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| number = ML17325A277
| number = ML17325A277
| issue date = 11/28/2017
| issue date = 11/28/2017
| title = Nine Mile Point Nuclear Station, Units 1 - November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation
| title = November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation
| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
| addressee name = Marshall M L
| addressee name = Marshall M
| addressee affiliation = NRC/NRR/DORL/LPLI
| addressee affiliation = NRC/NRR/DORL/LPLI
| docket = 05000220, 05000410
| docket = 05000220, 05000410
| license number = DPR-063, NPF-069
| license number = DPR-063, NPF-069
| contact person = Marhsall M L, NRR/DORL/LPL, 415-2871
| contact person = Marhsall M, NRR/DORL/LPL, 415-2871
| package number = ML17325A307
| package number = ML17325A307
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:Nine Mile Point Nuclear Station, Unit 1 TSTF-542November 28, 2017Pre Submittal Briefing Introduction  
{{#Wiki_filter:Nine Mile Point Nuclear Station, Unit 1 TSTF-542 November 28, 2017 Pre Submittal Briefing
*Purpose TSTF-542, "Reactor Pressure Vessel Water Inventory Control," submittal.Application of TSTF
 
-542 to NMP1 Custom Technical Specifications
Introduction
*Outline Table of contents and formatOperating Conditions and Mode Switch positionsSafety LimitVariations
* Purpose TSTF-542, Reactor Pressure Vessel Water Inventory Control, submittal.
*NMP1 is pre
Application of TSTF-542 to NMP1 Custom Technical Specifications
-GDC plantThe NMP1 current licensing basis incorporates the proposed GDC that are equivalent to the 10 CFR Part 50, Appendix A, GDCs 13, 14, 30 and 33.Criterion 13  
* Outline Table of contents and format Operating Conditions and Mode Switch positions Safety Limit Variations
-Instrumentation and ControlCriterion 14  
* NMP1 is pre-GDC plant The NMP1 current licensing basis incorporates the proposed GDC that are equivalent to the 10 CFR Part 50, Appendix A, GDCs 13, 14, 30 and 33.
-Reactor Coolant Pressure BoundaryCriterion 30  
Criterion 13 - Instrumentation and Control Criterion 14 - Reactor Coolant Pressure Boundary Criterion 30 - Quality of Reactor Coolant Pressure Boundary Criterion 33- Reactor Coolant Makeup 1    NMP1 TSTF-542 Variations
-Quality of Reactor Coolant Pressure BoundaryCriterion 33
 
-Reactor Coolant MakeupNMP1 TSTF-542 Variations 1
NMP1 TS Format 2 NMP1 TSTF-542 Variations
NMP1 TS FormatNMP1 TSTF-542 Variations 2
 
NMP1 Operating Conditions and ModesNMP1 TSTF-542 Variations 3STS ModeNMP1 TS Reactor Operating Condition 1 -Power OperationPower Operating Condition 2 -Startup 3 -Hot Shutdown (>200 F)Shutdown Condition  
NMP1 Operating Conditions and Modes STS Mode                    NMP1 TS Reactor Operating Condition 1 - Power Operation Power Operating Condition 2 - Startup 3 - Hot Shutdown (>200°F)                 Shutdown Condition - Hot (>212°F) 4 - Cold Shutdown (200°F)               Shutdown Condition - Cold (212°F)
-Hot (>212 F)4 - F)Shutdown Condition  
Refueling Condition 5 - Refueling Major Maintenance Condition (defueled)
- F)5 -RefuelingRefueling ConditionMajor Maintenance Condition (defueled)NMP1 TS Reactor Operating ConditionNMP1 Reactor Mode Switch PositionPower Operating ConditionRun StartupShutdown Condition  
NMP1 TS Reactor Operating Condition      NMP1 Reactor Mode Switch Position Run Power Operating Condition Startup Shutdown Condition - Hot (>212°F)         Shutdown Shutdown Condition - Cold (212°F)       Shutdown or Refuel Refueling Condition                      Refuel Major Maintenance Condition (defueled) 3      NMP1 TSTF-542 Variations
-Hot (>212 F)ShutdownShutdown Condition  
 
- F)Shutdown or RefuelRefueling ConditionRefuelMajor Maintenance Condition (defueled)
NMP1 SL 2.1.1.d and 2.1.1.e
NMP1 SL 2.1.1.d and 2.1.1.e
*The NMP1 TS Safety Limit for RPV water level is to keep water above  
* The NMP1 TS Safety Limit for RPV water level is to keep water above -10 inches indicated scale (74 inches above the TAF).
-10 inches indicated scale (74 inches above the TAF).d. Whenever the reactor is in the shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be more than 6 feet, 3 inches (-10 inches indicator scale) below minimum normal water level (Elevation 302'9") except as specified in "e" below.e. For the purpose of performing major maintenance (not to exceed 12 weeks in duration) on the reactor vessel; the reactor water level may be lowered 9' below the minimum normal water level (Elevation 302'9"). Whenever the reactor water level is to be lowered below the low
: d. Whenever the reactor is in the shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be more than 6 feet, 3 inches (-10 inches indicator scale) below minimum normal water level (Elevation 302'9") except as specified in "e" below.
-low-low level setpoint redundant instrumentation will be provided to monitor the reactor water level.NMP1 TSTF-542 Variations 4
: e. For the purpose of performing major maintenance (not to exceed 12 weeks in duration) on the reactor vessel; the reactor water level may be lowered 9 below the minimum normal water level (Elevation 302'9"). Whenever the reactor water level is to be lowered below the low-low-low level setpoint redundant instrumentation will be provided to monitor the reactor water level.
NMP1 ECCS Systems  
4    NMP1 TSTF-542 Variations
*The NMP1 design includes a Core Spray System to ensure adequate core cooling.
 
