Text

Rev. 48 to Technical Requirements Manual
	ML22292A119
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/2022
From:	; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML22292A107	List: ML22292A061; ML22292A062; ML22292A063; ML22292A064; ML22292A065; ML22292A066; ML22292A067; ML22292A068; ML22292A069; ML22292A070; ML22292A071; ML22292A072; ML22292A073; ML22292A074; ML22292A075; ML22292A076; ML22292A077; ML22292A078; ML22292A079; ML22292A080; ML22292A081; ML22292A082; ML22292A083; ML22292A084; ML22292A085; ML22292A086; ML22292A087; ML22292A088; ML22292A089; ML22292A090; ML22292A091; ML22292A092; ML22292A093; ML22292A094; ML22292A095; ML22292A096; ML22292A097; ML22292A098; ML22292A099; ML22292A100; ML22292A101; ML22292A102; ML22292A103; ML22292A104; ML22292A105; ML22292A106; ML22292A108; ML22292A109; ML22292A110; ML22292A111; ... further results
References
	NMP2L2821
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NINE MILE POINT UNIT 2 TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES DCP-i Rev. 33 3.3-27 Rev. 48 i Rev. 2 3.3-27a Rev. 8 ii Rev. 36 3.3-28 Rev. 19 iii Rev. 30 3.3-29 Rev. 19 iv Rev. 47 3.3-30 Rev. 40 v Rev. 21 3.3-31 Rev. 28 vi Rev. 41 3.3-32 Rev. 28 vii Rev. 36 3.3-33 Rev. 2 viii Rev. 21 3.3-34 Rev. 28 ix Rev. 29 3.3-35 Rev. 23 x Rev. 21 3.3-36 Rev. 2 1.1-1 Rev. 2 3.3-37 Rev. 2 1.2-1 Rev. 2 3.3-38 Rev. 14 1.3-1 Rev. 2 3.3-39 Rev. 23 1.4-1 Rev. 2 3.3-40 Rev. 45 3.0-1 Rev. 32 3.4-1 Rev. 2 3.0-2 Rev. 14 3.4-2 Rev. 2 3.0-3 Rev. 13 3.4-3 Rev. 2 3.0-4 Rev. 14 3.4-4 Rev. 2 3.1-1 Rev. 2 3.4-5 Rev. 2 3.3-1 Rev. 40 3.4-6 Rev. 2 3.3-2 Rev. 5 3.4-7 Rev. 2 3.3-3 Rev. 2 3.4-8 Rev. 2 3.3-4 Rev. 2 3.4-9 Rev. 10 3.3-5 Rev. 2 3.4-10 Rev. 10 3.3-6 Rev. 40 3.4-11 Rev. 38 3.3-7 Rev. 41 3.4-12 Rev. 38 3.3-8 Rev. 27 3.4-13 Rev. 30 3.3-9 Rev. 25 3.4-14 Rev. 30 3.3-10 Rev. 37 3.4-15 Rev. 30 3.3-11 Rev. 43 3.4-16 Rev. 30 3.3-11a Rev. 36 3.5-1 Rev. 40 3.6-1 Rev. 2 3.3-12 Rev. 2 3.6-2 Rev. 35 3.3-13 Rev. 2 3.6-3 Rev. 2 3.3-14 Rev. 2 3.6-4 Rev. 2 3.3-15 Rev. 2 3.6-5 Rev. 2 3.3-16 Rev. 46 3.6-6 Rev. 3 3.3-17 Rev. 2 3.6-7 Rev. 35 3.3-18 Rev. 2 3.6-8 Rev. 34 3.3-19 Rev. 2 3.6-9 Rev. 34 3.3-20 Rev. 2 3.6-10 Rev. 34 3.3-21 Rev. 2 3.6-11 Rev. 35 3.3-22 Rev. 2 3.6-12 Rev. 34 3.3-23 Rev. 23 3.6-13 Rev. 41 3.3-24 Rev. 2 3.6-14 Rev. 34 3.3-25 Rev. 7 3.6-15 Rev. 35 3.3-26 Rev. 7 NMP2 TRM TRM LEP-i Rev. 48 March 2022

NINE MILE POINT UNIT 2 TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES 3.6-16 Rev. 35 3.9-3 Rev. 2 3.6-17 Rev. 34 3.9-4 Rev. 46 3.6-18 Rev. 34 3.9-5 Rev. 2 3.6-19 Rev. 34 3.11-1 Rev. 2 3.6-20 Rev. 34 3.11-2 Rev. 2 3.6-21 Rev. 34 5.5-1 Rev. 2 3.6-22 Rev. 34 5.5-2 Rev. 11 3.6-22a Rev. 41 5.5-3 Rev. 21 3.6-23 Rev. 34 5.5-4 Rev. 33 3.6-23a Rev. 33 5.5-5 Rev. 2 3.6-23b Rev. 33 5.5-6 Rev. 2 3.6-24 Rev. 2 5.5-7 Rev. 33 3.6-25 Rev. 2 5.5-8 Rev. 33 3.6-26 Rev. 2 5.5-9 Rev. 2 3.6-27 Rev. 2 5.5-10 Rev. 41 3.6-28 Rev. 2 5.5-11 Rev. 41 3.6-29 Rev. 2 5.5-12 Rev. 41 3.6-30 Rev. 35 5.5-13 Rev. 41 3.6-31 Rev. 2 5.5-14 Rev. 41 3.6-32 Rev. 2 5.5-15 Rev. 28 3.7-1 Rev. 40 5.5-16 Rev. 40 3.7-2 Rev. 44 5.5-17 Rev. 40 3.7-3 Rev. 40 5.5-18 Rev. 40 3.7-4 Rev. 2 3.7-5 Rev. 24 3.7-6 Rev. 41 3.7-6a Rev. 41 3.7-7 Rev. 16 3.7-8 Rev. 2 3.7-9 Rev. 2 3.7-10 Rev. 2 3.7-11 Rev. 2 3.7-12 Rev. 2 3.7-13 Rev. 21 3.7-14 Rev. 2 3.7-15 Rev. 2 3.7-16 Rev. 14 3.8-1 Rev. 17 3.8-2 Rev. 2 3.8-3 Rev. 2 3.8-4 Rev. 2 3.8-5 Rev. 39 3.8-6 Rev. 47 3.8-7 Rev. 39 3.8-8 Rev. 46 3.8-9 Rev. 2 3.9-1 Rev. 2 3.9-2 Rev. 2 NMP2 TRM TRM LEP-ii Rev. 48 March 2022

NINE MILE POINT UNIT 2 TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES B3.0-1 Rev. 32 B3.8-1 Rev. 17 B3.1-1 Rev. 2 B3.8-2 Rev. 29 B3.3-1 Rev. 2 B3.8-3 Rev. 29 B3.3-2 Rev. 2 B3.8-4 Rev. 29 B3.3-3 Rev. 2 B3.9-1 Rev. 2 B3.3-4 Rev. 36 B3.9-2 Rev. 2 B3.3-5 Rev. 2 B3.9-3 Rev. 2 B3.3-6 Rev. 2 B3.9-4 Rev. 2 B3.3-7 Rev. 2 B3.11-1 Rev. 23 B3.3-8 Rev. 2 B3.3-9 Rev. 2 B3.3-10 Rev. 2 B3.3-11 Rev. 2 B3.3-12 Rev. 2 B3.3-13 Rev. 19 B3.3-14 Rev. 27 B3.3-15 Rev. 2 B3.3-16 Rev. 4 B3.4-1 Rev. 2 B3.4-2 Rev. 21 B3.4-3 Rev. 2 B3.4-4 Rev. 2 B3.5-1 Rev. 40 B3.6-1 Rev. 2 B3.6-2 Rev. 2 B3.6-3 Rev. 2 B3.6-4 Rev. 2 B3.7-1 Rev. 27 B3.7-2 Rev. 2 B3.7-3 Rev. 41 B3.7-4 Rev. 41 B3.7-5 Rev. 2 B3.7-6 Rev. 2 B3.7-7 Rev. 2 B3.7-8 Rev. 2 B3.7-9 Rev. 2 B3.7-10 Rev. 2 B3.7-11 Rev. 10 NMP2 TRM TRM LEP-iii Rev. 48 March 2022

TABLE OF CONTENTS TRM SPECIFICATIONS. . . . . . . . . . . . . . . . . . . . . 1.1-1 1.0 USE AND APPLICATION . . . . . . . . . . . . . . 1.1-1 1.1 Definitions . . . . . . . . . . . . . . . . . . 1.1-1 1.2 Logical Connectors. . . . . . . . . . . . . . . 1.2-1 1.3 Completion Times. . . . . . . . . . . . . . . . 1.3-1 1.4 Frequency . . . . . . . . . . . . . . . . . . . 1.4-1 2.0 NOT USED 3.0 TLCO APPLICABILITY. . . . . . . . . . . . . . . 3.0-1 TRSR APPLICABILITY. . . . . . . . . . . . . . . 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS. . . . . . . . . . . 3.1-1 3.1.1 Not used 3.1.2 Not used 3.1.3 Not used 3.1.4 Control Rod Scram Times < 800 psig. . . . . . . 3.1-1 3.2 NOT USED (continued)

NMP2 TRM i Rev. 2 November 2000

TABLE OF CONTENTS (continued) 3.3 INSTRUMENTATION . . . . . . . . . . . . . . 3.3-1 3.3.1.1 Reactor Protection System (RPS) RESPONSE TIME . 3.3-1 3.3.1.2 Reactor Protection System (RPS) Shorting Links 3.3-2 3.3.2 Control Rod Block Instrumentation . . . . . . . 3.3-4 3.3.3.1 Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation. . . . . . . . . 3.3-10 3.3.3.1.1 Deleted 3.3.3.2 Remote Shutdown System. . . . . . . . . . . . . 3.3-12 3.3.4 End of Cycle Recirculation Pump Trip (EOC-RPT)

SYSTEM RESPONSE TIME. . . . . . . . . . . . 3.3-14 3.3.5 Emergency Core Cooling System (ECCS)

Instrumentation . . . . . . . . . . . . . . 3.3-15 3.3.6.1 Primary Containment ISOLATION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . 3.3-17 3.3.6.2 Primary Containment Isolation Instrumentation . 3.3-18 3.3.7.1 Area Radiation Monitoring Instrumentation . . . 3.3-20 3.3.7.2 Seismic Monitoring Instrumentation. . . . . . . 3.3-23 3.3.7.3 Traversing In-Core Probe (TIP) System . . . . . 3.3-27 3.3.7.4 Deleted 3.3-28 3.3.8 Not used 3.3.9 Service Water System Instrumentation. . . . . . 3.3-30 3.3.10 Meteorological Monitoring Instrumentation . . . 3.3-35 3.3.11 Offgas System Explosive Gas Monitoring. . . . . 3.3-38 (continued)

NMP2 TRM ii Rev. 36 September 2017

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM. . . . . . . . . . . . . 3.4-1 3.4.1 Reactor Coolant System (RCS) Chemistry. . . . . 3.4-1 3.4.2 Structural Integrity. . . . . . . . . . . . . . 3.4-9 3.4.3 Not used 3.4.4 Not used 3.4.5 Not used 3.4.6 Pressure Isolation Valves . . . . . . . . . . . 3.4-11 3.4.7 Not used 3.4.8 Reactor Coolant System (RCS) Specific Activity. 3.4-16 3.5 EMERGENCY CORE COOLING SYSTEMS. . . . . . . . . 3.5-1 3.5.1 Emergency Core Cooling Systems (ECCS) RESPONSE TIME. . . . . . . . . . . . . . . . . . . . 3.5-1 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . 3.6-1 3.6.1 Primary Containment Isolation Valves. . . . . . 3.6-1 3.6.2 Not used 3.6.3 Not used 3.6.4.1 Secondary Containment . . . . . . . . . . . . . 3.6-24 3.6.4.2 Secondary Containment Isolation Valves. . . . . 3.6-27 3.6.4.3 Standby Gas Treatment System. . . . . . . . . . 3.6-32 (continued)

NMP2 TRM iii Rev. 30 April 2010

TABLE OF CONTENTS (continued) 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . 3.7-1 3.7.1 Service Water (SW) System - Shutdown. . . . . . 3.7-1 3.7.2 Control Room Envelope Filtration System . . . . 3.7-4 3.7.3 Snubbers. . . . . . . . . . . . . . . . . . . . 3.7-5 3.7.4 Sealed Source Contamination . . . . . . . . . . 3.7-7 3.7.5 Main Turbine Bypass System. . . . . . . . . . . 3.7-9 3.7.6 Revetment-Ditch Structure . . . . . . . . . . . 3.7-10 3.7.7 Liquid Holdup Tanks . . . . . . . . . . . . . . 3.7-14 3.7.8 Explosive Gas Mixture . . . . . . . . . . . . . 3.7-16 3.8 ELECTRICAL POWER SYSTEMS. . . . . . . . . . . . 3.8-1 3.8.1 Not used 3.8.2.1 AC Circuits Inside Primary Containment. . . . . 3.8-1 3.8.2.2 Primary Containment Penetration Conductor Overcurrent Protective Devices. . . . . . . 3.8-4 3.8.2.3 Emergency Lighting System - Overcurrent Protective Devices. . . . . . . . . . . . . 3.8-7 3.9 REFUELING OPERATIONS. . . . . . . . . . . . . . 3.9-1 3.9.1 Not used 3.9.2 Decay Time. . . . . . . . . . . . . . . . . . . 3.9-1 3.9.3 Communications. . . . . . . . . . . . . . . . . 3.9-2 3.9.4 Refueling Platform. . . . . . . . . . . . . . . 3.9-3 3.9.5 Crane Travel - Spent Fuel Storage Pool. . . . . 3.9-5 3.10 NOT USED (continued)

NMP2 TRM iv Rev.47 March 2022 l

TABLE OF CONTENTS (continued) 3.11 RADIOACTIVE EFFLUENTS . . . . . . . . . . . . . 3.11-1 3.11.1 Solid Radioactive Wastes. . . . . . . . . . . . 3.11-1 4.0 NOT USED 5.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . 5.5-1 5.1 NOT USED 5.2 NOT USED 5.3 NOT USED 5.4 NOT USED (continued)

NMP2 TRM v Rev. 21 April 2006

TABLE OF CONTENTS (continued) 5.5 PROGRAMS. . . . . . . . . . . . . . . . . . . . 5.5-1 5.5.1 Not used 5.5.2 Primary Coolant Sources Outside Containment Program. . . . . . . . . . . . . . . . . . . 5.5-1 5.5.3 Deleted . . . . . . . . . . . . . . . . . . . . 5.5-2 5.5.4 Not used 5.5.5 Component Cyclic or Transient Limit . . . . . . 5.5-3 5.5.6 Not used 5.5.7 Ventilation Filter Testing Program. . . . . . . 5.5-4 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program . . . . . . . . . . . . . 5.5-5 5.5.9 Diesel Fuel Oil Testing Program . . . . . . . . 5.5-6 5.5.10 Technical Specifications Bases Control Program. 5.5-7 5.5.11 Safety Function Determination Program . . . . . 5.5-8 5.5.12 10 CFR 50 Appendix J Testing Program Plan . . . 5.5-9 5.5.13 Snubber Program. 5.5-10 5.5.14 Control Room Envelope Habitability Program. . . 5.5-15 5.5.15 Technical Requirements Manual Control Program 5.5-18 TRM BASES . . . . . . . . . . . . . . . . . . . . . . . . B3.0-1 B3.0 TLCO AND TRSR APPLICABILITY . . . . . . . . . . B3.0-1 B3.1 REACTIVITY CONTROL SYSTEMS. . . . . . . . . . . B3.1-1 B3.1.1 Not used B3.1.2 Not used B3.1.3 Not used B3.1.4 Control Rod Scram Times < 800 psig. . . . . . . B3.1-1 (continued)

NMP2 TRM vi Rev. 41 March 2019

TABLE OF CONTENTS (continued)

B3.2 NOT USED B3.3 INSTRUMENTATION . . . . . . . . . . . . . . . B3.3-1 B3.3.1.1 Reactor Protection System (RPS) RESPONSE TIME . B3.3-1 B3.3.1.2 Reactor Protection System (RPS) Shorting Links B3.3-2 B3.3.2 Control Rod Block Instrumentation . . . . . . . B3.3-3 B3.3.3.1 Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation. . . . . . . . . B3.3-4 B3.3.3.1.1 Deleted B3.3.3.2 Remote Shutdown System. . . . . . . . . . . . . B3.3-5 B3.3.4 End of Cycle Recirculation Pump Trip (EOC-RPT)

