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| number = ML17325A277 | | number = ML17325A277 | ||
| issue date = 11/28/2017 | | issue date = 11/28/2017 | ||
| title = | | 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 | | 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 | | 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- | {{#Wiki_filter:Nine Mile Point Nuclear Station, Unit 1 TSTF-542 November 28, 2017 Pre Submittal Briefing | ||
*Purpose TSTF-542, | |||
-542 to NMP1 Custom Technical Specifications | Introduction | ||
*Outline Table of contents and | * Purpose TSTF-542, Reactor Pressure Vessel Water Inventory Control, submittal. | ||
*NMP1 is pre | Application of TSTF-542 to NMP1 Custom Technical Specifications | ||
-GDC | * Outline Table of contents and format Operating Conditions and Mode Switch positions Safety Limit Variations | ||
-Instrumentation and | * 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 | 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 | |||
-Reactor Coolant | NMP1 TS Format 2 NMP1 TSTF-542 Variations | ||
NMP1 TS | |||
NMP1 Operating Conditions and | 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 - | 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) | |||
- F)Shutdown or | |||
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 | : 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 | : 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 | * 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 | * 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 ADS and Core Spray systems are considered the ECCS systems at NMP1. | ||
-542)3.3.5.3 RCIC system Instrumentation | 5 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 | |||
Table 3.6.2b/4.6.2b Instrumentation that Initiates Primary Coolant System or Containment | 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 | * 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 | * 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 | * 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) | * 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 | * 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. | |||
Pressure Vessel (RPV) Water Inventory Control | 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: | ||
. c. Verify for the required core spray subsystem, each manual power operated and automatic valve in the flow path, that is not locked, sealed | : 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 | 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. | ||
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 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 > -10 inches indicator scale for 36 hours. | |||
-10 inches | 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 | 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 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 | |||
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) | |||
New LCOs -RPV WIC | (Indicator Scale) | ||
- Cold and Refuel. See Table 3.6. | (b) Shutdown Cooling 2(e) 2(e)(f) 5 inches (a) (a) | ||
- Hot. | (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 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. | : 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 | 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 | 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, | : 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. | |||
Note 1: | and | ||
New RPV WIC Instrumentation | : 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 | * The variations proposed are consistent with TSTF-542. | ||
* Questions? | |||
20 NMP1 TSTF-542 Variations}} |
Latest revision as of 05:54, 29 October 2019
ML17325A277 | |
Person / Time | |
---|---|
Site: | Nine Mile Point |
Issue date: | 11/28/2017 |
From: | Exelon Generation Co |
To: | Marshall M Plant Licensing Branch 1 |
Marhsall M, NRR/DORL/LPL, 415-2871 | |
Shared Package | |
ML17325A307 | List: |
References | |
Download: ML17325A277 (21) | |
Text
Nine Mile Point Nuclear Station, Unit 1 TSTF-542 November 28, 2017 Pre Submittal Briefing
Introduction
- Purpose TSTF-542, Reactor Pressure Vessel Water Inventory Control, submittal.
Application of TSTF-542 to NMP1 Custom Technical Specifications
- Outline Table of contents and format Operating Conditions and Mode Switch positions Safety Limit Variations
- 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.
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
- 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.
- 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.
- 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 ADS and Core Spray systems are considered the ECCS systems at NMP1.
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.
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.
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.
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 />.
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.
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.
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 ---
Conclusion
- The variations proposed are consistent with TSTF-542.
- Questions?