*This water injection system is a low pressure system and requires the Automatic Depressurization System (ADS) to lower reactor vessel pressure to allow water injection.
NMP1 ECCS Systems
*As described in the NMP1 Updated Final Safety Analysis Report (UFSAR), Section VII, the ADS and Core Spray systems are the engineered safety features (ESF) to either prevent or mitigate the consequences of major accidents.
* The NMP1 design includes a Core Spray System to ensure adequate core cooling.
*The ADS and Core Spray systems are considered the ECCS systems at NMP1.NMP1 TSTF-542 Variations 5
* This water injection system is a low pressure system and requires the Automatic Depressurization System (ADS) to lower reactor vessel pressure to allow water injection.
LCO VariationsNUREG-1433, BWR/4 ISTSModified for TSTF
* As described in the NMP1 Updated Final Safety Analysis Report (UFSAR), Section VII, the ADS and Core Spray systems are the engineered safety features (ESF) to either prevent or mitigate the consequences of major accidents.
-542NMP1 CTS equivalent3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation3.6.2/4.6.2, Protective Instrumentation (section 2.2.4 and 2.2.5 below)Table 3.6.2d/4.6.2d Instrumentation That Initiates Core SprayTable 3.6.2f/4.6.2f Instrumentation that Initiates Auto Depressurization3.3.5.2 RPV WIC Instrumentation (added by TSTF-542)3.6.2/4.6.2 Protective Instrumentation (section 2.2.5 below)Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System and Containment Isolation (Revised)Table 3.6.2m/4.6.2m RPV WIC Instrumentation (New table added to NMP1 CTS for TSTF
* The ADS and Core Spray systems are considered the ECCS systems at NMP1.
-542)3.3.5.3 RCIC system Instrumentation (Renumbered from 3.3.5.2)3.6.2/4.6.2 Protective Instrumentation (section 2.2.6 below)
NMP1 TSTF-542 Variations
Table 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.3.3.6.1, Primary Containment Isolation Instrumentation3.6.2/4.6.2, Protective Instrumentation (section 2.2.7 below)
 
Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System or Containment IsolationTable 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.NMP1 TSTF-542 Variations 6
LCO Variations NUREG-1433, BWR/4 ISTS                          NMP1 CTS equivalent Modified for TSTF-542 3.3.5.1, Emergency Core Cooling System (ECCS) 3.6.2/4.6.2, Protective Instrumentation (section Instrumentation                              2.2.4 and 2.2.5 below)
LCO Variations3.3.6.2, Secondary Containment Isolation3.6.2/4.6.2, Protective Instrumentation Table 3.6.2j/4.6.2j, Emergency Ventilation Initiation3.4.2 Reactor Building Integrity  
* Table 3.6.2d/4.6.2d Instrumentation That Initiates Core Spray
-Isolation Valves(section 2.2.8 below)3.3.7.1, [Main Control Room Environmental Control (MCREC)] System Instrumentation3.4.5, Control Room Air Treatment System 3.6.2/4.6.2, Protective Instrumentation Table 3.6.2l/4.6.2l, Control Room Air Treatment System Initiation(section 2.2.9 below)3.5.2, ECCS Shutdown3.1.4, Core Spray System 3.1.5, Solenoid
* Table 3.6.2f/4.6.2f Instrumentation that Initiates Auto Depressurization 3.3.5.2 RPV WIC Instrumentation (added by     3.6.2/4.6.2 Protective Instrumentation (section TSTF-542)                                    2.2.5 below)
-Actuated Pressure Relief Valves (Automatic Depressurization System). There are no changes to section 3.1.5.(section 2.2.3 below)3.6.1.3, Primary Containment Isolation Valves (PCIVs)3.2.7, Reactor Coolant System Isolation Valves3.3.4, Primary Containment Isolation Valves (section 2.2.10 below)3.6.4.1, [Secondary] Containment3.4.0, Reactor Building 3.4.1, Leakage Rate 3.4.3, Access Control (section 2.2.11 below)3.6.4.2, Secondary Containment Isolation Valves (SCIVs)3.4.2, Reactor Building Integrity  
* Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System and Containment Isolation (Revised)
-Isolation Valves (section 2.2.12 below)3.6.4.3, Standby Gas Treatment (SGT) System3.4.4, Emergency Ventilation System (section 2.2.13 below)NMP1 TSTF-542 Variations 7
* Table 3.6.2m/4.6.2m RPV WIC Instrumentation (New table added to NMP1 CTS for TSTF-542) 3.3.5.3 RCIC system Instrumentation           3.6.2/4.6.2 Protective Instrumentation (section (Renumbered from 3.3.5.2)                    2.2.6 below)
LCO Variations3.7.4, [Main Control Room Environmental Control (MCREC)] System3.4.5, Control Room Air Treatment System (section 2.2.14 below)3.7.5, [Control Room Air Conditioning (AC)]
* Table 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.
SystemNMP1 does not have an equivalent standalone TS that requires changes described in the traveler.(section 2.2.15 below)3.8.2, AC Sources  
3.3.6.1, Primary Containment Isolation       3.6.2/4.6.2, Protective Instrumentation (section Instrumentation                              2.2.7 below)
-ShutdownThe equivalent NMP1 TS do not have OPDRV requirements in these sections and are not included.3.8.5, DC Sources  
* Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System or Containment Isolation
-Shutdown3.8.8, Inverters  
* Table 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.
-Shutdown3.8.10, Distribution Systems
6 NMP1 TSTF-542 Variations
-ShutdownNMP1 TSTF-542 Variations 8
 