SYSTEM RESPONSE TIME. . . . . . . . . . . . B3.3-6 B3.3.5 Emergency Core Cooling System (ECCS)

Instrumentation . . . . . . . . . . . . . . B3.3-7 B3.3.6.1 Primary Containment ISOLATION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . B3.3-8 B3.3.6.2 Primary Containment Isolation Instrumentation . B3.3-9 B3.3.7.1 Area Radiation Monitoring Instrumentation . . . B3.3-10 B3.3.7.2 Seismic Monitoring Instrumentation. . . . . . . B3.3-11 B3.3.7.3 Traversing In-Core Probe (TIP) System . . . . . B3.3-12 B3.3.7.4 Deleted B3.3-13 B3.3.8 Not used B3.3.9 Service Water System Instrumentation. . . . . . B3.3-14 B3.3.10 Meteorological Monitoring Instrumentation . . . B3.3-15 B3.3.11 Offgas System Explosive Gas Monitoring. . . . . B3.3-16 (continued)

NMP2 TRM vii Rev. 36 September 2017

TABLE OF CONTENTS (continued)

B3.4 REACTOR COOLANT SYSTEM. . . . . . . . . . . . . B3.4-1 B3.4.1 Reactor Coolant System (RCS) Chemistry. . . . . B3.4-1 B3.4.2 Structural Integrity. . . . . . . . . . . . . . B3.4-2 B3.4.3 Not used B3.4.4 Not used B3.4.5 Not used B3.4.6 Pressure Isolation Valves . . . . . . . . . . . B3.4-3 B3.4.7 Not used B3.4.8 Reactor Coolant System (RCS) Specific Activity. B3.4-4 B3.5 EMERGENCY CORE COOLING SYSTEMS. . . . . . . . . B3.5-1 B3.5.1 Emergency Core Cooling Systems (ECCS) RESPONSE TIME. . . . . . . . . . . . . . . . . . . . B3.5-1 B3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . B3.6-1 B3.6.1 Primary Containment Isolation Valves. . . . . . B3.6-1 B3.6.2 Not used B3.6.3 Not used B3.6.4.1 Secondary Containment . . . . . . . . . . . . . B3.6-2 B3.6.4.2 Secondary Containment Isolation Valves. . . . . B3.6-3 B3.6.4.3 Standby Gas Treatment System. . . . . . . . . . B3.6-4 (continued)

NMP2 TRM viii Rev. 21 April 2006

TABLE OF CONTENTS (continued)

B3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . B3.7-1 B3.7.1 Service Water (SW) System - Shutdown. . . . . . B3.7-1 B3.7.2 Control Room Envelope Filtration System . . . . B3.7-2 B3.7.3 Snubbers. . . . . . . . . . . . . . . . . . . . B3.7-3 B3.7.4 Sealed Source Contamination . . . . . . . . . . B3.7-5 B3.7.5 Main Turbine Bypass System. . . . . . . . . . . B3.7-6 B3.7.6 Revetment-Ditch Structure . . . . . . . . . . . B3.7-7 B3.7.7 Liquid Holdup Tanks . . . . . . . . . . . . . . B3.7-10 B3.7.8 Explosive Gas Mixture . . . . . . . . . . . . . B3.7-11 B3.8 ELECTRICAL POWER SYSTEMS. . . . . . . . . . . . B3.8-1 B3.8.1 Not used B3.8.2.1 AC Circuits Inside Primary Containment. . . . . B3.8-1 B3.8.2.2 Primary Containment Penetration Conductor Overcurrent Protective Devices. . . . . . . B3.8-2 B3.8.2.3 Emergency Lighting System - Overcurrent Protective Devices. . . . . . . . . . . . . B3.8-4 B3.9 REFUELING OPERATIONS. . . . . . . . . . . . . . B3.9-1 B3.9.1 Not used B3.9.2 Decay Time. . . . . . . . . . . . . . . . . . . B3.9-1 B3.9.3 Communications. . . . . . . . . . . . . . . . . B3.9-2 B3.9.4 Refueling Platform. . . . . . . . . . . . . . . B3.9-3 B3.9.5 Crane Travel - Spent Fuel Storage Pool. . . . . B3.9-4 (continued)

NMP2 TRM ix Rev. 29 April 2010

TABLE OF CONTENTS (continued)

B3.10 NOT USED B3.11 RADIOACTIVE EFFLUENTS . . . . . . . . . . . . . B3.11-1 B3.11.1 Solid Radioactive Wastes. . . . . . . . . . . . B3.11-1 NMP2 TRM x Rev. 21 April 2006

Definitions TRM 1.1 TRM 1.0 USE AND APPLICATION TRM 1.1 Definitions

NOTES--------------------------------------

1. The defined terms of this section appear in capitalized type and are applicable throughout this Technical Requirements Manual (TRM).

2. The terms defined in Technical Specification Section 1.1 also appear in capitalized type in this TRM and are applicable to this TRM.

3. The terms defined in the OFFSITE DOSE CALCULATION MANUAL (ODCM) Part I, Section 1.1 also appear in capitalized type in this TRM and are applicable to this TRM.

Definition Term None NMP2 TRM 1.1-1 Rev. 2 November 2000

Logical Connectors TRM 1.2 TRM 1.0 USE AND APPLICATION TRM 1.2 Logical Connectors Technical Specifications Section 1.2, Logical Connectors, is applicable to Section 3.0 of this Technical Requirements Manual.

NMP2 TRM 1.2-1 Rev. 2 November 2000

Completion Times TRM 1.3 TRM 1.0 USE AND APPLICATION TRM 1.3 Completion Times Technical Specifications Section 1.3, Completion Times, is applicable to Section 3.0 of this Technical Requirements Manual.

NMP2 TRM 1.3-1 Rev. 2 November 2000

Frequency TRM 1.4 TRM 1.0 USE AND APPLICATION TRM 1.4 Frequency Technical Specifications Section 1.4, Frequency, is applicable to Section 3.0 of this Technical Requirements Manual.

NMP2 TRM 1.4-1 Rev. 2 November 2000

TECHNICAL REQUIREMENTS MANUAL SECTION 2.0 IS NOT USED.

TLCO Applicability TRM 3.0 TRM 3.0 TLCO APPLICABILITY TLCO 3.0.1 TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TLCO 3.0.2.

TLCO 3.0.2 Upon discovery of a failure to meet a TLCO, the Required Actions of the associated Conditions shall be met, except as provided in TLCO 3.0.5.

If the TLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

TLCO 3.0.3 When a TLCO is not met and the associated ACTIONS are not met or an associated ACTION is not provided, action shall be taken immediately to initiate a CR.

TLCO 3.0.3 is only applicable in MODES 1, 2, and 3.

TLCO 3.0.4 When a TLCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or (continued)

NMP2 TRM 3.0-1 Rev. 32 August 2012

TLCO Applicability TRM 3.0 TRM 3.0 TLCO APPLICABILITY (continued)

TLCO 3.0.4 c. When an allowance is stated in the individual value, (continued) parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

TLCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TLCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

NMP2 TRM 3.0-2 Rev. 14 February 2004

TRSR Applicability TRM 3.0 TRM 3.0 TRSR APPLICABILITY TRSR 3.0.1 TRSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the TRSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the TLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the TLCO except as provided in TRSR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

TRSR 3.0.2 The specified Frequency for each TRSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as once, the above interval extension does not apply.

If a Completion Time requires periodic performance on a once per basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

TRSR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.

A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

NMP2 TRM 3.0-3 Rev. 13 November 2002

TRSR Applicability TRM 3.0 TRM 3.0 TRSR APPLICABILITY (continued)

TRSR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a TLCO shall only be made when the TLCOs Surveillances have been met within their specified Frequency, except as provided by TRSR 3.0.3. When a TLCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with TLCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

NMP2 TRM 3.0-4 Rev. 14 February 2004

Control Rod Scram Times < 800 psig TRM 3.1.4 TRM 3.1 REACTIVITY CONTROL SYSTEMS TRM 3.1.4 Control Rod Scram Times < 800 psig The Control Rod Scram Times for reactor pressures < 800 psig for Technical Specification SR 3.1.4.3 are described in Table T3.1.4-1.

TABLE T3.1.4-1 (Page 1 of 1)

Control Rod Scram Times < 800 psig Notch Position 0 psig Scram Time(a),(b) (sec) 05(c) 2.04 (a) Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids as time zero.

(b) For intermediate reactor steam dome pressures, the scram time criteria are determined by linear interpolation for notch position 05 between the 0 psig scram time in this Table and the

> 800 psig scram time in Technical Specifications Table 3.1.4-1.

(c) For reactor steam dome pressure < 800 psig, only notch position 05 scram time limit applies.

NMP2 TRM 3.1-1 Rev. 2 November 2000

Reactor Protection System (RPS) RESPONSE TIME TRM 3.3.1.1 TRM 3.3 INSTRUMENTATION TRM 3.3.1.1 Reactor Protection System (RPS) RESPONSE TIME The RPS RESPONSE TIMES for Technical Specifications SR 3.3.1.1.17 are listed in Table T3.3.1.1-1.

TABLE T3.3.1.1-1 (Page 1 of 1)

RPS RESPONSE TIMES FUNCTION RESPONSE TIME (from Technical Specifications Table 3.3.1.1-1) (seconds)

2. Average Power Range Monitor

f. 2-Out-Of-4 Voter < 0.05

3. Reactor Vessel Steam Dome Pressure - High(a) < 0.55

4. Reactor Vessel Water Level - Low, Level 3(a) < 1.05

5. Main Steam Line Isolation Valve - Closure < 0.06

8. Turbine Stop Valve - Closure < 0.07

9. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low < 0.08 (a) Sensor is eliminated from response time testing (RTT) for the RPS circuits. Response to a process step function shall be < 5 seconds. RTT and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required. Time delay relays in the RTT loops require response verification through calibration.

NMP2 TRM 3.3-1 Rev. 40 April 2018

RPS Shorting Links TRM 3.3.1.2 TRM 3.3 INSTRUMENTATION TRM 3.3.1.2 Reactor Protection System (RPS) Shorting Links TLCO 3.3.1.2 The shorting links shall be removed from the RPS circuitry.

APPLICABILITY: MODE 5 during spiral reload with multiple control rods withdrawn, MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, and either:

a. SHUTDOWN MARGIN not demonstrated for the current core configuration, or

b. The Refuel position one-rod-out interlock inoperable.

NOTE----------------------

Not applicable for a single control rod withdrawn per Technical Specification 3.10.5, Single Control Rod Drive (CRD) Removal -

Refueling.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shorting links not A.1 Suspend CORE Immediately removed from RPS ALTERATIONS except circuitry. for control rod insertion.

AND Immediately A.2 Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

NMP2 TRM 3.3-2 Rev. 5 August 2001

RPS Shorting Links TRM 3.3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.3.1.2.1 Verify shorting links removed from RPS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuitry.

NMP2 TRM 3.3-3 Rev. 2 November 2000

Control Rod Block Instrumentation TRM 3.3.2 TRM 3.3 INSTRUMENTATION TRM 3.3.2 Control Rod Block Instrumentation TLCO 3.3.2 The control rod block instrumentation for each Function in Table T3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.2-1.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. For Functions 1 and 2, A.1 Restore inoperable 7 days one required channel channel to OPERABLE inoperable. status.

B. For Functions 3 and 4, B.1 Place at least one 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one or more required inoperable channel in channel(s) inoperable. the tripped condition.

OR For Function 2, more than one required channel inoperable.

(continued)

NMP2 TRM 3.3-4 Rev. 2 November 2000

Control Rod Block Instrumentation TRM 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. For Function 1, more C.1 Place at least one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months than one required inoperable channel in channel inoperable. the tripped condition.

OR For Function 2, control rod block capability not maintained.

OR Required Action and associated Completion Time of Condition A not met.

NMP2 TRM 3.3-5 Rev. 2 November 2000

Control Rod Block Instrumentation TRM 3.3.2 SURVEILLANCE REQUIREMENTS

NOTES--------------------------------------

1. Refer to Table T3.3.2-1 to determine which TRSRs apply to each Control Rod Block Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY TRSR 3.3.2.1 -------------------NOTES-------------------

1. For Function 1, not required to be performed when entering the MODE 2 IRM range Applicability from a higher IRM range until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering the MODE 2 IRM range Applicability.

2. For Function 2, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

31 days Perform CHANNEL FUNCTIONAL TEST.

TRSR 3.3.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days TRSR 3.3.2.3 -------------------NOTES-------------------

1. For Functions 1.b and 1.d, not required to be performed when entering the MODE 2 IRM range Applicability from a higher IRM range until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering the MODE 2 IRM range Applicability.

2. For Functions 2.b and 2.d, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

3. Neutron detectors are excluded.

92 days Perform CHANNEL CALIBRATION.

(continued)

NMP2 TRM 3.3-6 Rev. 40 April 2018

Control Rod Block Instrumentation TRM 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TRSR 3.3.2.4 Perform CHANNEL FUNCTIONAL TEST. 24 months TRSR 3.3.2.5 Perform CHANNEL CALIBRATION. 18 months TRSR 3.3.2.6 Perform CHANNEL CALIBRATION. 24 months NMP2 TRM 3.3-7 Rev. 41 March 2019

Control Rod Block Instrumentation TRM 3.3.2 TABLE T3.3.2-1 (Page 1 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE FUNCTION CONDITIONS FUNCTION REQUIREMENTS ALLOWABLE VALUE

1. Source Range Monitors

a. Detector Not 2(a) 3 TRSR 3.3.2.1 N/A Full In (d) 5 2 TRSR 3.3.2.1 N/A

b. Upscale 2(b) 3 TRSR 3.3.2.1 < 1.6 x 105 cps TRSR 3.3.2.3 5 2(d) TRSR 3.3.2.1 < 1.6 x 105 cps TRSR 3.3.2.3

c. Inop 2(b) 3 TRSR 3.3.2.1 N/A (d) 5 2 TRSR 3.3.2.1 N/A

d. Downscale 2(c) 3 TRSR 3.3.2.1 > 1.8 cps TRSR 3.3.2.3 5 2(d) TRSR 3.3.2.1 > 1.8 cps TRSR 3.3.2.3

2. Intermediate Range Monitors

a. Detector Not 2, 5(f) 6 TRSR 3.3.2.1 N/A Full In

b. Upscale 2, 5(f) 6 TRSR 3.3.2.1 < 110/125 divisions of TRSR 3.3.2.3 full scale

c. Inop 2, 5(f) 6 TRSR 3.3.2.1 N/A

d. Downscale 2(e), 5(e)(f) 6 TRSR 3.3.2.1 > 3/125 divisions of full TRSR 3.3.2.3 scale (continued)

(a) With SRM count rate < 100 cps or IRMs on range 2 or below.

(b) With IRM channels on range 7 or below.

(c) With IRMs on range 2 or below.

(d) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector.

(e) With IRMs on range 2 or higher.

(f) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

NMP2 TRM 3.3-8 Rev. 27 September 2008

Control Rod Block Instrumentation TRM 3.3.2 TABLE T3.3.2-1 (Page 2 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE FUNCTION CONDITIONS FUNCTION REQUIREMENTS ALLOWABLE VALUE

3. Scram Discharge 1, 2, 5(f) 2 TRSR 3.3.2.2 < 39.75 inches Volume Water TRSR 3.3.2.5 Level - High, Float Switch

4. Reactor Coolant System Recirculation Flow

a. Upscale 1 2 TRSR 3.3.2.4 < 111% of rated flow TRSR 3.3.2.6

b. Inop 1 2 TRSR 3.3.2.4 N/A (f) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

NMP2 TRM 3.3-9 Rev. 25 April 2008

Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation TRM 3.3.3.1 TRM 3.3 INSTRUMENTATION TRM 3.3.3.1 Non-Type A, Non-Category 1 Post Accident Monitoring (PAM)

Instrumentation TLCO 3.3.3.1 The PAM instrumentation for each Function in Table T3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore channel to 30 days with one channel OPERABLE status.

inoperable.

