017-09-29
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Category:Technical Specifications
MONTHYEARML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML22357A1002023-03-31031 March 2023 And Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20210M0142020-09-0808 September 2020 And Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML19176A4212019-08-29029 August 2019 Issuance of Amendment No. 203 Adoption of 10 CFR 50.69 ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.12018-11-12012 November 2018 License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1 L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements2018-07-0303 July 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML17346A0852017-12-12012 December 2017 Final Pre-App TS Markups ML17250A8702017-09-0707 September 2017 MNGP TSTF-542 Draft Variations ML17250A8712017-09-0707 September 2017 MNGP TSTF-542 TS Draft Markups ML17172A4312017-06-23023 June 2017 Correction of Amendment No. 194, Issuance of Amendment to Adopt F Tstf 545, Revision 3, Ts Inservice Testing Program Removal & Clarify Sr Usage Rule Application to Section 5.5 Testing ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML15335A4932015-11-20020 November 2015 Technical Requirements Manual, Revision 17 L-MT-15-032, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-09-0202 September 2015 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods L-MT-15-043, Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-05-29029 May 2015 Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15110A2802015-04-15015 April 2015 Operating License and Technical Specifications ML14323A0332015-01-0808 January 2015 Issuance of Amendment No. 187 Regarding Revision to TS 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML14281A3182014-11-25025 November 2014 Issuance of Amendment Regarding Reduction in Steam Dome Pressure Safety Limit L-MT-14-088, Areva Atrium 10XM Fuel Transition License Amendment Request Supplement2014-11-11011 November 2014 Areva Atrium 10XM Fuel Transition License Amendment Request Supplement ML14246A4492014-11-0303 November 2014 Issuance of Amendment to Revise TS 3.5.1, ECCS - Operating L-MT-14-043, License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification2014-05-30030 May 2014 License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification ML14035A2482014-03-28028 March 2014 Issuance of Amendment No. 180 to Implement Maximum Extended Load Line Limit Analysis Plus (Mellla+) Operating Domain ML14072A3902014-03-13013 March 2014 License Amendment Request for Fuel Storage Changes, Supplement to Propose a Spent Fuel Pool Boral Monitoring Program Technical Specification ML13218A0612014-01-28028 January 2014 Issuance of Amendment No. 178 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML13316B2982013-12-0909 December 2013 Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate ML13168A3732013-08-28028 August 2013 Issuance of Amendment No. 175 to Make Minor Corrections and Editorial Changes, Clarify Fuel Storage Capacity, and Remove Obsolete Information ML13168A2192013-08-0909 August 2013 Issuance of Amendment No. 174 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities L-MT-13-055, License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology2013-07-15015 July 2013 License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology ML13189A1942013-06-27027 June 2013 Operating License and Technical Specifications Updating Instructions L-MT-13-030, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs2013-04-19019 April 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs L-MT-12-076, License Amendment Request for Fuel Storage Changes2012-10-30030 October 2012 License Amendment Request for Fuel Storage Changes L-MT-12-071, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2012-09-18018 September 2012 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. L-MT-12-055, License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes2012-08-21021 August 2012 License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes L-MT-12-051, License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer2012-05-25025 May 2012 License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer L-MT-12-028, License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer2012-04-0505 April 2012 License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer ML12083A2522012-03-22022 March 2012 Enclosure 2 - Monticello Nuclear Generating Plant Technical Requirements Manual Revision 10 L-MT-11-022, 002 Monticello - Technical Requirements Manual, Revision 72011-04-27027 April 2011 002 Monticello - Technical Requirements Manual, Revision 7 L-MT-09-047, Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments2009-08-31031 August 2009 Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments L-MT-09-020, License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation2009-05-29029 May 2009 License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation L-MT-09-041, Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function2009-04-0202 April 2009 Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function ML0834406812009-01-30030 January 2009 (Mngp), License Amendment No. 159 Regarding the Power Range Neutron Monitoring System L-MT-08-012, License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-04-22022 April 2008 License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process L-MT-08-013, License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2008-04-0404 April 2008 License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0810101932008-03-31031 March 2008 Monticello, License Amendment Request: Extended Power Uprate ML0802806012008-01-30030 January 2008 Technical Specifications 2024-10-01
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2.2 Variations NSPM is proposing the following variations from the TS changes described in the TSTF-542 or the applicable parts of the NRC staffs safety evaluation. These variations do not affect the applicability of TSTF-542 or the NRC staff's safety evaluation to the proposed license amendment.