Revised Core Spray LCONMP1 TSTF-542 Variations 9
LCO Variations 3.3.6.2, Secondary Containment Isolation        3.6.2/4.6.2, Protective Instrumentation
New LCOs -RPV WICNMP1 TSTF-542 Variations 10    LIMITING CONDITION FOR OPERATION
* Table 3.6.2j/4.6.2j, Emergency Ventilation Initiation 3.4.2 Reactor Building Integrity - Isolation Valves (section 2.2.8 below) 3.3.7.1, [Main Control Room Environmental       3.4.5, Control Room Air Treatment System Control (MCREC)] System Instrumentation        3.6.2/4.6.2, Protective Instrumentation
* Table 3.6.2l/4.6.2l, Control Room Air Treatment System Initiation (section 2.2.9 below) 3.5.2, ECCS Shutdown                            3.1.4, Core Spray System 3.1.5, Solenoid-Actuated Pressure Relief Valves (Automatic Depressurization System). There are no changes to section 3.1.5.
(section 2.2.3 below) 3.6.1.3, Primary Containment Isolation Valves   3.2.7, Reactor Coolant System Isolation Valves (PCIVs)                                        3.3.4, Primary Containment Isolation Valves (section 2.2.10 below) 3.6.4.1, [Secondary] Containment                3.4.0, Reactor Building 3.4.1, Leakage Rate 3.4.3, Access Control (section 2.2.11 below) 3.6.4.2, Secondary Containment Isolation Valves 3.4.2, Reactor Building Integrity - Isolation (SCIVs)                                        Valves (section 2.2.12 below) 3.6.4.3, Standby Gas Treatment (SGT) System    3.4.4, Emergency Ventilation System (section 2.2.13 below) 7 NMP1 TSTF-542 Variations
 
LCO Variations 3.7.4, [Main Control Room Environmental     3.4.5, Control Room Air Treatment System Control (MCREC)] System                    (section 2.2.14 below) 3.7.5, [Control Room Air Conditioning (AC)] NMP1 does not have an equivalent standalone System                                      TS that requires changes described in the traveler.
(section 2.2.15 below) 3.8.2, AC Sources - Shutdown                The equivalent NMP1 TS do not have OPDRV 3.8.5, DC Sources - Shutdown                requirements in these sections and are not 3.8.8, Inverters - Shutdown                included.
3.8.10, Distribution Systems- Shutdown 8 NMP1 TSTF-542 Variations


====3.1.9 Reactor====
Revised Core Spray LCO 9 NMP1 TSTF-542 Variations
Pressure Vessel (RPV) Water Inventory Control  Applicability
:  Applies to the operating status of the core spray systems and Reactor Water Inventory Control when the reactor coolant temperature is less than or equal to 212 F. Objective:  To assure the RPV water inventory is maintained above -10 inches indicator scale.
Specification
:  a. Whenever irradiated fuel is in the reactor vessel and the reactor coolant temperature is less than or equal to 212F, DRAIN TIME of RPV water inventory to
-10 inches indicator scale shall be  36 hours and one core spray subsystem shall be operable except as specified in Specifications b through f below. b. If the required core spray subsystem becomes inoperable, that sub system shall be considered operable provided that the component is returned to an operable condition within 4 hours. c. If Specification s a and b are not met, then immediately initiate action to establish a method of water injection capable of operating without offsite electrical power
. SURVEILLANCE REQUIREMENT