B. One or more Functions B.1 Restore one channel 7 days with two channels to OPERABLE status.

inoperable.

C. Required Action and C.1 Complete IR 14 days associated Completion evaluation of the Time of Conditions A degraded condition, or B not met. including preplanned alternate methods of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channel to OPERABLE status.

NMP2 TRM 3.3-10 Rev. 37 October 2017

Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation TRM 3.3.3.1 SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other required channel is OPERABLE.

SURVEILLANCE FREQUENCY TRSR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days TRSR 3.3.3.1.2 Perform CHANNEL CALIBRATION. 24 months TRSR 3.3.3.1.3 Perform CHANNEL CALIBRATION. 184 days NMP2 TRM 3.3-11 Rev. 43 December 2019

Non-Type A, Non-Category 1 Post Accident Monitoring (PAM) Instrumentation TRM 3.3.3.1 TABLE T3.3.3.1-1 (Page 1 of 1)

Non-Type A, Non-Category 1 Post Accident Monitoring (PAM) Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Suppression Chamber Air Temperature 2 TRSR 3.3.3.1.1 TRSR 3.3.3.1.2

2. Drywell H2 Concentration Analyzer 2 TRSR 3.3.3.1.1 TRSR 3.3.3.1.3

3. Drywell O2 Concentration Analyzer 2 TRSR 3.3.3.1.1 TRSR 3.3.3.1.3 NMP2 TRM 3.3-11a Rev. 36 September 2017

Remote Shutdown System TRM 3.3.3.2 TRM 3.3 INSTRUMENTATION TRM 3.3.3.2 Remote Shutdown System

1. The required Remote Shutdown System Monitoring Instrumentation is listed in Table T3.3.3.2-1.

2. The required Remote Shutdown System Controls are listed in Table T3.3.3.2-2.

TABLE T3.3.3.2-1 (Page 1 of 1)

Remote Shutdown System Monitoring Instrumentation Required Readout Location FUNCTION Instruments

1. Service Water Pump Discharge Flow 2 per division 2CES*PNL405

2. Reactor Vessel Pressure 1 per division 2CES*PNL405

3. Reactor Vessel Water Level Wide Range 1 per division 2CES*PNL405

4. Reactor Vessel Water Level Narrow Range 1 per division 2CES*PNL405

5. RCIC Turbine Speed 1 2CES*PNL405

6. Suppression Pool Water Level 1 per division 2CES*PNL405

7. RHR Loop A Flow 1 2CES*PNL405

8. RHR Heat Exchanger Service Water A Flow 1 2CES*PNL405

9. Suppression Pool Temperature 1 per division 2CES*PNL405

10. RHR Loop B Flow 1 2CES*PNL405

11. RHR Heat Exchanger Service Water B Flow 1 2CES*PNL405

12. Safety/Relief Valve Position 1 per valve 2CES*PNL405

13. RCIC Flow Indicator/Controller 1 2CES*PNL405 NMP2 TRM 3.3-12 Rev. 2 November 2000

Remote Shutdown System TRM 3.3.3.2 TABLE T3.3.3.2-2 (Page 1 of 1)

Remote Shutdown System Controls Required Total Systems/

FUNCTION(a) Systems/ Subsystems Subsystems

1. RCIC System 1 1

2. RHR System

a. Shutdown Cooling Mode 1 per division 2

b. Suppression Pool Cooling Mode 1 per division 2

3. Service Water System

a. Pumps 2 per division 6

b. Supply Valves to Division I and Division II Diesels 1 per division 1 per division

4. ADS System (Pressure Relief) 4 valves per 4 valves per division division

5. Nuclear Steam Supply Shutoff System (Isolation Groups 4 1 per division 1 per division and 5 Reset)

6. Nitrogen Supply to ADS Accumulator Tanks 1 per division 1 per division (a) Includes applicable transfer switches NMP2 TRM 3.3-13 Rev. 2 November 2000

EOC-RPT SYSTEM RESPONSE TIME TRM 3.3.4 TRM 3.3 INSTRUMENTATION TRM 3.3.4 End of Cycle Recirculation Pump Trip (EOC-RPT) SYSTEM RESPONSE TIME The EOC-RPT SYSTEM RESPONSE TIMES for Technical Specifications SR 3.3.4.1.5 are listed in Table T3.3.4-1.

TABLE T3.3.4-1 (Page 1 of 1)

EOC-RPT SYSTEM RESPONSE TIMES Response Time FUNCTION (msec)

1. Turbine Stop Valve - Closure < 190

2. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low < 190 NMP2 TRM 3.3-14 Rev. 2 November 2000

Emergency Core Cooling System (ECCS) Instrumentation TRM 3.3.5 TRM 3.3 INSTRUMENTATION TRM 3.3.5 Emergency Core Cooling System (ECCS) Instrumentation TLCO 3.3.5 One channel per trip system of the Automatic Depressurization System (ADS) Manual Inhibit Function shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Declare associated Immediately inoperable. ADS Trip System inoperable.

NMP2 TRM 3.3-15 Rev. 2 November 2000

Emergency Core Cooling System (ECCS) Instrumentation TRM 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.3.5.1 Perform CHANNEL FUNCTIONAL TEST. 92 days 24 months staggered (48 TRSR 3.3.5.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. months per division)

NMP2 TRM 3.3-16 Rev. 46 February 2022

Primary Containment ISOLATION SYSTEM RESPONSE TIME TRM 3.3.6.1 TRM 3.3 INSTRUMENTATION TRM 3.3.6.1 Primary Containment ISOLATION SYSTEM RESPONSE TIME The Primary Containment ISOLATION SYSTEM RESPONSE TIME for Technical Specification SR 3.3.6.1.7 is calculated by adding the Table T3.3.6.1-1 Isolation System Instrumentation Response Time value to the Table T3.6.1-2 Maximum Closing Time value for the associated valves.

TABLE T3.3.6.1-1 (Page 1 of 1)

Isolation System Instrument Response Times Trip Function Valve Group Instrumentation Response Time (sec)

Main Steam Line Isolation(a)

a. Reactor Vessel Water Level - 1 < 1.0 Low Low Low, Level 1

b. Main Steam Line Pressure - Low 1 < 1.0

c. Main Steam Line Flow - High 1 < 0.5 (a) Sensor is eliminated from response time testing (RTT) for the MSIV actuation logic circuits.

Response to a process step function shall be < 5 seconds. RTT and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required. Time delay relays in the RTT loops require response verification through calibration.

NMP2 TRM 3.3-17 Rev. 2 November 2000

Primary Containment Isolation Instrumentation TRM 3.3.6.2 TRM 3.3 INSTRUMENTATION TRM 3.3.6.2 Primary Containment Isolation Instrumentation TLCO 3.3.6.2 Two channels per trip system for each RCIC Primary Containment Isolation Instrumentation input listed below shall be OPERABLE:

a. Drywell Pressure - High

b. RCIC Steam Supply Pressure - Low APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months channels inoperable. channel(s) in trip.

B. Isolation capability B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not maintained. capability.

C. Required Action and C.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion penetration flow Time not met. path.

NMP2 TRM 3.3-18 Rev. 2 November 2000

Primary Containment Isolation Instrumentation TRM 3.3.6.2 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided isolation capability is maintained for either 2ICS*MOV148 or 2ICS*MOV164.

SURVEILLANCE FREQUENCY TRSR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRSR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days TRSR 3.3.6.2.3 Calibrate the trip unit. 92 days TRSR 3.3.6.2.4 Perform CHANNEL CALIBRATION. The Allowable 24 months Values shall be:

a. Drywell Pressure - High: < 1.88 psig; and

b. RCIC Steam Supply Pressure - Low:

> 70 psia.

TRSR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months NMP2 TRM 3.3-19 Rev. 2 November 2000

Area Radiation Monitoring Instrumentation TRM 3.3.7.1 TRM 3.3 INSTRUMENTATION TRM 3.3.7.1 Area Radiation Monitoring Instrumentation TLCO 3.3.7.1 The area radiation monitoring instrumentation for each alarm Function in Table T3.3.7.1-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.7.1-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore Alarm 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with Alarm Setpoint Setpoint to within not within limit. limit.

B. Required Action and B.1 Perform area surveys Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion of the monitored area Time of Condition A with portable not met. monitoring instrumentation.

OR One or more channels inoperable for reasons other than Condition A.

NMP2 TRM 3.3-20 Rev. 2 November 2000

Area Radiation Monitoring Instrumentation TRM 3.3.7.1 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------

These TRSRs apply to each Function in Table T3.3.7.1-1.

SURVEILLANCE FREQUENCY TRSR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRSR 3.3.7.1.2 Perform SOURCE CHECK. 31 days TRSR 3.3.7.1.3 Perform CHANNEL FUNCTIONAL TEST. 184 days TRSR 3.3.7.1.4 Perform CHANNEL CALIBRATION. 18 months NMP2 TRM 3.3-21 Rev. 2 November 2000

Area Radiation Monitoring Instrumentation TRM 3.3.7.1 TABLE T3.3.7.1-1 (Page 1 of 1)

Area Radiation Monitoring Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS ALARM SETPOINT

1. Criticality Monitor (New Fuel With fuel 1 < 100 mR/hr above measured Storage Vault) in the new background fuel storage vault

2. Control Room Direct Radiation At all 1 < 0.25 mR/hr above measured Monitor times background NMP2 TRM 3.3-22 Rev. 2 November 2000

Seismic Monitoring Instrumentation TRM 3.3.7.2 TRM 3.3 INSTRUMENTATION TRM 3.3.7.2 Seismic Monitoring Instrumentation TLCO 3.3.7.2 The seismic monitoring instrumentation shown in Table T3.3.7.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Seismic monitoring A.1 Restore seismic 30 days instrument channel monitoring instrument inoperable. channel to OPERABLE status.

B. Required Action A and B.1 Complete CR 10 days associated Completion evaluation of the Time not met. degraded condition, including outlining the cause of the malfunction and the plans for restoring the instrument channel to OPERABLE status.

(continued)

NMP2 TRM 3.3-23 Rev. 23 December 2007

Seismic Monitoring Instrumentation TRM 3.3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. --------NOTE---------- C.1 Restore seismic 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Actions C.1, monitoring instrument C.2, C.3, and C.4 to OPERABLE status.

shall be completed if AND this Condition is entered. C.2 Perform 5 days

TRSR 3.3.7.2.3.

One or more seismic AND monitoring Functions inoperable due to C.3 Retrieve data from actuation during a actuated instruments 10 days seismic event greater and analyze to than or equal to determine the 0.01 g. magnitude of the vibratory ground motion.

AND C.4 Prepare and submit a 10 days Special Report to the Commission pursuant to 10 CFR 50.4 describing the magnitude, frequency spectrum, and resultant effect upon unit features important to safety.

NMP2 TRM 3.3-24 Rev. 2 November 2000

Seismic Monitoring Instrumentation TRM 3.3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.3.7.2.1 -------------------NOTES------------------- 31 days

1. For Function 1, CHANNEL CHECK includes battery and trigger only.

2. For Function 3, CHANNEL CHECK does not include seismic trigger.

Perform CHANNEL CHECK.

TRSR 3.3.7.2.2 Perform CHANNEL FUNCTIONAL TEST. 184 days TRSR 3.3.7.2.3 -------------------NOTE-------------------- 18 months For Function 4, CHANNEL CALIBRATION required to be for the range: + 1 g.

Perform CHANNEL CALIBRATION.

TRSR 3.3.7.2.4 -------------------NOTE-------------------- 24 months For Function 2, CHANNEL CALIBRATION required to be for the range: +/- 1 g.

Perform CHANNEL CALIBRATION.

NMP2 TRM 3.3-25 Rev. 7 January 2002

Seismic Monitoring Instrumentation TRM 3.3.7.2 TABLE T3.3.7.2-1 (Page 1 of 1)

Seismic Monitoring Instrumentation REQUIRED CHANNELS SURVEILLANCE MEASUREMENT FUNCTION PER FUNCTION REQUIREMENTS RANGE

1. Triaxial Time-History Accelerographs and Trigger

a. Reactor Bldg. Mat. El. 175-0 1 TRSR 3.3.7.2.1 0 + 1.0 g TRSR 3.3.7.2.2 TRSR 3.3.7.2.3

b. Reactor Bldg. Refueling Floor 1 TRSR 3.3.7.2.1 0 + 1.0 g El. 353-10 TRSR 3.3.7.2.2 TRSR 3.3.7.2.3

c. Control Bldg. Mat. El. 214-0 1 TRSR 3.3.7.2.1 0 + 1.0 g TRSR 3.3.7.2.2 TRSR 3.3.7.2.3

2. Triaxial Peak Accelerographs

a. Diesel Generator Bldg. Service 1 TRSR 3.3.7.2.4 0 - 5 g Water Piping

b. Prim. Cont. High Pr. Core Spray 1 TRSR 3.3.7.2.4 0 - 10 g Piping

c. Prim. Cont. Reactor Pedestal 1 TRSR 3.3.7.2.4 0 - 10 g

3. Triaxial Seismic Switches Reactor Bldg. Mat. El. 175-0 1 with control room TRSR 3.3.7.2.1 0.025 - 0.25 g annunciation TRSR 3.3.7.2.2 (adjustable)

TRSR 3.3.7.2.3

4. Triaxial Response-Spectrum Recorders

a. Reactor Bldg. Mt. El. 175-0 1 with control room TRSR 3.3.7.2.1 0 + 2 g annunciation TRSR 3.3.7.2.2 TRSR 3.3.7.2.3

b. Prim. Cont. RHR Piping Pene. 1 TRSR 3.3.7.2.3 0 + 2 g El. 294-6

c. Reactor Bldg. Refueling Fl. El. 1 TRSR 3.3.7.2.3 0 + 2 g 353-10

d. Control Bldg. Mat. El. 214-0 1 TRSR 3.3.7.2.3 0 + 2 g NMP2 TRM 3.3-26 Rev. 7 January 2002

Traversing In-Core Probe (TIP) System TRM 3.3.7.3 TRM 3.3 INSTRUMENTATION TRM 3.3.7.3 Traversing In-Core Probe (TIP) System TLCO 3.3.7.3 Five TIP subsystems shall be OPERABLE.

APPLICABILITY: During recalibration of the LPRM detectors, When monitoring APLHGR, LHGR, MCPR, or MFLPD using the TIP system.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two TIP A.1 Suspend use of the Immediately subsystem(s) inoperable TIP inoperable. subsystem(s) for recalibration of the LPRM detectors.

AND DRAFT A.2 Suspend use of the Immediately inoperable TIP subsystem(s) for monitoring the APLHGR, LHGR, MCPR, and MFLPD in the measurement locations REV 0 associated with the inoperable TIP subsystem.

B. Three or more TIP B.1 Suspend use of the Immediately subsystems inoperable. TIP system for recalibration of the LPRM detectors.

AND B.2 Suspend use of the Immediately inoperable TIP subsystems for monitoring the APLHGR, LHGR, MCPR, and MFLPD in the measurement locations associated with the inoperable TIP subsystems.

NMP2 TRM 3.3-27 Rev.48 March 2022

Traversing In-Core Probe (TIP) System TRM 3.3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.3.7.3.1 Normalize each TIP detector output. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use for calibration of the LPRM detectors DRAFT REV 0 NMP2 TRM 3.3-27a Rev. 8 March 2002

Deleted TRM 3.3.7.4 TRM 3.3 INSTRUMENTATION TRM 3.3.7.4 Deleted NMP2 TRM 3.3-28 Rev. 19 February 2006

Deleted TRM 3.3.7.4 NMP2 TRM 3.3-29 Rev. 19 February 2006

Service Water System Instrumentation TRM 3.3.9 TRM 3.3 INSTRUMENTATION TRM 3.3.9 Service Water System Instrumentation TLCO 3.3.9 The Service Water System Instrumentation channels shown in Table T3.3.9-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE-----------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table T3.3.9-1 for the channel.

B. As required by B.1 Verify discharge bay Once per hour Required Action A.1 level < 275 ft and referenced in elevation.

Table T3.3.9-1.

C. Required Action and C.1 Provide an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion discharge flow path Time of Condition B by closing not met. 2SWP*MOV30A or 2SWP*MOV30B.

D. As required by D.1 Verify water Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action A.1 temperature of the and referenced by intake tunnels Table T3.3.9-1. > 38o F.