- a. The MNGP TS, in some cases, utilizes different numbering and titles than the Standard TS on which TSTF-542 was based. The table below shows the differences between the plant-specific TS numbering and titles and the TSTF-542 numbering and titles. These differences are editorial and do not affect the applicability of TSTF-542 to the MNGP TS.
NUREG-1433 Numbering and Titles MNGP TS Numbering and Titles TS 3.3.7.1 [ Main Control Room TS 3.3.7.1 Control Room Environmental Control Emergency Filtration (MCREC) ] System (CREF) System Instrumentation Instrumentation TS 3.5.2 Reactor Pressure Vessel TS 3.5.2 RPV Water Inventory (RPV) Water Inventory Control.
TS 3.7.4 TS 3.7.5 TS 3.8.8 TS 3.8.10 Control.
ra
[ Main Control Room Environmental Control ft (MCREC) ] System
[ Control Room Air Conditioning (AC) ]
System Inverters - Shutdown Distribution Systems -
TS 3.7.4 TS 3.7.5 None TS 3.8.8 Control Room Emergency Filtration (CREF) System Control Room Ventilation System None Distribution Systems -
Shutdown Shutdown D
- b. TSTF-542 and the associated safety evaluation discuss the applicable regulatory requirements and guidance, including the 10 CFR 50, Appendix A, General Design Criteria (GDC). MNGP was not licensed to the 10 CFR 50, Appendix A, GDC. The MNGP Updated Final Safety Analysis Report (UFSAR), Appendix E contains a comparative evaluation of the design basis of MNGP with respect to the 70 General Design Criteria for Nuclear Power Plant Construction Permits proposed by the Atomic Energy Commission for public comment in July, 1967.
This difference does not alter the conclusion that the proposed change is applicable to MNGP.
- c. The MNGP TS include Amendment No. 189 (Reference 1) for TSTF-523, "Generic Letter 2008-01, Managing Gas Accumulation." The following changes have no effect on the adoption of TSTF-542 and are an acceptable variation:
- SR 3.5.2.2 has been modified from; Verify, for the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve," to; "Verify, for the required ECCS
injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
- SR 3.5.2.3 has been modified to retain the NOTE, "Not required to be met for system vent flow paths opened under administrative control."
- d. NSPM proposes to change the new Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation section to TS 3.3.5.3 for consistency purposes.
This change is editorial and does not affect the applicability of TSTF-542 to the MNGP TS.
- e. The MNGP design does not include a Reactor Vessel Water Level - Low Low Low feature. The corresponding MNGP TS Table 3.3.5-1 functions 1.a and 2.a and TS Table 3.3.7-1 Function 1 occur on a Reactor Vessel Water Level - Low Low signal. Therefore, it is appropriate to revise MNGP TS Table 3.3.5.3.-1 and 3.3.7.1-1to reflect this design difference.
- f. STS Table 3.3.5.1-1, Function 1.d, "Core Spray Pump Discharge Flow - Low (Bypass)" is not included in the MNGP TSs. The function is performed passively via a 2 1/2 inch bypass line with a restricting orifice and locked open manual ra isolation valve. As a result, this function is not being included in TS 3.3.5.3, "Reactor Pressure Vessel (RPV) Water Inventory Control," Table 3.3.5.3-1.
ft
- g. MNGP TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, does not include functions for manual initiation of Core Spray (CS) and Low Pressure Coolant Injection (LPCI). Since the design does not include this feature, proposed Table 3.3.5.3-1 does not include manual initiation functions for CS and LPCI. In addition, TS 3.3.5.3 does not include a surveillance requirement (SR) for a logic system functional test since the SR applies only to the manual initiation function. Therefore, as an alternative to NUREG-1433 SR 3.5.2.8, which Ddemonstrates ECCS injection/spray actuation on a manual initiation signal, NSPM proposes TS 3.5.2, RPV Water Inventory Control, include a new SR (SR 3.5.2.7) to verify the required CS or LPCI subsystem can be manually operated through the manipulation of the subsystem components from the Main Control Room. The manual operation of the LPCI and Core Spray subsystems for the control of reactor cavity or RPV inventory are relatively simple evolutions and involve the manipulation of a small number of components. These subsystem alignments can be performed by licensed operators from the Main Control Room. This alternative is justified by the fact that a draining event is a slow evolution when compared to a design basis loss of coolant accident (LOCA), which is assumed to occur at full power, and thus there is adequate time to take manual actions (i.e., hours versus minutes). Adequate time to take action is assured since the proposed Technical Specification 3.5.2, Condition E, prohibits plant conditions that result in Drain Times that are less than one hour.