====4.1.9 Reactor====
New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION                                    SURVEILLANCE REQUIREMENT 3.1.9  Reactor Pressure Vessel (RPV) Water Inventory            4.1.9 Reactor Pressure Vessel (RPV) Water Inventory Control                                                         Control Applicability:                                                  Applicability Applies to the operating status of the core spray              Applies to the periodic testing requirements for the systems and Reactor Water Inventory Control when                core spray system and RPV water inventory.
Pressure Vessel (RPV) Water Inventory Control   Applicability Applies to the periodic testing requirements for the core spray system and RPV water inventory
the reactor coolant temperature is less than or equal to 212°F.                                                         Objective:
. Objectiv e:   To verify the operability of the core spray system and RPV water inventory
Objective:                                                     To verify the operability of the core spray system and RPV water inventory.
.     Specification
To assure the RPV water inventory is maintained above -10 inches indicator scale.
:   a. Verify DRAIN TIME  36 hours in accordance with the Surveillance Frequency Control Program. b. Verify, for a required core spray subsystem, the downcomers in the suppression chamber have greater than or equal to three and one half foot of submergence or the condensate storage tank inventory is not less than 300,000 gallons, in accordance with the Surveillance Frequency Control Program
Specification:                                                  Specification:
. c. Verify for the required core spray subsystem, each manual power operated and automatic valve in the flow path, that is not locked, sealed or otherwise secured in position, is in the correct position, in accordance with the Surveillance Frequency Control Program.
: a. Whenever irradiated fuel is in the reactor vessel          a. Verify DRAIN TIME  36 hours in accordance and the reactor coolant temperature is less than or            with the Surveillance Frequency Control equal to 212°F, DRAIN TIME of RPV water                        Program.
inventory to -10 inches indicator scale shall be 36 hours and one core spray subsystem shall be            b. Verify, for a required core spray subsystem, the operable except as specified in Specifications b                downcomers in the suppression chamber have through f below.                                                greater than or equal to three and one half foot of submergence or the condensate storage
: b. If the required core spray subsystem becomes                    tank inventory is not less than 300,000 gallons, inoperable, that sub system shall be considered                in accordance with the Surveillance Frequency operable provided that the component is returned                Control Program.
to an operable condition within 4 hours.
: c. Verify for the required core spray subsystem,
: c. If Specifications a and b are not met, then                    each manual power operated and automatic immediately initiate action to establish a method of            valve in the flow path, that is not locked, sealed water injection capable of operating without offsite            or otherwise secured in position, is in the electrical power.                                              correct position, in accordance with the Surveillance Frequency Control Program.
10      NMP1 TSTF-542 Variations


New LCOs -RPV WICNMP1 TSTF-542 Variations 11  LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT
New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION                             SURVEILLANCE REQUIREMENT
: d. If DRAIN TIME
: d. If DRAIN TIME < 36 hours and  8 hours, within 4           d. Verify each valve credited for automatically hours perform the following actions:                         isolating a penetration flow path actuates to the isolation position on an actual or simulated (1) Verify secondary containment boundary is               isolation signal, in accordance with the capable of being established in less than the           Surveillance Frequency Control Program.
< 36 hours and  8 hours, within 4 hours perform the following actions:
DRAIN TIME.
  (1) Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.
AND                                                      e. Verify the required core spray subsystem actuates (2) Verify each secondary containment penetration           on a manual initiation signal, in accordance with flow path is capable of being isolated in less than     the Surveillance Frequency Control Program.
AN D (2) Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME,   AND (3) Verify one RBEVS is capable of being placed in operation in less than the DRAIN TIME.
the DRAIN TIME,                                         Vessel spray may be excluded.
AND (3) Verify one RBEVS is capable of being placed in operation in less than the DRAIN TIME.
: e. If Drain Time < 8 hours, immediately perform the following actions:
: e. If Drain Time < 8 hours, immediately perform the following actions:
  (1) Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level >  
(1) Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > -10 inches indicator scale for  36 hours.
-10 inches indicat or scale for  36 hours. AND (2) Initiate action to establish secondary containment boundary,   AND (3) Initiate action to isolate each secondary containment penetration low path or verify it can be manually isolated from the control room.
AND (2) Initiate action to establish secondary containment boundary, AND (3) Initiate action to isolate each secondary containment penetration low path or verify it can be manually isolated from the control room.
AND (4) Initiate action to verify one RBEVS is capable of being placed in operation.
AND (4) Initiate action to verify one RBEVS is capable of being placed in operation.
: d. Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal, in accordance with the Surveillance Frequency Control Program.
11 NMP1 TSTF-542 Variations
: e. Verify the required core spray subsystem actuates on a manual initiation signal, in accordance with the Surveillance Frequency Control Program
 
. Vessel spray may be excluded.
New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION                  SURVEILLANCE REQUIREMENT
: f. Specifications d and e not met, or DRAIN TIME is
          < 1 hour, immediately initiate action to restore DRAIN TIME to  36 hours.
12 NMP1 TSTF-542 Variations
 
Revision to Existing Instrumentation Tables 13  NMP1 TSTF-542 Variations


New LCOs -RPV WICNMP1 TSTF-542 Variations 12    LIMITING CONDITION FOR OPERATION
Revision to Existing Instrumentation Tables 14 NMP1 TSTF-542 Variations
: f. Specifications d and e not met, or DRAIN TIME is < 1 hour, immediately initiate action to restore DRAIN TIME to  36 hours.      SURVEILLANCE REQUIREMENT