(continued)

NMP2 TRM 3.3-30 Rev. 40 April 2018

Service Water System Instrumentation TRM 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Place intake heaters 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion in service.

Time of Condition D not met. OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months E.2 Enter the Conditions and Required Actions of Technical Specification 3.7.1, Service Water System and Ultimate Heat Sink, or TRM Specification 3.7.1, Plant Service Water System - Shutdown, as applicable.

F. As required by F.1 Verify service water Once per hour Required Action A.1 bay level > 234 ft and referenced by elevation.

Table T3.3.9-1.

G. Required Action and G.1 Provide an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion inlet flow path to Time of Condition F the service water not met. intake bay by opening 2SWP*MOV77A or 2SWP*MOV77B.

H. As required by H.1 Upon startup of the Immediately Required Action A.1 pump, follow Required and referenced by Action I.1 Table T3.3.9-1 for a pump in standby.

I. As required by I.1 Verify affected Once per hour Required Action A.1 strainer differential and referenced by pressure < 10 psid.

Table T3.3.9-1 for an operating pump.

(continued)

NMP2 TRM 3.3-31 Rev. 28 March 2010

Service Water System Instrumentation TRM 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. Required Action and J.1 Manually initiate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion backwash of the Time of Condition I affected strainer.

not met.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months J.2 Declare the affected service water pump inoperable.

K. As required by K.1 Close 2SWP*MOV95A or 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action A.1 2SWP*MOV95B.

and referenced by AND Table T3.3.9-1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months K.2 Declare Division 3 DG inoperable.

NMP2 TRM 3.3-32 Rev. 28 March 2010

Service Water System Instrumentation TRM 3.3.9 SURVEILLANCE REQUIREMENTS

NOTES--------------------------------------

1. Refer to Table T3.3.9-1 to determine which TRSRs apply to each Service Water System Instrumentation Function.

2. When a Function 1 or 3 channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. When a Function 2, 4, 5, 6, or 7 channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEILLANCE FREQUENCY TRSR 3.3.9.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRSR 3.3.9.2 Perform CHANNEL CHECK. 7 days TRSR 3.3.9.3 Perform CHANNEL FUNCTIONAL TEST. 24 months TRSR 3.3.9.4 Perform CHANNEL CALIBRATION. 24 months TRSR 3.3.9.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months NMP2 TRM 3.3-33 Rev. 2 November 2000

Service Water System Instrumentation TRM 3.3.9 TABLE T3.3.9-1 (Page 1 of 1)

Service Water System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER REQUIRED SURVEILLANCE FUNCTION ACTION A.1 REQUIREMENTS ALLOWABLE VALUE FUNCTION AND INSTRUMENT NUMBER

1. Service Water Discharge 2 B TRSR 3.3.9.3 < 275 ft 23/4 inches Bay Level (2SWP*LS30A, B) TRSR 3.3.9.4 elevation TRSR 3.3.9.5

2. Service Water Intake Tunnel 1 and 2 Water Temperature

a. Tunnel 1 2 D TRSR 3.3.9.2 > 38o F (2SWP*TSL64A, 64B) TRSR 3.3.9.3 TRSR 3.3.9.4 TRSR 3.3.9.5

b. Tunnel 2 2 D TRSR 3.3.9.2 > 38o F (2SWP*TSL65A, 65B) TRSR 3.3.9.3 TRSR 3.3.9.4 TRSR 3.3.9.5

3. Service Water Intake Bay 2 F TRSR 3.3.9.3 > 233 ft 11/4 inches Level (2SWP*LS73A, B) TRSR 3.3.9.4 elevation TRSR 3.3.9.5

4. Service Water Pumps 1 per H,I TRSR 3.3.9.1 < 14.5 psid Discharge Strainer strainer TRSR 3.3.9.3 Differential Pressure - TRSR 3.3.9.4 Division 1 TRSR 3.3.9.5 (2SWP*PDSH1A, C, E)

5. Service Water Pumps 1 per H,I TRSR 3.3.9.1 < 14.5 psid Discharge Strainer strainer TRSR 3.3.9.3 Differential Pressure - TRSR 3.3.9.4 Division 2 TRSR 3.3.9.5 (2SWP*PDSH1B, D, F)

6. Service Water Inlet 1 per K TRSR 3.3.9.3 > 17.5 psig Pressure for Division 3 division TRSR 3.3.9.4 DG (2SWP*PSL95A, 95B) TRSR 3.3.9.5

7. Service Water Inlet 1 per K TRSR 3.3.9.3 > 71.7 seconds and Pressure for Division 3 division TRSR 3.3.9.4 < 94.2 seconds DG timer (2-2SWPA26, TRSR 3.3.9.5 2-2SWPB26)

NMP2 TRM 3.3-34 Rev. 28 March 2010

Meteorological Monitoring Instrumentation TRM 3.3.10 TRM 3.3 INSTRUMENTATION TRM 3.3.10 Meteorological Monitoring Instrumentation TLCO 3.3.10 The Meteorological Monitoring Instrumentation channels shown in Table T3.3.10-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Complete CR 10 days associated Completion evaluation of the Time not met. degraded condition, including outlining the cause of the inoperability, and the plans and schedule for restoring the channel to OPERABLE status.

NMP2 TRM 3.3-35 Rev. 23 December 2007

Meteorological Monitoring Instrumentation TRM 3.3.10 SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------

These TRSRs apply to each Function in Table T3.3.10-1.

SURVEILLANCE FREQUENCY TRSR 3.3.10.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRSR 3.3.10.2 Perform CHANNEL CALIBRATION. 184 days NMP2 TRM 3.3-36 Rev. 2 November 2000

Meteorological Monitoring Instrumentation TRM 3.3.10 TABLE T3.3.10-1 (Page 1 of 1)

Meteorological Monitoring Instrumentation Function Required Channels per Function

1. Wind Speed

a. 30 ft 1

b. 200 ft 1

2. Wind Direction

a. 30 ft 1

b. 200 ft 1

3. Air Temperature Difference (30/200 ft) 1 NMP2 TRM 3.3-37 Rev. 2 November 2000

Offgas System Explosive Gas Monitoring TRM 3.3.11 TRM 3.3 INSTRUMENTATION TRM 3.3.11 Offgas System Explosive Gas Monitoring TLCO 3.3.11 One Offgas System Explosive Gas Monitoring system hydrogen monitoring channel shall be OPERABLE for each operating offgas recombiner.

APPLICABILITY: During offgas system operation.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required monitoring A.1 Perform TRSR 3.7.8.1 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channel inoperable using the common during single train hydrogen analyzer.

operation.

OR Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months A.2 Perform TRSR 3.7.8.1 using grab sample analysis.

AND 30 days A.3 Restore hydrogen monitoring channel to OPERABLE status.

(continued)

NMP2 TRM 3.3-38 Rev. 14 February 2004

Offgas System Explosive Gas Monitoring TRM 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or both required B.1 Perform TRSR 3.7.8.1 Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months monitoring channel(s) for the train(s) with inoperable during two inoperable monitoring train operation. channel(s) using the common hydrogen concentration and approved methodology.

AND 30 days B.2 Restore hydrogen monitoring channel to OPERABLE status.

C. Required Action A.3 or C.1 Explain in the next In accordance with B.2 and associated Radioactive Effluent Technical Completion Time not Release Report the Specification met. reason for the 5.6.3 inoperability not being corrected in a timely manner.

NMP2 TRM 3.3-39 Rev. 23 December 2007

RCS Chemistry TRM 3.4.1 TRM 3.4 REACTOR COOLANT SYSTEM TRM 3.4.1 Reactor Coolant System (RCS) Chemistry TLCO 3.4.1 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table T3.4.1-1.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS chemistry not A.1 Determine chlorides Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months within limits in and pH. upon discovery of MODE 1. conductivity not AND within limit A.2 Perform TRSR 3.4.1.3. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months upon discovery of conductivity not within limit AND A.3 Restore RCS chemistry to within limits. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND

NOTE-------

Only applicable to conductivity and chloride concentration.

336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months cumulative in the past 365 days B. Required Action A.3 B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time not met.

(continued)

NMP2 TRM 3.4-1 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. -------NOTE------- C.1 Determine chlorides Not applicable during Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and pH.

Noble Metal Chemical upon discovery of Addition (NMCA). conductivity not within limit

AND C.2 Perform TRSR 3.4.1.3.

RCS chemistry not Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limits in upon discovery of MODE 2 or 3. conductivity not within limit AND C.3 Restore RCS chemistry to within limits.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months D. -------NOTE-------

Only applicable in D.1 Determine chlorides Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MODES 2 and 3 during and pH. upon discovery of NMCA. conductivity not

within limit AND Conductivity > 2.0 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D.2 Perform TRSR 3.4.1.3.

and 20 mho/cm upon discovery of at 25°C conductivity not within limit AND OR

NOTE-------

4.3 pH < 5.6 NMCA may continue provided RCS chemistry can be returned to within OR limits within the Completion Time.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 8.6 < pH 9.9 D.3 Restore applicable RCS chemistry parameter to within limits.

(continued)

NMP2 TRM 3.4-2 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. -------NOTE------- E.1 Determine chlorides Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Only applicable in and pH. upon discovery of MODES 2 and 3 during conductivity not NMCA. within limit AND Chlorides > 0.1 ppm. E.2 Perform TRSR 3.4.1.3. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months upon discovery of conductivity not AND within limit

NOTE-------

NMCA may continue provided chlorides can be returned to within limits within the Completion Time.

E.3 Restore chlorides 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limits.

F. Required Action C.3, F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D.3 or E.3 and AND associated Completion Time not met. F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR

NOTE-------

Not applicable during NMCA.

Conductivity

> 10 µmho/cm at 25oC in MODE 1, 2 or 3.

OR Chloride concentration

> 0.5 ppm in MODE 1, 2 or 3.

(continued)

NMP2 TRM 3.4-3 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. -------NOTE------- G.1 Determine chlorides Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Not applicable during and pH. upon discovery of NMCA. conductivity not

AND within limit Conductivity or pH not within limits in other than MODES 1, 2, and G.2 Perform TRSR 3.4.1.3. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

3. upon discovery of conductivity not AND within limit G.3 Restore applicable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months RCS chemistry parameter to within limits.

H. -------NOTE------- H.1 Restore chloride 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Not applicable during concentration to NMCA. within limits.

Chloride concentration not within limits in other than MODES 1, 2, and 3.

(continued)

NMP2 TRM 3.4-4 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. -------NOTE------- I.1 Determine chlorides Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Only applicable in and pH. upon discovery of other than MODES 1, 2 conductivity not or 3 during NMCA. within limit AND Conductivity > 10.0 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I.2 Perform TRSR 3.4.1.3.

upon discovery of and 20 mho/cm conductivity not at 25°C within limit AND OR

NOTE-------

NMCA may continue 4.3 pH < 5.3 provided RCS chemistry can be returned to within OR limits within the Completion Time.

8.6 < pH 9.9 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months I.3 Restore applicable RCS chemistry parameter to within limits.

J. -------NOTE------- -------NOTE-------

Only applicable in NMCA may continue other than MODES 1, 2 provided chlorides or 3 during NMCA. can be returned to

within limits within the Completion Time.

Chlorides > 0.5 ppm.

J.1 Restore chlorides 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to within limits.

(continued)

NMP2 TRM 3.4-5 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. --------NOTE---------- K.1 Determine, by Prior to entering Required Action K.1 engineering MODE 2 or 3 shall be completed if evaluation, that the this Condition is structural integrity entered. of the reactor

coolant system remains acceptable Required Action G.3 or for continued H.1 and associated operation.

Completion Time not met.

L. -------NOTES------- L.1 Suspend NMCA. Immediately

1. Only applicable during NMCA in other than MODE 1. AND

2. Required Action L.3 shall be completed if this Condition L.2 Restore the Immediately is entered. applicable RCS

chemistry parameter to within the limits provided in this Conductivity > 20 Condition.

mho/cm at 25°C AND OR Prior to entering pH < 4.3 MODE 2 or 3 L.3 Determine, by engineering evaluation, that the AND OR structural integrity of the reactor coolant system Prior to pH > 9.9 remains acceptable recommencing NMCA.

for continued operation.

OR Required Action I.3 or J.1 and associated Completion Time not met.

NMP2 TRM 3.4-6 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.4.1.1 -------------------NOTE--------------------

Only required to be met when the continuous recording conductivity monitor is inoperable.

Once within Obtain an in-line conductivity measurement 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and every of the reactor coolant. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter when in MODE 1, 2, or 3

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter when in other than MODES 1, 2, and 3 TRSR 3.4.1.2 Analyze a sample of the reactor coolant for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chlorides, conductivity, and pH.

TRSR 3.4.1.3 Perform a CHANNEL CHECK of the continuous 7 days conductivity monitor with an in-line flow cell.

NMP2 TRM 3.4-7 Rev. 2 November 2000

RCS Chemistry TRM 3.4.1 TABLE T3.4.1-1 (Page 1 of 1)

Reactor Coolant Chemistry Limits CONDUCTIVITY MODE CHLORIDES (µmhos/cm @25oC) pH 1 < 0.2 ppm < 1.0 5.6 < pH < 8.6 2 and 3 < 0.1 ppm < 2.0 5.6 < pH < 8.6 At all other times < 0.5 ppm < 10.0 5.3 < pH < 8.6 NMP2 TRM 3.4-8 Rev. 2 November 2000

Structural Integrity TRM 3.4.2 TRM 3.4 REACTOR COOLANT SYSTEM TRM 3.4.2 Structural Integrity TLCO 3.4.2 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where relief or an alternative has been granted by the Commission.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Structural integrity A.1 Initiate action to Immediately of Class 1 components maintain RCS not conforming as temperature < 50o F required. above minimum temperature required by NDT considerations.

Immediately OR A.2 Initiate action to isolate affected component(s).

B. Structural integrity B.1 Initiate action to Immediately of Class 2 components maintain RCS not conforming as temperature < 200o F.

required.

OR Immediately B.2 Initiate action to isolate affected component(s).

C. Structural integrity C.1 Initiate action to Immediately of Class 3 components isolate affected not conforming as components.

required.

(continued)

NMP2 TRM 3.4-9 Rev. 10 August 2002

Structural Integrity TRM 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.4.2.1 Perform required inspection and testing in In accordance accordance with Section XI of the ASME with ASME Section Boiler and Pressure Vessel Code and XI, as modified applicable addenda as required by by approved 10 CFR 50.55a, except where relief or an relief or alternative has been granted by the alternative Commission.

NMP2 TRM 3.4-10 Rev. 10 August 2002

Pressure Isolation Valves TRM 3.4.6 TRM 3.4 REACTOR COOLANT SYSTEM TRM 3.4.6 Pressure Isolation Valves TLCO 3.4.6 The following monitors associated with the Pressure Isolation Valves (PIVs) shall be OPERABLE:

a. The Reactor Coolant System Interface Valves - Leakage Pressure Monitors in Table T3.4.6-2.

NOTE----------------------------

The Reactor Coolant System Pressure Isolation Valves are listed in Table T3.4.6-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each monitor.

A. DRAFT CONDITION One or more required Table T3.4.6-2 pressure monitors inoperable.

A.1 OR REQUIRED ACTION Restore inoperable monitor to OPERABLE status.

COMPLETION TIME 7 days REV 0 A.2 Verify the pressure to be less than the alarm setpoint.

7 days AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter NMP2 TRM 3.4-11 Rev. 38 October 2017

Pressure Isolation Valves TRM 3.4.6 Page intentionally deleted.

DRAFT REV 0 NMP2 TRM 3.4-12 Rev. 38 October 2017

Pressure Isolation Valves TRM 3.4.6 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------

Refer to Table T3.4.6-2 to determine which TRSRs apply for each monitor.