Therefore, there is sufficient time for the licensed operators to take manual action to stop an unanticipated draining event, and to manually start an ECCS injection/spray subsystem or the additional method of water injection.
Consequently, there is no need for manual initiation logic to actuate the required
subsystem components. Manual operation of the required subsystem would be an equivalent alternative to system initiation via manual initiation logic.
- h. The MNGP design does not provide the capability to perform channel checks for the following NUREG-1433 functions in proposed Table 3.3.5.3-1, "RPV Water Inventory Control Instrumentation": Function 1.c, "Reactor Steam Dome Pressure
- Low (Injection Permissive), Function 2.c, "Reactor Steam Dome Pressure -
Low (Injection Permissive)," and Function 2.d, "Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)." The current TS do not include channel checks for these functions. Therefore, channel checks are not included for these functions.
- i. MNGP TS 3.8.5, DC Sources - Shutdown, does not include NUREG-1433 Condition A, its associated Required Actions or COMPLETION TIMES. Nor does MNGP TS 3.8.5 contain NUREG-1433 Required Action B.1. Therefore, MNGP TS 3.8.5 Required Action A.1 corresponds with NUREG-1433 Required Action B.2.
The MNGP TS contain the following requirements that differ from the Standard Technical Specifications on which TSTF-542 was based, but are encompassed in the TSTF-542 justification:
j.
ra MNGP TS Table 3.3.5.1, Functions 1.d and 2.d describe the Reactor Steam Dome Pressure Permissive-Low (Pump Permissive) functions for Core Spray ft and LPCI. These channels delay Core Spray and LPCI pump starts on Reactor Vessel Water Level - Low Low until reactor steam dome pressure is below the setpoint. This ensures that, prior to starting low pressure ECCS subsystem pumps, the reactor pressure has fallen to a value below these subsystems' maximum design pressure. This function is bypassed during manual operation; therefore, these Mode 4 and 5 functions and their corresponding surveillance requirements can be removed from the TS because the required ECCS D
subsystem is proposed to be started by manual operation.
- k. MNGP TS Table 3.3.5.1, Functions 1.e and 2.e describe Reactor Steam Dome Pressure Permissive bypass time delays for the Core Spray and LPCI pumps.
The Bypass Timer channels allow the Core Spray and LPCI pumps to start on Reactor Vessel Water Level - Low Low after the bypass timer times out, even if the reactor steam dome pressure is above its permissive setpoint. This ensures that starting the pumps of the low pressure ECCS subsystems will occur on a Reactor Vessel Water Level - Low Low signal after an 18 minute time delay. This time delay is unnecessary for manual operation; therefore, these Mode 4 and 5 functions and their corresponding surveillance requirements can be removed from the TS because the required ECCS subsystem is proposed to be started by manual operation.
- l. MNGP TS Table 3.3.5.1, Function 1.f, describes the Core Spray Pump Start -
Time Delay Relays for the Core Spray pumps. Along with the LPCI Pump Start -
Time Delay Relays (Function 2.f), the purpose of the time delay relays is to stagger the start of the CS and LPCI pumps that are in each of Divisions 1 and 2,
thus limiting the starting transients on the 4.16 kV essential buses. This time delay is unnecessary for manual operation; therefore, these Mode 4 and 5 functions can be removed from the TS because the required ECCS subsystem is proposed to be started by manual operation.
- m. MNGP TS lack a Control Room Air Inlet Radiation - High function (NUREG 1433 Table 3.3.7.1-1 Function 5). Instead, the equivalent function is performed by MNGP Table 3.3.7.1-1 Function 3, Reactor Building Ventilation Exhaust Radiation - High. Like the Control Room Air Inlet Radiation - High function, this function initiates the Control Room Emergency Filtration (CREF) System to isolate the control room envelope from untreated outside air. Therefore, the Reactor Building Ventilation Exhaust Radiation - High function is being revised accordingly.
- n. In the MNGP TS, NUREG -1433 SR 3.5.2.2 and SR 3.5.2.3 are combined into a single SR 3.5.2.2 because the requirements for suppression pool water level and condensate storage tank levels are applicable to both CS and LPCI Systems, i.e.
both CS and LPCI Systems have the capability to draw a suction flow path from the CSTs and the Suppression Pool). .
- o. TSTF-542 inadvertently omitted the corresponding TS Bases markup for the ra deletion of TS 3.3.6.1 Required Action I.2 regarding actions to isolate RHR shutdown cooling. MNGP TS Bases changes are made consistent with this TS change.
ft D
D ra ft