Revision to Existing Instrumentation TablesNMP1 TSTF-542 Variations 13 Revision to Existing Instrumentation TablesNMP1 TSTF-542 Variations 14 New LCOs -RPV WIC InstrumentationNMP1 TSTF-542 Variations 15 New LCOs -RPV WIC InstrumentationNMP1 TSTF-542 Variations 16TABLE 3.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTAT ION  Limiting Condition for Operation Parameter  Minimum No. of Tripped or Operable Trip Systems Minimum No. of Operable Instrument Channels per Operable        Trip System Set Point Reactor Mode Switch Position in Which Function Must Be Operable  Shutdown Refuel Startup Run   PRIMARY COOLANT ISOLATION   (1) Low-Low Reactor Water Level (a) Cleanup 2 2(f) (Indicator Scale)
New LCOs - RPV WIC Instrumentation 15 NMP1 TSTF-542 Variations
(a) (a)             (b) Shutdown Cooling 2(e) 2 (e)(f) (Indicator Scale)
 
(a) (a)           (2) Manual 2 1 --- (a) (a)
New LCOs - RPV WIC Instrumentation TABLE 3.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION 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 Shutdown   Refuel   Startup   Run PRIMARY COOLANT ISOLATION (1)   Low-Low Reactor Water Level (a) Cleanup                         2                   2(f)                       5 inches      (a)       (a)
New LCOs -RPV WIC InstrumentationNMP1 TSTF-542 Variations 17NOTES FOR TABLES 3.6.2m and 4.6.2m (a) The Parameters in this table are only applicable in the Shutdown Condition  
(Indicator Scale)
- Cold and Refuel. See Table 3.6.2 b or Table 3.6.2d for Parameter applicab i lity in the Shutdown Condition  
(b) Shutdown Cooling               2(e)                 2(e)(f)                     5 inches      (a)       (a)
- Hot. (b) May be bypassed when necessary for performing major maintenance as specified in Specification 2.1.1.e.
(Indicator Scale)
  (c) The instrumentation that initiates the Core Spray System is not required to be operable, if there is no fuel in the reactor vessel.
(2)   Manual                             2                     1                           ---         (a)       (a) 16      NMP1 TSTF-542 Variations
  (d) A channel may be placed in an inoperable status for up to 6 hours for required surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that parameter.
 
New LCOs - RPV WIC Instrumentation NOTES FOR TABLES 3.6.2m and 4.6.2m (a)   The Parameters in this table are only applicable in the Shutdown Condition - Cold and Refuel. See Table 3.6.2b or Table 3.6.2d for Parameter applicability in the Shutdown Condition - Hot.
(b)   May be bypassed when necessary for performing major maintenance as specified in Specification 2.1.1.e.
(c)   The instrumentation that initiates the Core Spray System is not required to be operable, if there is no fuel in the reactor vessel.
(d)   A channel may be placed in an inoperable status for up to 6 hours for required surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that parameter.
With the number of Operable channels less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement:
With the number of Operable channels less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement:
: 1. With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours or take the ACTION required by Specification 3.6.2a for that Parameter.
: 1.     With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours or take the ACTION required by Specification 3.6.2a for that Parameter.
: 2. With more than one channel inoperable, take the ACTION required by Specification 3.6.2a for that Parameter.   (e) In the cold shutdown and refueling conditions, only one Operable Trip System is required provided shutdown cooling system integrity is maintained. With one of the two required Operable Channels in the required Trip System not operable, place the inoperable channel in the tripped condition within 12 hours. Otherwise, either:
: 2.     With more than one channel inoperable, take the ACTION required by Specification 3.6.2a for that Parameter.
(e)   In the cold shutdown and refueling conditions, only one Operable Trip System is required provided shutdown cooling system integrity is maintained. With one of the two required Operable Channels in the required Trip System not operable, place the inoperable channel in the tripped condition within 12 hours. Otherwise, either:
: 1. Immediately initiate action to restore the channel to operable status.
: 1. Immediately initiate action to restore the channel to operable status.
or 2. Immediately initiate action to isolate the shutdown cooling system.  
or
: 2. Immediately initiate action to isolate the shutdown cooling system.
17      NMP1 TSTF-542 Variations