SURVEILLANCE FREQUENCY TRSR 3.4.6.1 Perform CHANNEL FUNCTIONAL TEST. 31 days TRSR 3.4.6.2 Deleted TRSR 3.4.6.3 Perform CHANNEL CALIBRATION. 24 months NMP2 TRM 3.4-13 Rev. 30 April 2010

Pressure Isolation Valves TRM 3.4.6 TABLE T3.4.6-1 (Page 1 of 1)

Reactor Coolant System Pressure Isolation Valves VALVE NUMBER SYSTEM 2CSH*V108 HPCS 2CSH*MOV107 HPCS 2CSL*V101 LPCS 2CSL*MOV104 LPCS 2ICS*V156 RCIC 2ICS*V157 RCIC 2RHS*V16A, B, C RHR 2RHS*V39A, B RHR 2RHS*MOV24A, B, C RHR 2RHS*MOV40A, B RHR 2RHS*MOV67A, B RHR 2RHS*MOV104 RHR 2RHS*MOV112 RHR 2RHS*MOV113 RHR NMP2 TRM 3.4-14 Rev. 30 April 2010

Pressure Isolation Valves TRM 3.4.6 TABLE T3.4.6-2 (Page 1 of 1)

Reactor Coolant System Interface Valves - Leakage Pressure Monitors Instrument Number Valve Number Setpoint (psig) Surveillance Requirements 2RHS*PSX7A(a) 2RHS*MOV24A 475 + 6 TRSR 3.4.6.1 2RHS*MOV40A TRSR 3.4.6.3 2RHS*PSX7B(a) 2RHS*MOV24B 475 + 6 TRSR 3.4.6.1 2RHS*MOV40B TRSR 3.4.6.3 2RHS*MOV104 2RHS*PSX7C(a) 2RHS*MOV24C 475 + 6 TRSR 3.4.6.1 TRSR 3.4.6.3 2CSL*PS108 2CSL*MOV104 525 + 6 TRSR 3.4.6.1 TRSR 3.4.6.3 2RHS*PS111(a) 2RHS*MOV112 171 + 6 TRSR 3.4.6.1 2RHS*MOV113 TRSR 3.4.6.3 (a) Pressure switch has process indication.

NMP2 TRM 3.4-15 Rev. 30 April 2010

RCS Specific Activity TRM 3.4.8 TRM 3.4 REACTOR COOLANT SYSTEM TRM 3.4.8 Reactor Coolant System (RCS) Specific Activity The following Surveillance Requirements associated with the RCS Specific Activity shall be performed.

APPLICABILITY: MODE 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.4.8.1 Perform an isotopic analysis of an offgas 31 days sample including quantitative measurements for at least Xe-133, Xe-135, and Kr-88.

NMP2 TRM 3.4-16 Rev. 30 April 2010

ECCS RESPONSE TIME TRM 3.5.1 TRM 3.5 EMERGENCY CORE COOLING SYSTEMS TRM 3.5.1 Emergency Core Cooling Systems (ECCS) RESPONSE TIME The ECCS RESPONSE TIMES for Technical Specification SR 3.5.1.8 and SR 3.5.2.8 are listed in Table T3.5.1-1.

TABLE T3.5.1-1 (Page 1 of 1)

ECCS RESPONSE TIMES Response Time FUNCTION (seconds)

1. Low Pressure Core Spray System(c)

a. Diesel Generator Start Time < 10(a)

b. Injection Valve Opening Time < 20(b)

2. Low Pressure Coolant Injection Mode of RHR System (Division 1 and Division 2)(c)

a. Diesel Generator Start Time < 10(a)

b. Injection Valve Opening Time < 20(b)

3. Not used

4. High Pressure Core Spray System(c) < 27 (a) Time to rated speed and voltage upon receipt of start signal.

(b) Time from receipt of open signal to full open.

(c) ECCS actuation instrumentation is eliminated from response time testing (RTT). Time delay relays in the RTT loops require response verification through calibration. Sensor response to a process step function shall be < 5 seconds.

NMP2 TRM 3.5-1 Rev. 40 April 2018

Primary Containment Isolation Valves TRM 3.6.1 TRM 3.6 CONTAINMENT SYSTEMS TRM 3.6.1 Primary Containment Isolation Valves

1. The Primary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions for Technical Specifications SR 3.6.1.3.2 and SR 3.6.1.3.3 are listed in Table T3.6.1-1.

2. The Primary Containment Isolation Valves and, if applicable, valve groups, isolation signals, and isolation times are listed in Table T3.6.1-2.

NMP2 TRM 3.6-1 Rev. 2 November 2000

Primary Containment Isolation Valves TRM 3.6.1 TABLE T3.6.1-1 (Page 2 of 5)

Primary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Manual Valves for Technical Specifications SR 3.6.1.3.2 (continued) 2ICS*V258 2ISC*V130 2ISC*V77 2MSS*V213C 2ICS*V259 2ISC*V131 2ISC*V80 2MSS*V213D 2ICS*V260 2ISC*V132 2ISC*V81 2MSS*V372A 2ICS*V268 2ISC*V133 2ISC*V82 2MSS*V372B 2ICS*V288 2ISC*V134 2ISC*V83 2MSS*V372C 2ISC*V100 2ISC*V136 2ISC*V84 2MSS*V372D 2ISC*V101 2ISC*V48 2ISC*V85 2MSS*V373A 2ISC*V102 2ISC*V49 2ISC*V86 2MSS*V373B 2ISC*V103 2ISC*V50 2ISC*V87 2MSS*V373C 2ISC*V104 2ISC*V51 2ISC*V90 2MSS*V373D 2ISC*V105 2ISC*V52 2ISC*V91 2MSS*V383A 2ISC*V106 2ISC*V53 2ISC*V92 2MSS*V383B 2ISC*V107 2ISC*V54 2ISC*V93 2MSS*V383C 2ISC*V108 2ISC*V55 2ISC*V94 2MSS*V383D 2ISC*V109 2ISC*V56 2ISC*V95 2MSS*V384A 2ISC*V110 2ISC*V57 2ISC*V96 2MSS*V384B 2ISC*V111 2ISC*V58 2ISC*V97 2MSS*V384C 2ISC*V112 2ISC*V59 2ISC*V98 2MSS*V384D 2ISC*V113 2ISC*V60 2ISC*V99 2RCS*V100A 2ISC*V114 2ISC*V61 2MSS*V19 2RCS*V100B 2ISC*V115 2ISC*V62 2MSS*V20 2RCS*V101A 2ISC*V116 2ISC*V63 2MSS*V210A 2RCS*V101B 2ISC*V117 2ISC*V64 2MSS*V210B 2RCS*V102A 2ISC*V118 2ISC*V65 2MSS*V210C 2RCS*V102B 2ISC*V119 2ISC*V66 2MSS*V210D 2RCS*V103A 2ISC*V120 2ISC*V67 2MSS*V211A 2RCS*V103B 2ISC*V121 2ISC*V68 2MSS*V211B 2RCS*V160A 2ISC*V122 2ISC*V69 2MSS*V211C 2RCS*V160B 2ISC*V123 2ISC*V70 2MSS*V211D 2RCS*V161A 2ISC*V124 2ISC*V71 2MSS*V212A 2RCS*V161B 2ISC*V125 2ISC*V72 2MSS*V212B 2RCS*V39A 2ISC*V126 2ISC*V73 2MSS*V212C 2RCS*V39B 2ISC*V127 2ISC*V74 2MSS*V212D 2RCS*V40A 2ISC*V128 2ISC*V75 2MSS*V213A 2RCS*V40B 2ISC*V129 2ISC*V76 2MSS*V213B 2RCS*V41A NMP2 TRM 3.6-3 Rev. 2 November 2000

Primary Containment Isolation Valves TRM 3.6.1 TABLE T3.6.1-1 (Page 3 of 5)

Primary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Manual Valves for Technical Specifications SR 3.6.1.3.2 (continued) 2RCS*V41B 2RHS*V342 2RHS*V72 2RCS*V42A 2RHS*V349 2SAS*HCV160(a) 2RCS*V42B 2RHS*V350 2SAS*HCV161(a) 2RCS*V72A 2RHS*V351 2SFC*V203(a) 2RCS*V72B 2RHS*V352 2SFC*V262 2RCS*V75A 2RHS*V357 2SFC*V263 2RCS*V75B 2RHS*V358 2SLS*V30 2RCS*V77A 2RHS*V359 2SLS*V31 2RCS*V77B 2RHS*V398 2WCS*V148 2RCS*V78A 2RHS*V399 2WCS*V149 2RCS*V78B 2RHS*V402 2WCS*V155 2RHS*V115 2RHS*V403 2WCS*V156 2RHS*V116 2RHS*V405 2WCS*V240 2RHS*V157 2RHS*V411 2WCS*V241 2RHS*V185 2RHS*V412 2WCS*V242 2RHS*V187 2RHS*V413 2WCS*V243 2RHS*V192(a) 2RHS*V414 2WCS*V244 2RHS*V233 2RHS*V415 2WCS*V245 2RHS*V234 2RHS*V416 2WCS*V323 2RHS*V266 2RHS*V417 2WCS*V324 2RHS*V267 2RHS*V418 2WCS*V325 2RHS*V268 2RHS*V43 2WCS*V326 2RHS*V269 2RHS*V431 2RHS*V278 2RHS*V44 2RHS*V279 2RHS*V45 2RHS*V280 2RHS*V46 2RHS*V281 2RHS*V53 2RHS*V317 2RHS*V62 2RHS*V318 2RHS*V63 2RHS*V323 2RHS*V64 2RHS*V324 2RHS*V65 2RHS*V333 2RHS*V66 2RHS*V334 2RHS*V67 2RHS*V335 2RHS*V68 2RHS*V336 2RHS*V69 2RHS*V341 (a) Normally locked closed.

NMP2 TRM 3.6-4 Rev. 2 November 2000

Primary Containment Isolation Valves TRM 3.6.1 TABLE T3.6.1-1 (Page 4 of 5)

Primary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Blind Flanges and Plugs for Technical Specification SR 3.6.1.3.2 Component ID Reference Comments Drawing FPW NA NA Blind Flange Z74 FPW NA NA Blind Flange Z46C Z14 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z14 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z16 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z16 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z21B PLUG EV-1L-9 315 Degrees Off Top Dead Center Z21B PLUG EV-1L-9 45 Degrees Off Top Dead Center Z22 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z22 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z24 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z24 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z29 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z29 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z67 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z67 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z68 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z68 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z69 PLUG EV-1L-9 315 Degrees Off Top Dead Center Z69 PLUG EV-1L-9 45 Degrees Off Top Dead Center Z9A PLUG EV-1L-9 315 Degrees Off Top Dead Center Z9A PLUG EV-1L-9 45 Degrees Off Top Dead Center Z9B PLUG EV-1L-9 315 Degrees Off Top Dead Center Z9B PLUG EV-1L-9 45 Degrees Off Top Dead Center Z9C PLUG EV-1L-9 315 Degrees Off Top Dead Center Z9C PLUG EV-1L-9 45 Degrees Off Top Dead Center NMP2 TRM 3.6-5 Rev. 2 November 2000

Primary Containment Isolation Valves TRM 3.6.1 TABLE T3.6.1-1 (Page 5 of 5)

Primary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Valves for Technical Specifications SR 3.6.1.3.3 Component ID Reference Drawing 2AAS*HCV136(a) PID-20E 2AAS*HCV137(a) PID-20E 2CSH*V83(a) PID-33A 2CSH*V84(a) PID-33A 2FWS*V89A(a) PID-6B 2FWS*V89B(a) PID-6B 2FWS*V90A(a) PID-6B 2FWS*V90B(a) PID-6B 2SAS*HCV162(a) PID-19J 2SAS*HCV163(a) PID-19J 2ICS*V182(a) PID-35A 2ICS*V183(a) PID-35A 2ICS*V185(b) PID-35C 2ICS*V186(b) PID-35C 2RCS*V83A(a) PID-29B 2RCS*V83B(a) PID-29C 2RCS*V84A(a) PID-29B 2RCS*V84B(a) PID-29C 2RHS*V209(a) PID-31A 2RHS*V210(a) PID-31A 2RHS*V211(a) PID-31A 2RHS*V212(a) PID-31A 2RHS*V220(a) PID-31A 2RHS*V221(a) PID-31A 2SFC*V204(a) PID-38C (a) Normally locked closed.

(b) Normally sealed closed.

NMP2 TRM 3.6-6 Rev. 3 February 2001

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 2 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

A. AUTOMATIC (continued) 2DFR*MOV120 DFR Drain Tank Line Outside IV 8 B,F,Z,RM 45 2DFR*MOV121 DFR Drain Tank Line Inside IV 8 B,F,Z,RM 54 2DER*MOV119 DER Line from Drywell Inside IV 8 B,F,Z,RM 35 2DER*MOV120 DER Line from Drywell Outside IV 8 B,F,Z,RM 35 2RCS*SOV104 RCS Sample Inside IV 2 B,Z,RM 5 2RCS*SOV105 RCS Sample Outside IV 2 B,Z,RM 5 2FPW*SOV218(i) RCS A Water Spray Outside IV NA NA NA 2FPW*SOV219(i) RCS A Water Spray Inside IV NA NA NA 2FPW*SOV220(i) RCS B Water Spray Outside IV NA NA NA 2FPW*SOV221(i) RCS B Water Spray Inside IV NA NA NA 2DFR*MOV139 DFR Vent Line Outside IV 8 B,F,Z,RM 20 2DFR*MOV140 DFR Vent Line Inside IV 8 B,F,Z,RM 20 2DER*MOV130 DER Vent Line Inside IV 8 B,F,Z,RM 18 2DER*MOV131 DER Vent Line Outside IV 8 B,F,Z,RM 18 2CCP*MOV265 Sply to Drywell Space Cooler 8 B,F,Z,RM 60 Outside IV 2CCP*MOV273 Sply to Drywell Space Cooler 8 B,F,Z,RM 60 Inside IV 2CCP*MOV122 Return from Drywell Space Cooler 8 B,F,Z,RM 60 Inside IV 2CCP*MOV124 Return from Drywell Space Cooler 8 B,F,Z,RM 60 Outside IV NMP2 TRM 3.6-8 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 3 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

A. AUTOMATIC (continued) 2CPS*AOV104 Purge Inlet to Drywell Outside IV 9 B,F,Y,Z,RM 5 2CPS*AOV105 Purge Inlet to Sup. Chamber 9 B,F,Y,Z,RM 5 Outside IV 2CPS*AOV106(n) Purge Inlet to Drywell Inside IV 9 B,F,Y,Z,RM 5 2CPS*AOV107(n) Purge Inlet to Sup. Chamber Inside 9 B,F,Y,Z,RM 5 IV 2CPS*AOV108(n) Purge Exhaust from Drywell Inside 9 B,F,Y,Z,RM 5 IV 2CSP*AOV109(n) Purge Exhaust from Sup. Chamber 9 B,F,Y,Z,RM 5 Inside IV 2CPS*AOV110 Purge Exhaust from Drywell Outside 9 B,F,Y,Z,RM 5 IV 2CPS*AOV111 Purge Exhaust from Sup. Chamber 9 B,F,Y,Z,RM 5 Outside IV 2IAS*SOV164 ADS Hdr A N 2 Supply Outside IV 8 B,F,Z,RM 5 2IAS*SOV165 ADS Hdr B N 2 Supply Outside IV 8 B,F,Z,RM 5 2IAS*SOV166 IAS to MSS Safety Relief Valve 8 B,F,Z,RM 5 Outside IV 2IAS*SOV184 IAS to MSS Safety Relief Valve 8 B,F,Z,RM 5 Inside IV 2IAS*SOV168 Inst. Air to Testable Check 8 B,F,Z,RM 5 Outside IV 2IAS*SOV180 Inst. Air to Testable Check Inside 8 B,F,Z,RM 5 IV 2IAS*SOV167 IAS to test Ck. & Vac. Bkrs. 8 B,F,Z,RM 5 Outside IV 2IAS*SOV185 IAS to test Ck. & Vac. Bkrs. 8 B,F,Z,RM 5 Inside IV NMP2 TRM 3.6-9 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 4 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

