ML17325A277

Nine Mile Point Nuclear Station, Units 1 - November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation

ML17325A277
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Site:	Nine Mile Point
Issue date:	11/28/2017
From:	Exelon Generation Co
To:	Marshall M L Plant Licensing Branch 1
Marhsall M L, NRR/DORL/LPL, 415-2871
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ML17325A307	List: ML17325A277
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Download: ML17325A277 (21)

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Nine Mile Point Nuclear Station, Unit 1 TSTF-542November 28, 2017Pre 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 formatOperating Conditions and Mode Switch positionsSafety LimitVariations

• NMP1 is pre

-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

-Instrumentation and ControlCriterion 14

-Reactor Coolant Pressure BoundaryCriterion 30

-Quality of Reactor Coolant Pressure BoundaryCriterion 33

-Reactor Coolant MakeupNMP1 TSTF-542 Variations 1

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

-Hot (>212 F)4 - F)Shutdown Condition

- F)5 -RefuelingRefueling ConditionMajor Maintenance Condition (defueled)NMP1 TS Reactor Operating ConditionNMP1 Reactor Mode Switch PositionPower Operating ConditionRun StartupShutdown Condition

-Hot (>212 F)ShutdownShutdown Condition

- F)Shutdown or RefuelRefueling ConditionRefuelMajor Maintenance Condition (defueled)

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.NMP1 TSTF-542 Variations 4

NMP1 ECCS Systems

• 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.NMP1 TSTF-542 Variations 5

LCO VariationsNUREG-1433, BWR/4 ISTSModified for TSTF

-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

-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)

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 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

-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

-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

-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

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)]

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

-ShutdownThe equivalent NMP1 TS do not have OPDRV requirements in these sections and are not included.3.8.5, DC Sources

-Shutdown3.8.8, Inverters

-Shutdown3.8.10, Distribution Systems

-ShutdownNMP1 TSTF-542 Variations 8

Revised Core Spray LCONMP1 TSTF-542 Variations 9

New LCOs -RPV WICNMP1 TSTF-542 Variations 10 LIMITING CONDITION FOR OPERATION

3.1.9 Reactor

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 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 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 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

Pressure Vessel (RPV) Water Inventory Control Applicability Applies to the periodic testing requirements for the core spray system and RPV water inventory

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

. Specification

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 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

. 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.

New LCOs -RPV WICNMP1 TSTF-542 Variations 11 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> perform the following actions:

(1) Verify secondary containment boundary is capable of being established in less than the DRAIN TIME.

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.

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 indicat or 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.

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.

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 WICNMP1 TSTF-542 Variations 12 LIMITING CONDITION FOR OPERATION

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 />. 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)

(a) (a) (b) Shutdown Cooling 2(e) 2 (e)(f) (Indicator Scale)

(a) (a) (2) Manual 2 1 --- (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

- Cold and Refuel. See Table 3.6.2 b or Table 3.6.2d for Parameter applicab i lity 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 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 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 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) ---

Conclusion

• The variations proposed are consistent with TSTF-542.*Questions?NMP1 TSTF-542 Variations 20