New LCOs -RPV WIC InstrumentationNMP1 TSTF-542 Variations 18NOTES FOR TABLES 3.6.2m and 4.6.2m (f) A channel may be placed in an inoperable status for up to 6 hours for required surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that Parameter.
New LCOs - RPV WIC Instrumentation NOTES FOR TABLES 3.6.2m and 4.6.2m (f)   A channel may be placed in an inoperable status for up to 6 hours for required surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that Parameter.
With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for one trip system, either
With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for one trip system, either
: 1. Place the inoperable channel(s) in the tripped condition within
: 1.     Place the inoperable channel(s) in the tripped condition within
: a. 12 hours for Parameters common to SCRAM Instrumentation, and
: a.       12 hours for Parameters common to SCRAM Instrumentation, and
: b. 24 hours for Parameters not common to SCRAM Instrumentation.
: b.       24 hours for Parameters not common to SCRAM Instrumentation.
or 2. Take the ACTION required by Specification 3.6.2a for that Parameter.
or
With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for both trip systems,   1. Place the inoperable channel(s) in one trip system in the tripped condition within one hour. and 2. a. Place the inoperable channel(s) in the remaining trip system in the tripped condition within (1) 12 hours for Parameters common to SCRAM Instrumentation, and (2) 24 hours for Parameters not common to SCRAM Instrumentation.
: 2.     Take the ACTION required by Specification 3.6.2a for that Parameter.
or   b. take the ACTION required by Specification 3.6.2a for that Parameter.
With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for both trip systems,
  (g) The trip circuit will be calibrated and tested in accordance with the Surveillance Frequency Control Program, the primary sensor   will be calibrated and tested in accordance with the Surveillance Frequency Control Program.
: 1.     Place the inoperable channel(s) in one trip system in the tripped condition within one hour.
Note 1: Surveillance intervals are specified in the Surveillance Frequency Control Program unless otherwise noted in Table 4.6.2m.
and
New RPV WIC Instrumentation SRsNMP1 TSTF-542 Variations 19  Parameter PRIMARY COOLANT ISOLATION (Cleanup and Shutdown Cooling) (1) Low-Low Reactor Water Level  (2) Manual      Sensor Check Note 1   ---    Instrument Channel Test Note 1 (g)   Note 1    Instrument Chann el  Calibration Note 1 (g)    ---
: 2.     a.       Place the inoperable channel(s) in the remaining trip system in the tripped condition within (1)     12 hours for Parameters common to SCRAM Instrumentation, and (2)     24 hours for Parameters not common to SCRAM Instrumentation.
or
: b.       take the ACTION required by Specification 3.6.2a for that Parameter.
(g)   The trip circuit will be calibrated and tested in accordance with the Surveillance Frequency Control Program, the primary sensor will be calibrated and tested in accordance with the Surveillance Frequency Control Program.
Note 1: Surveillance intervals are specified in the Surveillance Frequency Control Program unless otherwise noted in Table 4.6.2m.
18      NMP1 TSTF-542 Variations
 
New RPV WIC Instrumentation SRs Instrument Instrument    Channel Parameter                 Sensor Check Channel Test Calibration PRIMARY COOLANT ISOLATION (Cleanup and Shutdown Cooling)
(1)   Low-Low Reactor Water         Note 1       Note 1(g)   Note 1(g)
Level (2)    Manual                          ---         Note 1        ---
19      NMP1 TSTF-542 Variations
 
Conclusion
Conclusion
*The variations proposed are consistent with TSTF-542.*Questions?NMP1 TSTF-542 Variations 20}}
* The variations proposed are consistent with TSTF-542.
* Questions?
20 NMP1 TSTF-542 Variations}}

Latest revision as of 05:54, 29 October 2019

November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation
ML17325A277
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Text

Nine Mile Point Nuclear Station, Unit 1 TSTF-542 November 28, 2017 Pre Submittal Briefing

Introduction

Application of TSTF-542 to NMP1 Custom Technical Specifications

  • Outline Table of contents and format Operating Conditions and Mode Switch positions Safety Limit Variations

Criterion 13 - Instrumentation and Control Criterion 14 - Reactor Coolant Pressure Boundary Criterion 30 - Quality of Reactor Coolant Pressure Boundary Criterion 33- Reactor Coolant Makeup 1 NMP1 TSTF-542 Variations

NMP1 TS Format 2 NMP1 TSTF-542 Variations

NMP1 Operating Conditions and Modes STS Mode NMP1 TS Reactor Operating Condition 1 - Power Operation Power Operating Condition 2 - Startup 3 - Hot Shutdown (>200°F) Shutdown Condition - Hot (>212°F) 4 - Cold Shutdown (200°F) Shutdown Condition - Cold (212°F)

Refueling Condition 5 - Refueling Major Maintenance Condition (defueled)

NMP1 TS Reactor Operating Condition NMP1 Reactor Mode Switch Position Run Power Operating Condition Startup Shutdown Condition - Hot (>212°F) Shutdown Shutdown Condition - Cold (212°F) Shutdown or Refuel Refueling Condition Refuel Major Maintenance Condition (defueled) 3 NMP1 TSTF-542 Variations

NMP1 SL 2.1.1.d and 2.1.1.e

  • The NMP1 TS Safety Limit for RPV water level is to keep water above -10 inches indicated scale (74 inches above the TAF).
d. Whenever the reactor is in the shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be more than 6 feet, 3 inches (-10 inches indicator scale) below minimum normal water level (Elevation 302'9") except as specified in "e" below.
e. For the purpose of performing major maintenance (not to exceed 12 weeks in duration) on the reactor vessel; the reactor water level may be lowered 9 below the minimum normal water level (Elevation 302'9"). Whenever the reactor water level is to be lowered below the low-low-low level setpoint redundant instrumentation will be provided to monitor the reactor water level.

4 NMP1 TSTF-542 Variations

NMP1 ECCS Systems

  • The NMP1 design includes a Core Spray System to ensure adequate core cooling.