A. AUTOMATIC (continued) 2HCS*MOV1 A,B H 2 Recombiners Sply to Supp. 8 B,F,Z,RM 30 Chamber Outside IVs 2HCS*MOV2 A,B H 2 Recomb. Ret. from Supp. Chamber 8 B,F,Z,RM 30 Outside IVs 2HCS*MOV3 A,B H 2 Recomb. Return from Drywell 8 B,F,Z,RM 30 Outside IVs 2HCS*MOV4 A,B(q) H 2 Recomb. Sply. To Supp. Chamber 8 B,F,Z,RM 30 Inside IVs 2HCS*MOV5 A,B(n) H 2 Recomb. Ret. from Supp. Chamber 8 B,F,Z,RM 30 Inside IVs 2HCS*MOV6 A,B(q) H 2 Recomb. Ret. from Drywell Inside 8 B,F,Z,RM 30 IVs 2CPS*SOV119 Containment Purge to Supp. Chamber 9 B,F,Y,Z,RM 2 Outside IV 2CPS*SOV120 Containment Purge to Drywell 9 B,F,Y,Z,RM 2 Outside IV 2CPS*SOV121(n) Containment Purge to Supp. Chamber 9 B,F,Y,Z,RM 2 Inside IV 2CPS*SOV122(n) Containment Purge to Drywell 9 B,F,Y,Z,RM 2 Inside IV 2CMS*SOV24A,B,C,D CMS from Drywell Inside & Outside 8 B,F,Z,RM 5 IVs 2CMS*SOV26A,B,C,D CMS from SP Inside & Outside IVs 8 B,F,Z,RM 5 2CMS*SOV32 A,B CMS to Drywell Outside IVs 8 B,F,Z,RM 5 2CMS*SOV33 A,B(n) CMS to Drywell Inside IVs 8 B,F,Z,RM 5 2CMS*SOV34 A,B(n) CMS to SP Inside IVs 8 B,F,Z,RM 5 2CMS*SOV35 A,B CMS to SP Outside IVs 8 B,F,Z,RM 5 2CMS*SOV60 A,B CMS from Drywell Outside IVs 8 B,F,Z,RM 5 2CMS*SOV61 A,B(n) CMS from Drywell Inside IVs 8 B,F,Z,RM 5 2CMS*SOV62 A,B CMS to Drywell Outside IVs 8 B,F,Z,RM 5 2CMS*SOV63 A,B(n) CMS to Drywell Inside IVs 8 B,F,Z,RM 5 NMP2 TRM 3.6-10 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 6 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

A. AUTOMATIC (continued) 2GSN*SOV166 Nitrogen Purge to TIP Indexing 3 B,F,Z,RM 5 Mechanism Outside IV 2RDS*AOV124(k) SCRAM Discharge Volume Vent NA NA 2RDS*AOV132(k) SCRAM Discharge Volume Vent NA NA 2RDS*AOV123(k) SCRAM Discharge Volume Drain NA NA 2RDS*AOV130(k) SCRAM Discharge Volume Drain NA NA NMP2 TRM 3.6-12 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 7 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL ISOLATION TIME GROUP (a) (SECONDS) (p)

B. REMOTE MANUAL 2RHS*MOV15 A,B(s) Containment Spray to Drywell 12 RM NA Outside IVs 2RHS*MOV1 A,B,C RHS Pump Suction Outside IVs 12 RM NA 2RHS*MOV30 A,B RHS Test Line to SP Outside IVs 12 RM NA 2RHS*MOV25 A,B(q)(s) Containment Spray to Drywell 12 RM NA Outside IVs 2RHS*MOV24 A,B,C(s)(v) RHS/LPCI to RPV Outside IVs 12 RM NA 2CSH*MOV118 CSH Suction from SP Outside IV 12 RM NA 2CSH*MOV105 HPCS Min Flow Bypass Outside IV 12 RM NA 2CSH*MOV107(s)(v) CSH to RPV Outside IV 12 RM NA 2CSL*MOV112 CSL Suction from SP Outside IV 12 RM NA 2CSL*MOV104(s)(v) CSL to RPV Outside IV 12 RM NA 2ICS*MOV136 ICS Suction from SP Outside IV 12 RM NA 2ICS*MOV143(n) ICS Min Flow to SP Outside IV 12 RM NA 2ICS*MOV122(q) ICS Turbine Exhaust to SP Outside 12 RM NA IV 2ICS*MOV126(q)(s) ICS to RPV Outside IV 12 RM NA 2NMS*VEX1 A,B,C,D,E(d) Traversing Incore Probe Shear 12 RM NA Outside IVs 2FWS*MOV21 A,B Feedwater to RPV Outside IVs 12 RM NA 2WCS*MOV200 WCS to RPV Outside IV 12 RM NA 2RHS*MOV26 A,B(c) RHS HX Vent Inboard IVs 12 RM NA 2RHS*MOV27 A,B(c) RHS HX Vent Outboard IVs 12 RM NA 2SLS*MOV5 A,B(g) SLS to RPV Outside IV 12 RM NA NMP2 TRM 3.6-13 Rev. 41 March 2019

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 8 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

C. MANUAL 2SAS*HCV160 SAS to Drywell Outside IV NA NA NA 2SAS*HCV161 SAS to Drywell Outside IV NA NA NA 2SAS*HCV162 SAS to Drywell Inside IV NA NA NA 2SAS*HCV163 SAS to Drywell Inside IV NA NA NA 2AAS*HCV134 AAS to Drywell Outside IV NA NA NA 2AAS*HCV135 AAS to Drywell Outside IV NA NA NA 2AAS*HCV136 AAS to Drywell Inside IV NA NA NA 2AAS*HCV137 AAS to Drywell Inside IV NA NA NA 2RHS*V192 RCIC/RHS Vacuum Breaker Outside IV NA NA NA 2SFC*V203 Inner Refuel Seal Leakoff Outboard NA NA NA IV 2SFC*V204 Inner Refuel Seal Leakoff Inboard NA NA NA IV 2ICS*V288(s) Keep-Fill Between 2ICS*MOV126 and NA NA NA 2ICS*V157 NMP2 TRM 3.6-14 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 11 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

D. OTHER (continued) 2RHS*V19(d)(f) Discharge Check from RCIC to Supp. NA NA NA Pool 2RHS*V20(d)(f) Discharge Check from RCIC to Supp. NA NA NA Pool 2RHS*V117(d)(f) Check Valve from RCIC Drain to NA NA NA Supp. Pool 2RHS*V118(d)(f) Check Valve from RCIC Drain to NA NA NA Supp. Pool 2FWS*V23 A,B Feedwater to RPV Outside IVs NA NA NA 2FWS*V12 A,B Feedwater to RPV Inside IVs NA NA NA Excess Flow Check(e)

Reactor Instrumentation Lines 2ISC*EFV1 Inst. Line from MSS NA NA NA 2ISC*EFV2 Inst. Line from N14, 200° NA NA NA 2ISC*EFV3 Inst. Line from N14, 160° NA NA NA 2ISC*EFV4 Inst. Line from N13, 190° NA NA NA 2ISC*EFV5 Inst. Line from N14, 20° NA NA NA 2ISC*EFV6 Inst. Line from N14, 340° NA NA NA 2ISC*EFV7 Inst. Line from N13, 10° NA NA NA 2ISC*EFV8 Inst. Line from N12, 160° NA NA NA 2ISC*EFV10 Inst. Line from N12, 200° NA NA NA 2ISC*EFV11 To 2ISC*FT47K, FT48B NA NA NA 2ISC*EFV13 To 2ISC*FT47H NA NA NA 2ISC*EFV14 Vessel Bottom Tap, Loop A Jet Pump NA NA NA 2ISC*EFV15 Inst. Line from N12, 340° NA NA NA NMP2 TRM 3.6-17 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 12 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

D. OTHER (continued) 2ISC*EFV17 Inst. Line from N12, 20° NA NA NA 2ISC*EFV18 To 2ISC*FT47J, FT48A NA NA NA 2ISC*EFV20 To 2ISC*FT47E NA NA NA 2ISC*EFV21 Vessel Bottom Tap for CSH, RDS NA NA NA 2ISC*EFV22 Vessel Bottom Tap for WCS and NA NA NA Loop B J.P.

2ISC*EFV23 To 2ISC*FT48C and Postaccident NA NA NA Sampling 2ISC*EFV24 To 2ISC*FT48D and Postaccident NA NA NA Sampling 2ISC*EFV25 To 2ISC*FT47L NA NA NA 2ISC*EFV26 To 2ISC*FT47C NA NA NA 2ISC*EFV27 To 2ISC*FT47A NA NA NA 2ISC*EFV28 To 2ISC*FT47R NA NA NA 2ISC*EFV29 To 2ISC*FT47G NA NA NA 2ISC*EFV30 To 2ISC*FT47N NA NA NA 2ISC*EFV31 To 2ISC*FT48A NA NA NA 2ISC*EFV32 To 2ISC*FT47T NA NA NA 2ISC*EFV33 To 2ISC*FT47V, FT48C NA NA NA 2ISC*EFV34 To 2ISC*FT47B NA NA NA 2ISC*EFV35 To 2ISC*FT47D NA NA NA 2ISC*EFV36 To 2ISC*FT47F NA NA NA 2ISC*EFV37 To 2ISC*FT47S NA NA NA 2ISC*EFV38 To 2ISC*FT47M NA NA NA 2ISC*EFV39 To 2ISC*FT47P NA NA NA 2ISC*EFV40 To 2ISC*FT48B NA NA NA 2ISC*EFV41 To 2ISC*FT47U NA NA NA 2ISC*EFV42 To 2ISC*FT47W, FT48D NA NA NA 2ICS*EFV1 To 2ICS*PDT167 NA NA NA 2ICS*EFV2 To 2ICS*PDT167 NA NA NA 2ICS*EFV3 To 2ICS*PDT168 NA NA NA 2ICS*EFV4 To 2ICS*PDT168 NA NA NA 2ICS*EFV5 To 2ICS*PT142,143 NA NA NA NMP2 TRM 3.6-18 Rev. 34 August 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 13 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION SIGNAL (a) ISOLATION TIME GROUP (SECONDS) (p)

D. OTHER (continued) 2RHS*EFV 5,6 To 2RHS*PDT18B NA NA NA 2RHS*EFV7 To 2RHS*PDT18A NA NA NA 2MSS*EFV 1A,B,C,D To Flow Elements A,B,C,D NA NA NA Steamlines 2MSS*EFV 2A,B,C,D To Flow Elements A,B,C,D NA NA NA Steamlines 2MSS*EFV 3A,B,C,D To Flow Elements A,B,C,D NA NA NA Steamlines 2MSS*EFV 4A,B,C,D To Flow Elements A,B,C,D NA NA NA Steamlines 2RCS*EFV45 A,B To 2RCS*FT 7 A/B, FT 9 A/B NA NA NA 2RCS*EFV46 A,B To 2RCS*FT 7 A/B, FT 9 A/B NA NA NA 2RCS*EFV47 A,B To 2RCS*FT 6 A/B, FT 8 A/B NA NA NA 2RCS*EFV48 A,B To 2RCS*FT 6 A/B, FT 8 A/B NA NA NA 2RCS*EFV52 A,B To 2RCS*PDT 15 A/B NA NA NA 2RCS*EFV53 A,B To 2RCS*PDT 15 A/B NA NA NA 2RCS*EFV62 A,B To 2RCS*PT44 A/B NA NA NA 2RCS*EFV63 A,B To 2RCS*PT42 A/B NA NA NA 2WCS*EFV221 To 2WCS-FT 134 NA NA NA 2WCS*EFV222 To 2WCS*FT67X, PDS 115 NA NA NA 2WCS*EFV223 To 2WCS*FT67Y NA NA NA 2WCS*EFV224 To 2WCS*FT67Y NA NA NA 2WCS*EFV300 To 2WCS*FT67X, PDS 115 NA NA NA 2CSH*EFV3 To 2CSH*PDT109 NA NA NA 2CSL*EFV1 To 2CSL*PDT132 and 2RHS*PDT18A NA NA NA Excess Flow Check(e)

Other Instrumentation Lines 2ISC*EFV9 Containment Pressure NA NA NA 2ISC*PT15C,16B,16D NMP2 TRM 3.6-19 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 14 of 18)

Primary Containment Isolation Valves ISOLATION VALVE NO. VALVE FUNCTION VALVE ISOLATION ISOLATION TIME GROUP SIGNAL (a) (SECONDS) (p)

D. OTHER (continued) 2ISC*EFV12 Containment Pressure NA NA NA 2ISC*PT15B,17B,17D 2ISC*EFV16 Containment Pressure NA NA NA 2ISC*PT15A,16A,16C 2ISC*EFV19 Containment Pressure NA NA NA 2ISC*PT15D,17A,17C 2CMS*EFV1A To CMS*PT1A NA NA NA 2CMS*EFV1B To CMS*PT1B NA NA NA 2CMS*EFV3A To CMS*PT2A NA NA NA 2CMS*EFV3B To CMS*PT2B NA NA NA 2CMS*EFV5A To CMS*PT7A NA NA NA 2CMS*EFV5B To CMS*PT7B NA NA NA 2CMS*EFV6 To CMS-PT168 NA NA NA 2CMS*EFV8A To CMS*LT9A,11A,114 NA NA NA 2CMS*EFV8B To CMS*LT9B,11B,105 NA NA NA 2CMS*EFV9A To CMS*LT9A,11A,114 NA NA NA 2CMS*EFV9B To CMS*LT99B,11B,105 NA NA NA 2CMS*EFV10 To CMS-PI173 NA NA NA 2DER*EFV31 To DER*PT134 NA NA NA 2IAS*EFV200 To 2IAS*PT230 off ADS Accum. NA NA NA 2IAS*EFV201 To 2IAS*PT231 off ADS Accum. NA NA NA 2IAS*EFV202 To 2IAS*PT232 off ADS Accum. NA NA NA 2IAS*EFV203 To 2IAS*PT235 off ADS Accum. NA NA NA 2IAS*EFV204 To 2IAS*PT234 off ADS Accum. NA NA NA 2IAS*EFV205 To 2IAS*PT233 off ADS Accum. NA NA NA 2IAS*EFV206 To 2IAS*PT236 off ADS Accum. NA NA NA 2RCS*EFV44 A,B To 2RCS*PT84 A/B NA NA NA 2CSH*EFV1 To 2CSH*LT123, LT124 NA NA NA 2CSH*EFV2 To 2CSH*LT123, LT124 NA NA NA NMP2 TRM 3.6-20 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 15 of 18)

Primary Containment Isolation Valves Table Notations

Isolates on injection signal, not primary containment isolation signal.

(a) See page 17 in this Table for the key to the isolation signals.

(b) Deleted.

(c) These valves are the RHR heat exchangers vent lines isolation valves.

The vent line connects to the RHR safety relief valves (SRVs) discharge header before it penetrates the primary containment. The position indicators for these valves are provided in the Control Room for remote manual isolation.

(d) Type C leakage tests not required.

(e) The associated instrument lines shall not be isolated during Type A testing. Type C testing is not required. The reactor instrumentation line excess flow check valves shall be tested in accordance with Technical Specification SR 3.6.1.3.9.

(f) These valves are check valves, located in the vacuum breaker lines for RHR SRVs discharge headers. The SRV discharge header terminates under pool water and therefore has no containment isolation valves other than those on lines feeding into it.

(g) 2SLS*MOV5A and B are globe stop check valves. These valves close upon reverse flow. The motor operator is provided to remote manually close the valve from the Control Room.

(h) These valves are testable check valves. They close upon reverse flow.

These valves can only be tested against a zero d/p.

(i) Valves are maintained closed. The FPW lines are capped. Valves are Type C tested.

(j) Not used.

(k) Valves close on a SCRAM signal; not part of primary containment isolation system but are included here for Type C testing per Technical Specification 3.6.1.1. These valves are not required to be OPERABLE per this specification but are required to be OPERABLE per Technical Specification 3.1.8.

(l) Not subject to Type A or Type C leak test because of constant monitoring under constant 1800 psig pressure and the possible detrimental effects of shutdown.

(m) Not used.

(n) These valves are Type C tested and may be tested in the reverse direction.

(o) Deleted NMP2 TRM 3.6-21 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 16 of 18)

Primary Containment Isolation Valves (p) The maximum isolation times for primary containment automatic isolation valves listed in this Table are either the analytical times used in the accident analysis as described in the USAR; or times derived by applying margins to the vendor test data obtained in accordance with industry codes and standards or the GL 89-10 calculated time. For non-analytical automatic primary containment isolation valves, the maximum isolation time is derived as follows:

1. Valves with full stroke times less than or equal to 10 seconds, maximum isolation time approximately equals the vendor tested closure time or the GL 89-10 calculated time multiplied by 2.0.

2. Valves with full stroke times greater than 10 seconds, maximum isolation time approximately equals the vendor tested closure time or the GL 89-10 calculated time multiplied by 1.5.