5 NMP1 TSTF-542 Variations

LCO Variations NUREG-1433, BWR/4 ISTS NMP1 CTS equivalent Modified for TSTF-542 3.3.5.1, Emergency Core Cooling System (ECCS) 3.6.2/4.6.2, Protective Instrumentation (section Instrumentation 2.2.4 and 2.2.5 below)

  • Table 3.6.2d/4.6.2d Instrumentation That Initiates Core Spray
  • Table 3.6.2f/4.6.2f Instrumentation that Initiates Auto Depressurization 3.3.5.2 RPV WIC Instrumentation (added by 3.6.2/4.6.2 Protective Instrumentation (section TSTF-542) 2.2.5 below)
  • Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System and Containment Isolation (Revised)
  • Table 3.6.2m/4.6.2m RPV WIC Instrumentation (New table added to NMP1 CTS for TSTF-542) 3.3.5.3 RCIC system Instrumentation 3.6.2/4.6.2 Protective Instrumentation (section (Renumbered from 3.3.5.2) 2.2.6 below)
  • Table 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.

3.3.6.1, Primary Containment Isolation 3.6.2/4.6.2, Protective Instrumentation (section Instrumentation 2.2.7 below)

  • Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System or Containment Isolation
  • Table 3.6.2c/4.6.2c Instrumentation That Initiates or Isolates Emergency Cooling.

6 NMP1 TSTF-542 Variations

LCO Variations 3.3.6.2, Secondary Containment Isolation 3.6.2/4.6.2, Protective Instrumentation

  • Table 3.6.2j/4.6.2j, Emergency Ventilation Initiation 3.4.2 Reactor Building Integrity - Isolation Valves (section 2.2.8 below) 3.3.7.1, [Main Control Room Environmental 3.4.5, Control Room Air Treatment System Control (MCREC)] System Instrumentation 3.6.2/4.6.2, Protective Instrumentation
  • Table 3.6.2l/4.6.2l, Control Room Air Treatment System Initiation (section 2.2.9 below) 3.5.2, ECCS Shutdown 3.1.4, Core Spray System 3.1.5, Solenoid-Actuated Pressure Relief Valves (Automatic Depressurization System). There are no changes to section 3.1.5.

(section 2.2.3 below) 3.6.1.3, Primary Containment Isolation Valves 3.2.7, Reactor Coolant System Isolation Valves (PCIVs) 3.3.4, Primary Containment Isolation Valves (section 2.2.10 below) 3.6.4.1, [Secondary] Containment 3.4.0, Reactor Building 3.4.1, Leakage Rate 3.4.3, Access Control (section 2.2.11 below) 3.6.4.2, Secondary Containment Isolation Valves 3.4.2, Reactor Building Integrity - Isolation (SCIVs) Valves (section 2.2.12 below) 3.6.4.3, Standby Gas Treatment (SGT) System 3.4.4, Emergency Ventilation System (section 2.2.13 below) 7 NMP1 TSTF-542 Variations

LCO Variations 3.7.4, [Main Control Room Environmental 3.4.5, Control Room Air Treatment System Control (MCREC)] System (section 2.2.14 below) 3.7.5, [Control Room Air Conditioning (AC)] NMP1 does not have an equivalent standalone System TS that requires changes described in the traveler.

(section 2.2.15 below) 3.8.2, AC Sources - Shutdown The equivalent NMP1 TS do not have OPDRV 3.8.5, DC Sources - Shutdown requirements in these sections and are not 3.8.8, Inverters - Shutdown included.

3.8.10, Distribution Systems- Shutdown 8 NMP1 TSTF-542 Variations

Revised Core Spray LCO 9 NMP1 TSTF-542 Variations

New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.1.9 Reactor Pressure Vessel (RPV) Water Inventory 4.1.9 Reactor Pressure Vessel (RPV) Water Inventory Control Control Applicability: Applicability Applies to the operating status of the core spray Applies to the periodic testing requirements for the systems and Reactor Water Inventory Control when core spray system and RPV water inventory.

the reactor coolant temperature is less than or equal to 212°F. Objective:

Objective: To verify the operability of the core spray system and RPV water inventory.

To assure the RPV water inventory is maintained above -10 inches indicator scale.

Specification: Specification:

a. Whenever irradiated fuel is in the reactor vessel a. Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> in accordance and the reactor coolant temperature is less than or with the Surveillance Frequency Control equal to 212°F, DRAIN TIME of RPV water Program.

inventory to -10 inches indicator scale shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and one core spray subsystem shall be b. Verify, for a required core spray subsystem, the operable except as specified in Specifications b downcomers in the suppression chamber have through f below. greater than or equal to three and one half foot of submergence or the condensate storage

b. If the required core spray subsystem becomes tank inventory is not less than 300,000 gallons, inoperable, that sub system shall be considered in accordance with the Surveillance Frequency operable provided that the component is returned Control Program.

to an operable condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c. Verify for the required core spray subsystem,
c. If Specifications a and b are not met, then each manual power operated and automatic immediately initiate action to establish a method of valve in the flow path, that is not locked, sealed water injection capable of operating without offsite or otherwise secured in position, is in the electrical power. correct position, in accordance with the Surveillance Frequency Control Program.

10 NMP1 TSTF-542 Variations

New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

d. If DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, within 4 d. Verify each valve credited for automatically hours perform the following actions: isolating a penetration flow path actuates to the isolation position on an actual or simulated (1) Verify secondary containment boundary is isolation signal, in accordance with the capable of being established in less than the Surveillance Frequency Control Program.

DRAIN TIME.

AND e. Verify the required core spray subsystem actuates (2) Verify each secondary containment penetration on a manual initiation signal, in accordance with flow path is capable of being isolated in less than the Surveillance Frequency Control Program.

the DRAIN TIME, Vessel spray may be excluded.

AND (3) Verify one RBEVS is capable of being placed in operation in less than the DRAIN TIME.

e. If Drain Time < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, immediately perform the following actions:

(1) Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > -10 inches indicator scale for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND (2) Initiate action to establish secondary containment boundary, AND (3) Initiate action to isolate each secondary containment penetration low path or verify it can be manually isolated from the control room.

AND (4) Initiate action to verify one RBEVS is capable of being placed in operation.

11 NMP1 TSTF-542 Variations

New LCOs - RPV WIC LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

f. Specifications d and e not met, or DRAIN TIME is

< 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, immediately initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

12 NMP1 TSTF-542 Variations

Revision to Existing Instrumentation Tables 13 NMP1 TSTF-542 Variations

Revision to Existing Instrumentation Tables 14 NMP1 TSTF-542 Variations

New LCOs - RPV WIC Instrumentation 15 NMP1 TSTF-542 Variations

New LCOs - RPV WIC Instrumentation TABLE 3.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION 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 Shutdown Refuel Startup Run PRIMARY COOLANT ISOLATION (1) Low-Low Reactor Water Level (a) Cleanup 2 2(f) 5 inches (a) (a)

(Indicator Scale)

(b) Shutdown Cooling 2(e) 2(e)(f) 5 inches (a) (a)

(Indicator Scale)

(2) Manual 2 1 --- (a) (a) 16 NMP1 TSTF-542 Variations

New LCOs - RPV WIC Instrumentation NOTES FOR TABLES 3.6.2m and 4.6.2m (a) The Parameters in this table are only applicable in the Shutdown Condition - Cold and Refuel. See Table 3.6.2b or Table 3.6.2d for Parameter applicability in the Shutdown Condition - Hot.

(b) May be bypassed when necessary for performing major maintenance as specified in Specification 2.1.1.e.

(c) The instrumentation that initiates the Core Spray System is not required to be operable, if there is no fuel in the reactor vessel.

(d) 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 surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that parameter.

With the number of Operable channels less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement:

1. With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or take the ACTION required by Specification 3.6.2a for that Parameter.
2. With more than one channel inoperable, take the ACTION required by Specification 3.6.2a for that Parameter.

(e) In the cold shutdown and refueling conditions, only one Operable Trip System is required provided shutdown cooling system integrity is maintained. With one of the two required Operable Channels in the required Trip System not operable, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Otherwise, either:

1. Immediately initiate action to restore the channel to operable status.

or

2. Immediately initiate action to isolate the shutdown cooling system.

17 NMP1 TSTF-542 Variations

New LCOs - RPV WIC Instrumentation NOTES FOR TABLES 3.6.2m and 4.6.2m (f) 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 surveillances without placing the Trip System in the tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that Parameter.

With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for one trip system, either

1. Place the inoperable channel(s) in the tripped condition within
a. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Parameters common to SCRAM Instrumentation, and
b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Parameters not common to SCRAM Instrumentation.

or

2. Take the ACTION required by Specification 3.6.2a for that Parameter.

With the number of Operable Channels one less than required by the Minimum Number of Operable Instrument Channels per Operable Trip System requirement for both trip systems,

1. Place the inoperable channel(s) in one trip system in the tripped condition within one hour.

and

2. a. Place the inoperable channel(s) in the remaining trip system in the tripped condition within (1) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Parameters common to SCRAM Instrumentation, and (2) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Parameters not common to SCRAM Instrumentation.

or

b. take the ACTION required by Specification 3.6.2a for that Parameter.

(g) The trip circuit will be calibrated and tested in accordance with the Surveillance Frequency Control Program, the primary sensor will be calibrated and tested in accordance with the Surveillance Frequency Control Program.

Note 1: Surveillance intervals are specified in the Surveillance Frequency Control Program unless otherwise noted in Table 4.6.2m.

18 NMP1 TSTF-542 Variations

New RPV WIC Instrumentation SRs Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration PRIMARY COOLANT ISOLATION (Cleanup and Shutdown Cooling)

(1) Low-Low Reactor Water Note 1 Note 1(g) Note 1(g)

Level (2) Manual --- Note 1 ---

19 NMP1 TSTF-542 Variations

Conclusion

  • The variations proposed are consistent with TSTF-542.
  • Questions?

20 NMP1 TSTF-542 Variations