3. Valve closing times do not include isolation instrumentation response time.

(q) These valves are leak tested and may be tested by pressurizing between the seats. Reference USAR Table 6.2-65.

(r) Relief Valves are Type C tested as part of 2RHS*MOV15A,B assembly.

(s) Penetrations that are associated with a closed loop outside containment only require Appendix J Type C testing of a single isolation valve inside or outside containment, provided a closed system outside containment is maintained. The closed system boundary includes the main process lines from the suppression pool or process penetration on the suction side of the associated pumps through the containment penetration on the discharge side, out to and including the first normally closed isolation valves (i.e., drain valves, interface boundary valves, relief valves, etc.). The designated closed system penetration leak tested isolation valves credited in the Appendix J Program are:

2RHS*MOV104 RHS Reactor Head Spray Outside IV (penetration Z-22) 2RHS*MOV40A,B Shutdown Cooling Return Outside IVs (penetrations Z-10A/10B) 2RHS*MOV112 SDC Supply Inside IV (penetration Z-11) 2RHS*MOV15A,B Containment Spray to Drywell Outside IVs (penetrations Z-8A/8B) 2RHS*MOV24A,B,C RHS/LPCI to RPV Outside IVs (penetrations Z-9A/9B/9C) 2CSH*MOV107 CSH to RPV Outside IV (penetration Z-14) 2CSL*MOV104 CSL to RPV Outside IV (penetration Z-16) 2ICS*MOV126 ICS to RPV Outside IV (penetration Z-22) 2ICS*V288 Keep-fill between 2ICS*MOV126 and 2ICS*V157 (penetration Z-22) 2RHS*RV152 SDC Supply from RCS RV Inside IV (penetration Z-11)

Note that for penetration Z-22, valve 2ICS*V156 may not be credited as the only tested isolation valve in conjunction with a closed loop, since it is a simple check valve outside containment which does not meet the provisions of 10CFR50, Appendix A, GDC 55.

(t) Valves are mechanically closed (gagged). Pressure source is eliminated by barrier installation as part of RHR system steam condensing mode retirement.

NMP2 TRM 3.6-22 Rev. 34 April 2016

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 17 of 18)

Primary Containment Isolation Valves (u) Automatic isolation signals to RCIC Turbine Exhaust Vacuum Breaker Line Isolation Valves 2ICS*MOV148 and 2ICS*MOV164 energize a 70-sec time delay to slow closure of these valves. The time delay is provided to ensure the exhaust steam in the turbine exhaust line has fully condensed prior to isolating the vacuum breaker line.

(v) Penetrations that are associated with a closed loop outside containment and do not constitute a potential primary containment atmospheric pathway during and following a DBA do not require Appendix J Type C testing as stated above in note (S). Pressure Isolation Valve Leakage testing of the outside containment isolation valve in water filled systems may be substituted provided a closed system outside containment is maintained and PIV testing confirms zero leakage through the penetration. This ensures that the penetration will remain filled with water during and following a DBA and therefore does not constitute a potential primary containment atmospheric pathway.

The closed system boundary includes the main process lines from the suppression pool or process penetration on the suction side of the associated pumps through the containment penetration on the discharge side, out to and including the first normally closed isolation valves (i.e., drain valves, interface boundary valves, relief valves, etc.).

The following designated closed system penetration Pressure Isolation Valves are leak tested and credited for the Appendix J Program:

2RHS*MOV40A,B Shutdown Cooling Return Outside IVs (penetrations Z-10A/10B) 2RHS*MOV113 SDC Supply Outside IV (penetration Z-11) 2CSH*MOV107 CSH to RPV Outside IV (penetration Z-14) 2CSL*MOV104 CSL to RPV Outside IV (penetration Z-16) 2RHS*MOV24A RHS/LPCI to RPV Outside Remote Manual IV (penetration Z-9A) 2RHS*MOV24B RHS/LPCI to RPV Outside Remote Manual IV (penetration Z-9B) 2RHS*MOV24C RHS/LPCI to RPV Outside Remote Manual IV (penetration Z-9C)

NMP2 TRM 3.6-22a Rev. 41 March 2019

Primary Containment Isolation Valves TRM 3.6.1 Table T3.6.1-2 (Page 18 of 18)

Primary Containment Isolation Valves Key to Isolation Signals A = Low reactor vessel water, Level 3 B = Low reactor vessel water, Level 2 C = Not used D = High main steam line flow E = High main steam line tunnel ambient temperature F = High drywell pressure G = Not used H = Low RCIC steam supply pressure J = High reactor water cleanup system equipment area ambient temperature K = Reactor core isolation cooling pipe routing area high temperature and RCIC equipment area high temperature, high steam line flow, high turbine exhaust diaphragm pressure L = High reactor vessel pressure M = High residual heat removal system equipment area ambient temperatures N = Not used P = Low main steam line turbine inlet pressure R = Low main condenser vacuum S = Standby liquid control system actuated T = High main steam line tunnel differential temperatures U = High reactor water cleanup system differential flow W = Not used X = Low reactor water level, Level 1 Y = Standby gas treatment exhaust high radiation LC = Not used RM = Remote manual switch from control room LMC= Not used Z = Manual isolation AA = Main steam line lead enclosure high ambient temperature BB = RCIC/RHR steamline flow - high CC = Reactor building high ambient temperature DD = Reactor building pipe chase high ambient temperature NMP2 TRM 3.6-23 Rev. 34 April 2016

Secondary Containment TRM 3.6.4.1 TRM 3.6 CONTAINMENT SYSTEMS TRM 3.6.4.1 Secondary Containment

1. The Secondary Containment equipment hatches for Technical Specification SR 3.6.4.1.2 are listed in Table T3.6.4.1-1.

2. The Secondary Containment access doors for Technical Specification SR 3.6.4.1.3 are listed in Table T3.6.4.1-2.

NMP2 TRM 3.6-24 Rev. 2 November 2000

Secondary Containment TRM 3.6.4.1 TABLE T3.6.4.1-1 Secondary Containment Equipment Hatches Component ID Reference Drawing Comments RF-ABN261-1 EC-32C Contains three plugs for the one opening RF-ABN261-2 EC-32C RF-ABN261-3 EC-32C RF-ABN261-4 EC-32C RF-ABS261-1 EC-32D RF-ABS261-2 EC-32D RF-ABS261-3 EC-32D RW-MST261-1 EC-32E NMP2 TRM 3.6-25 Rev. 2 November 2000

Secondary Containment TRM 3.6.4.1 TABLE T3.6.4.1-2 Secondary Containment Access Doors Reference Drawing Comments Component ID 2MDS*RR261-1 EM-2D 2MDS*RR261-2 EM-2D This Component ID contains two access doors, 2A and 2B.

2PHS*NA262-1 EM-2D Maintenance inspections are waived for NA262-1 while concrete blocks barrier is in place.

2PHS*NA262-2 EM-2D 2PHS*R240-6 EM-2C 2PHS*R240-7 EM-2C 2PHS*R261-1 EM-2D 2PHS*R261-2 EM-2D 2PHS*R261-5 EM-2D 2PHS*RS261-2 EM-2D 2PHS*RS289-1 EM-2E 2PHS*RS289-3 EM-2E 2PHS*RS306-1 EM-2H 2PHS*RS306-2 EM-2H 2PHS*RS328-1 EM-2F 2PHS*RS328-3 EM-2F 2PHS*RS353-1 EM-2G 2PHS*RS353-3 EM-2G 2PHS*RS408-1 EM-2G 2PHS*RS408-2 EM-2G 2PHS*SA262-1 EM-2D 2PHS*SA262-2 EM-2D 2PHS*SA262-3 EM-2D 2PHS*SA262-4 EM-2D 2PHS*SG261-3 EM-2D NMP2 TRM 3.6-26 Rev. 2 November 2000

Secondary Containment Isolation Valves TRM 3.6.4.2 TRM 3.6 CONTAINMENT SYSTEMS TRM 3.6.4.2 Secondary Containment Isolation Valves

1. The Secondary Containment Isolation Manual Valves and Blind Flanges Required to be Closed During Accident Conditions for Technical Specifications SR 3.6.4.2.1 are listed in Table T3.6.4.2-1.

2. The Secondary Containment automatic isolation valves and their associated isolation times for Technical Specifications SR 3.6.4.2.2 and SR 3.6.4.2.3 are listed in Table T3.6.4.2-2.

NMP2 TRM 3.6-27 Rev. 2 November 2000

Secondary Containment Isolation Valves TRM 3.6.4.2 TABLE T3.6.4.2-1 (Page 1 of 3)

Secondary Containment Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Component ID Reference Drawing Comments 2DFR-C01 PID-63E 2DFR-C02 PID-63E 2DFR-C03 PID-63E 2DFR-C04 PID-63E 2DFR-C05 PID-63D 2DFR-C06 PID-63D 2DFR-C07 PID-63D 2DFR-C08 PID-63D 2DFR-C09 PID-63C 2DFR-FC01 PID-63E 2DFR-FC02 PID-63E 2DFR-FC03 PID-63E 2DFR-FC04 PID-63E 2DFR-FC05 PID-63E 2DFR-V127(b) PID-63E 2DFR-V129 PID-63D 2DFR-V207 PID-63D 2DFR-V208 PID-63D 2DFR-V209 PID-63D 2DFR-V210 PID-63E 2DFR-V211 PID-63E 2FPW-V1010 PID-43G 2GTS*PDT5A PID-61B Bypass valve below PDT (Ref. BK-16TM)(a) 2GTS*PDT5B PID-61B Bypass valve below PDT (Ref. BK-16TM)(a) 2GTS-002-55-2 DB-315G Pipe plug in end cap (Ref. BK-16ND)

(continued)

(a) The component ID identifies the component associated with the actual item to be surveilled (the surveilled item does NOT have a Component ID). The comments identify the actual item to be surveilled.

(b) Normally locked closed.

NMP2 TRM 3.6-28 Rev. 2 November 2000

Secondary Containment Isolation Valves TRM 3.6.4.2 TABLE T3.6.4.2-1 (Page 2 of 3)

Secondary Containment Manual Valves and Blind Flanges Required to be Closed During Accident Conditions Component ID Reference Drawing Comments 2GTS-002-56-2 DB-315G Pipe plug in end cap (Ref. BK-16ND) 2HVR-002-70-4 DB-315G Pipe plug in end cap (Ref. BK-16ND) 2HVR-PDIS111 PID-52A Bypass valve for PDIS (Ref. BK-16UR)(a) 2HVR-PDIS111 EK-401BE Drain valve in 2HVR-PDIS111(L)

(Ref. BK-16UR)(a) 2HVR-PDIS111 EK-8J Plug in line 2HVR-PDIS111(L) near PDIS(a) 2HVR-PDIS112 PID-52A Bypass valve for PDIS (Ref. BK-16UR)(a) 2MSS*RE46A EP-2H Blind flange and plug, bottom thimble F-7505-C(a) 2MSS*RE46B EP-2H Blind flange and plug, bottom thimble F-7506-C(a) 2MSS*RE46C EP-2H Blind flange and plug, bottom thimble F-7507-C(a) 2MSS*RE46D EP-2H Blind flange and plug, bottom thimble F-7504-C(a) 2SFC-V319 PID-38C 2SRR-C01 EB-11A 2SRR-C02 EB-11A 2SRR-C03 EB-11A 2SRR-C04 EB-11A 2SRR-C05 EB-11A 2SRR-C06 EB-11A 2SRR-C07 EB-11A 2SRR-C08 EB-11A 2SRR-C09 EB-11B (continued)

(a) The component ID identifies the component associated with the actual item to be surveilled (the surveilled item does NOT have a Component ID). The comments identify the actual item to be surveilled.

NMP2 TRM 3.6-29 Rev. 2 November 2000

Secondary Containment Isolation Valves TRM 3.6.4.2 TABLE T3.6.4.2-2 (Page 1 of 1)

Secondary Containment Automatic Isolation Valves Component ID Damper Function Isolation Time (seconds) 2HVR*AOD1A Reactor Building Ventilation < 6 Supply Damper 2HVR*AOD1B Reactor Building Ventilation < 6 Supply Damper 2HVR*AOD9A Reactor Building Ventilation < 5 Exhaust Damper (below refuel floor) 2HVR*A0D9B Reactor Building Ventilation < 5 Exhaust Damper (below refuel floor) 2HVR*A0D10A Reactor Building Ventilation < 5 Exhaust Damper (above refuel floor) 2HVR*A0D10B Reactor Building Ventilation < 5 Exhaust Damper (above refuel floor)

NMP2 TRM 3.6-31 Rev. 2 November 2000

Standby Gas Treatment System TRM 3.6.4.3 TRM 3.6 CONTAINMENT SYSTEMS TRM 3.6.4.3 Standby Gas Treatment System Charcoal samples taken per Technical Specification 5.5.7.c for the Standby Gas Treatment System shall be verified to be within the acceptance criterion of Technical Specification 5.5.7.c within 31 days after removal.

NMP2 TRM 3.6-32 Rev. 2 November 2000

Service Water System - Shutdown TRM 3.7.1 TRM 3.7 PLANT SYSTEMS TRM 3.7.1 Service Water (SW) System - Shutdown TLCO 3.7.1 The necessary portions of the SW system needed to support equipment required to be OPERABLE shall be OPERABLE.

AND The SW supply header discharge water temperature shall be

< 84o F.

AND The necessary Divisions of the intake deicing heater system shall be OPERABLE and in operation when intake tunnel water temperature is < 38o F; each required Division shall have 14 heaters in operation in each intake structure.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required portions of A.1 Declare associated Immediately SW system inoperable. equipment inoperable.

B. SW supply header B.1 Suspend handling of Immediately discharge temperature recently irradiated fuel assemblies in

> 84o F. the secondary containment.

OR One or more required divisions of SW intake deicing heaters inoperable or not in operation, with intake tunnel water temperature < 38o F.

NMP2 TRM 3.7-1 Rev. 40 April 2018

Service Water System - Shutdown TRM 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.7.1.1 -------------------NOTE--------------------

Not required to be met if TRSR 3.7.1.5 and TRSR 3.7.1.8 satisfied.

Verify the water temperature of the intake 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months tunnels is > 38o F.

TRSR 3.7.1.2 Verify water level in the SW pump intake 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months bay is > 233.1 ft.

TRSR 3.7.1.3 Verify the water temperature of each SW 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months subsystem supply header is < 84o F.

AND 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when supply header water temperature is > 78o F TRSR 3.7.1.4 Not used.

TRSR 3.7.1.5 -------------------NOTE--------------------

Not required to be met if TRSR 3.7.1.1 satisfied.

Verify, for each intake deicer heater 31 days division, the current of each required heater feeder cable is within the limit.

(continued)

NMP2 TRM 3.7-2 Rev. 44 February 2020

Service Water System - Shutdown TRM 3.7.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TRSR 3.7.1.6 -------------------NOTE--------------------

Isolation of flow to individual components does not render SW System inoperable.

Verify each SW subsystem manual, power 31 days operated, and automatic valve in the flow path servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

TRSR 3.7.1.7 Verify each SW subsystem actuates on an 24 months actual or simulated initiation signal. staggered (48 months per division)

TRSR 3.7.1.8 -------------------NOTE--------------------

Not required to be met if TRSR 3.7.1.1 satisfied.

Verify, for each intake deicer heater 24 months division, the resistance of each required heater feeder cable and associated heater elements is within the limit.

NMP2 TRM 3.7-3 Rev. 40 April 2018

Control Room Envelope Filtration System TRM 3.7.2 TRM 3.7 PLANT SYSTEMS TRM 3.7.2 Control Room Envelope Filtration System Charcoal samples taken per Technical Specification 5.5.7.c for the Control Room Envelope Filtration System shall be verified to be within the acceptance criterion of Technical Specification 5.5.7.c within 31 days after removal.

NMP2 TRM 3.7-4 Rev. 2 November 2000

Snubbers TRM 3.7.3 TRM 3.7 PLANT SYSTEMS TRM 3.7.3 Snubbers TLCO 3.7.3 All required snubbers shall be functional.

NOTE---------------------------

Not required for those snubbers installed on non-safety related systems if their failure, or failure of their associated system(s), would not adversely impact any safety related system.

APPLICABILITY: MODES 1, 2, and 3, MODES 4 and 5 for snubbers located on systems required OPERABLE in these MODES.

ACTIONS

NOTES--------------------------------------

1. The TS LCO 3.0.8 allowance cannot be used for snubbers with only a non-seismic function.

2. Separate Condition entry is allowed for each snubber.

CONDITION REQUIRED ACTION COMPLETION TIME

--NOTE- --------

Condition A applies to the operability of the supported system from the start of removal of a snubber from the system until a replacement snubber has been installed.

A. One or more required A.1 Declare the supported Immediately snubbers removed from its supported system system inoperable.

during inservice OR inspection.

A.2 Replace or restore In accordance with snubber to functional time limit imposed status. by TS LCO 3.0.8 evaluation (continued)

NMP2 TRM 3.7-5 Rev. 24 January 2008

Snubbers TRM 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

--NOTE- --------

Required Action B.1.2 or B.2, as applicable, shall be completed if this Condition is entered.

B. One or more required B.1.1 Initiate an Immediately snubbers found non- Operability functional during Determination for the bench testing as part supported system.

of inservice inspection. AND B.1.2 Perform an Prior to closing engineering the Operability evaluation on the Determination supported system per Snubber Program Plan.

OR B.2 Perform an engineering evaluation on the In accordance with supported component time limit imposed per Snubber Program by TS LCO 3.0.8 Plan. evaluation C. One or more required C.1.1 ---------NOTE--------

snubbers non- Required Action C.1.2 functional for shall be completed if reasons other than Required Action C.1.1 Condition A or B. is performed.

Declare the supported Immediately system inoperable.

AND (continued)

NMP2 TRM 3.7-6 Rev. 41 March 2019

Snubbers TRM 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.1.2 Perform an Prior to declaring engineering the supported evaluation on the system OPERABLE supported system per Snubber Program Plan.

OR C.2 Replace or restore snubber to functional status. In accordance with time limit imposed by TS LCO 3.0.8 evaluation D. Required Action and D.1 Declare the supported Immediately associated Completion system inoperable.

Time of Condition A, B, or C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.7.3.1 IST Program snubbers shall be confirmed to In accordance be functional by performing visual with Snubber examination, functional testing, and Program Plan.

service life monitoring in accordance with the ASME OM Code, Section IST and Snubber Program Plan.

NMP2 TRM 3.7-6a Rev. 41 March 2019

Sealed Source Contamination TRM 3.7.4 TRM 3.7 PLANT SYSTEMS TRM 3.7.4 Sealed Source Contamination TLCO 3.7.4 Each sealed source containing radioactive material > 100 µCi of beta and/or gamma emitting material or > 5 µCi of alpha emitting material shall have < 0.005 µCi removable contamination.

APPLICABILITY: At all times ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowable for each source.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Suspend use and Immediately Required Action A.3 transfer of sealed shall be completed if source.

this Condition is AND entered.

A.2.1 Restore removable Prior to use contamination to One or more sealed within limit.

sources with removable contamination not OR within limit.

A.2.2 Dispose of sealed Prior to use source in accordance with 10 CFR.

AND A.3 Submit report of 12 months contaminated sealed source to the Commission.

NMP2 TRM 3.7-7 Rev. 16 May 2004

Sealed Source Contamination TRM 3.7.4 SURVEILLANCE REQUIREMENTS

NOTES--------------------------------------

1. Each Surveillance shall be performed by the licensee or other persons specifically authorized by the Commission or an Agreement State.

2. The test method shall have a detection sensitivity of at least 0.005 µCi per test sample.

SURVEILLANCE FREQUENCY TRSR 3.7.4.1 ------------------NOTE---------------------

Not required to be met for: a) sources with half-life < 30 days; b) gaseous sources; c) startup sources and fission detectors previously subjected to core flux; d) sources not in use; and e) hydrogen-3.

Verify contamination of each sealed source 6 months is within limit.

TRSR 3.7.4.2 ------------------NOTE---------------------

Only required to be met for sealed startup sources and fission detectors.

Verify contamination of each sealed source Once within is within limit. 31 days prior to use AND Following repair or maintenance to the source TRSR 3.7.4.3 ------------------NOTE---------------------

Only required to be met for sources not in use.

Verify contamination of each sealed source Once within is within limit. 6 months prior to transfer to another licensee NMP2 TRM 3.7-8 Rev. 2 November 2000

Main Turbine Bypass System TRM 3.7.5 TRM 3.7 PLANT SYSTEMS TRM 3.7.5 Main Turbine Bypass System The TURBINE BYPASS SYSTEM RESPONSE TIME for Technical Specifications SR 3.7.5.2 is contained in Table T3.7.5-1.

TABLE T3.7.5-1 (Page 1 of 1)

TURBINE BYPASS SYSTEM RESPONSE TIME Component RESPONSE TIME The time from initial movement of the main turbine stop valve < 0.3 second or control valve until 80% of the turbine bypass capacity is established.

The time from initial movement of the main turbine stop valve < 0.1 second or control valve until initial movement of the turbine bypass valve.

NMP2 TRM 3.7-9 Rev. 2 November 2000

Revetment-Ditch Structure TRM 3.7.6 TRM 3.7 PLANT SYSTEMS TRM 3.7.6 Revetment-Ditch Structure TLCO 3.7.6 The Revetment-Ditch Structure shall be:

a. Structurally sound and capable of limiting wave action as intended; and

b. Maintained so that the elevation of each survey point listed in Table T3.7.6-1 is not more than 1.0 foot below the listed elevation.

APPLICABILITY: At all times.

ACTIONS

NOTE---------------------------------------

Separate Condition entry is allowed for each survey point.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Pursuant to 90 days Required Action A.1 10 CFR 50.4, prepare shall be completed if and submit a Special this Condition is Report to the entered. Commission which

includes:

One or more survey a. An explanation of points more than 1.0 how the elevation foot below the listed change occurred elevation. and if the Revetment-Ditch Structure is continuing to change, (continued)

b. A planned course of repair (if required) and a schedule for accomplishing the repair, NMP2 TRM 3.7-10 Rev. 2 November 2000

Revetment-Ditch Structure TRM 3.7.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) a. An evaluation of and justification for continued plant operation, and

b. The current elevation of each survey point shown in Table T3.7.6-1.

SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------

Limited and full surveys shall be performed with survey equipment to at least third-order accuracy.

SURVEILLANCE FREQUENCY TRSR 3.7.6.1 Perform a visual inspection. Once within 7 days after any earthquake with an intensity

> Operating Basis Earthquake (OBE)

AND 12 months TRSR 3.7.6.2 Perform a limited survey. 12 months (continued)

NMP2 TRM 3.7-11 Rev. 2 November 2000

Revetment-Ditch Structure TRM 3.7.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TRSR 3.7.6.3 Perform a full survey. As soon as practical after any earthquake with an intensity

> OBE AND

NOTE------

Only required when the elevation change of one or more control points exceeds 2 inches in any 24 month period and continues to be required until two consecutive surveys show any additional elevation change to be < 2 inches in each 24 month period 12 months AND 24 months NMP2 TRM 3.7-12 Rev. 2 November 2000

Revetment-Ditch Structure TRM 3.7.6 TABLE T3.7.6-1 (Page 1 of 1)

Survey Points for Revetment-Ditch Structure Survey Point(a),(b) North-South East-West October 1985 Control Elevation 1C N 1283798.13 E 546895.34 252.165 1B N 1283821.89 E 546888.75 263.075 1A N 1283828.48 E 546887.88 264.290 2C N 1283770.08 E 546799.33 253.765 2B N 1283793.42 E 546798.66 263.725 2A N 1283800.70 E 546802.21 264.535 3C N 1283741.94 E 546703.71 252.920 3B N 1283766.13 E 546696.05 263.130 3A N 1283771.53 E 546695.04 263.215 4C N 1283660.46 E 546608.29 254.450 4B N 1283681.23 E 546607.66 263.560 4A N 1283684.30 E 546597.26 263.950 5C N 1283688.87 E 546510.60 255.665 5B N 1283705.21 E 546496.47 263.820 5A N 1283714.96 E 546498.16 263.440 6C N 1283672.49 E 546405.17 255.870 6B N 1283689.60 E 546407.84 264.180 6A N 1283694.74 E 546404.07 264.750 7C N 1283675.92 E 546305.02 256.575 7B N 1283696.02 E 546299.75 263.680 7A N 1283705.09 E 546309.27 265.235 8C N 1283684.19 E 546205.09 256.300 8B N 1283705.28 E 546205.14 263.125 8A N 1283712.00 E 546206.38 263.155 9C N 1283691.57 E 546110.39 257.715 9B N 1283710.39 E 546108.25 263.660 9A N 1283720.79 E 546102.81 263.090 10C N 1283673.00 E 546016.51 257.135 10B N 1283693.66 E 546004.95 265.540 10A N 1283701.25 E 546006.68 264.035 11C N 1283646.76 E 545918.23 256.155 11B N 1283666.83 E 545918.76 263.720 11A N 1283675.17 E 545912.02 263.385 12C N 1283626.38 E 545839.53 256.395 12B N 1283650.74 E 545835.16 264.085 12A N 1283656.67 E 545831.43 264.105 (a) See TRM Bases Figures 3.7.6-1 and 3.7.6-2 for location sketches.

(b) Survey points are anchored into back armor using stainless steel HILTI quick bolts.

NMP2 TRM 3.7-13 Rev. 21 April 2006

Liquid Holdup Tanks TRM 3.7.7 TRM 3.7 PLANT SYSTEMS TRM 3.7.7 Liquid Holdup Tanks TLCO 3.7.7 The quantity of radioactive material contained in each outside temporary liquid radwaste tank that is not surrounded by a liner, dike, or wall capable of holding the tanks contents and that does not have a tank overflow and surrounding area drains connected to the Liquid Radwaste Treatment System shall be limited to the value specified in Technical Specification 5.5.8.

APPLICABILITY: At all times.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.1 Suspend all additions Immediately Required Action A.3 of radioactive shall be completed if material to the tank.

this Condition is entered. AND 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months A.2 Reduce the tank Requirements of the contents to within TLCO not met.

the limit.

AND In accordance with Technical A.3 Describe the events Specification leading to this 5.6.3.

condition in the next Radioactive Effluent Release Report.

NMP2 TRM 3.7-14 Rev. 2 November 2000

Liquid Holdup Tanks TRM 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.7.7.1 Determine the quantity of radioactive 7 days when material contained in each applicable tank radioactive to be within the limit by analyzing a materials are representative sample of the tanks being added to contents. the tank NMP2 TRM 3.7-15 Rev. 2 November 2000

Explosive Gas Mixture TRM 3.7.8 TRM 3.7 PLANT SYSTEMS TRM 3.7.8 Explosive Gas Mixture TLCO 3.7.8 The concentration of hydrogen in the main condenser offgas treatment system shall be < 4% by volume.

APPLICABILITY: During offgas system operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Offgas hydrogen A.1 Restore concentration 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concentration not to within limit.

within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.7.8.1 Verify concentration of hydrogen in the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months main condenser offgas treatment system < 4%

by volume.

NMP2 TRM 3.7-16 Rev. 14 February 2004

AC Circuits Inside Primary Containment TRM 3.8.2.1 TRM 3.8 ELECTRICAL POWER SYSTEMS TRM 3.8.2.1 AC Circuits Inside Primary Containment TLCO 3.8.2.1 The AC Circuits Inside Primary Containment shown in Table T3.8.2.1-1 shall be de-energized.

APPLICABILITY: MODES 1, 2, and 3, except during entry into the drywell.

NOTE----------------------

Applicable before power ascension and following final drywell entry.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Open associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months circuits energized. circuit breaker(s).

NMP2 TRM 3.8-1 Rev. 17 January 2005

AC Circuits Inside Primary Containment TRM 3.8.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.8.2.1.1 --------------------NOTE-------------------

Only required to be met for circuit breakers not locked, not sealed, and not otherwise secured in the tripped condition.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Verify each required circuit de-energized by verifying that the associated circuit breakers are in the tripped condition.

TRSR 3.8.2.1.2 --------------------NOTE-------------------

Only required to be met for circuit breakers locked, sealed, or otherwise secured in the tripped condition.

31 days Verify each required circuit de-energized by verifying that the associated circuit breakers are in the tripped condition.

NMP2 TRM 3.8-2 Rev. 2 November 2000

AC Circuits Inside Primary Containment TRM 3.8.2.1 TABLE T3.8.2.1-1 AC Circuits Inside Primary Containment Required To Be De-Energized Circuit Breaker/Switch Power Source Position Equipment Powered 2LAR-PNLN12 1 Normal Receptacle Circuits - Elevation 289 2LAR-PNLN12 2 Normal Receptacle Circuits - Elevation 240 2LAR-PNLN12 3 Normal Receptacle Circuits - Elevation 261 2LAR-PNLN12 11 Normal Lighting Circuits - Elevation 261 2LAR-PNLN12 12 Normal Lighting Circuits - Elevation 261 2LAR-PNLN12 13 Normal Lighting Circuits - Elevation 240 2LAR-PNLN12 14 Normal Lighting Circuits - Elevation 240 & 261 2LAR-PNLN12 15 Normal Lighting Circuits - Elevation 240 & 289 2LAR-PNLN12 16 Normal Lighting Circuits - Elevation 289 2LAR-PNLN12 19 Normal Lighting Circuits - Elevation 289 2LAR-PNLU01 8 Essential Receptacle Circuits - Suppression Pool 2LAR-PNLU01 15 Communication Party Paging - Suppression Pool 2LAR-PNLU02 14 Essential Lighting Circuits - Elevation 240 2LAR-PNLU02 15 Essential Lighting Circuits - Elevations 261 and 289 2LAR-PNLU03 12 Communication Party Paging - Above Suppression Pool 2SCA-PNL406 9 2RDS-PLAT1 - Platform used to rotate and position CRD handling equipment during refueling only -

Elevation 250 2WPS-PNL200 20 2WPS-RCPT51A & 2WPS-RCPT51B - Elevation 261-0 2WPS-PNL200 26 2WPS-RCPT52A & 2WPS-RCPT52B - Elevation 261-0 NMP2 TRM 3.8-3 Rev. 2 November 2000

Primary Containment Penetration Conductor Overcurrent Protective Devices TRM 3.8.2.2 TRM 3.8 ELECTRICAL POWER SYSTEMS TRM 3.8.2.2 Primary Containment Penetration Conductor Overcurrent Protective Devices TLCO 3.8.2.2 The Primary Containment Penetration Conductor Overcurrent Protective Devices shall be OPERABLE, except for those associated with penetration assemblies that are capable of withstanding the maximum current available because of an electrical fault inside containment.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each overcurrent protective device.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more 13.8 kV A.1 Declare the affected Immediately overcurrent protective system(s) or devices inoperable. component(s) inoperable.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months A.2 Open associated redundant circuit breaker(s).

AND Once per 7 days A.3 Verify the redundant circuit breaker(s) open.

(continued)

NMP2 TRM 3.8-4 Rev. 2 November 2000

Primary Containment Penetration Conductor Overcurrent Protective Devices TRM 3.8.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more 600 volt B.1 Declare the affected Immediately MCC overcurrent system(s) or protective devices component(s) inoperable. inoperable.

AND B.2 Open the associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit breaker(s).

AND B.3 Verify the circuit Once per 7 days breaker(s) open.

C. Required Action and C.1 Complete IR 14 days associated Completion evaluation of the Time of Condition A, degraded condition, or B not met. including preplanned alternate methods of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channel to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.8.2.2.1 Select, on a rotating basis, at least 10% 24 months of the 13.8 kV circuit breakers and perform a CHANNEL CALIBRATION of the associated protective relays.

(continued)

NMP2 TRM 3.8-5 Rev. 39 October 2017

Primary Containment Penetration Conductor Overcurrent Protective Devices TRM 3.8.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TRSR 3.8.2.2.2 ------------------NOTE---------------------

For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

Select, on a rotating basis, at least 10% 24 months of the 13.8 kV circuit breakers and perform an integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuits function as designed.

Perform inspection and preventative maintenance of the selected 10% breaker population in accordance with procedures.

TRSR 3.8.2.2.3 ------------------NOTES--------------------

1. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status before resuming operation.

2. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

24 months Select, on a rotating basis, and functionally test a representative sample of at least 10% of each type of lower voltage circuit breakers.

Perform inspection and preventative maintenance of the selected 10% breaker population in accordance with procedures.

NMP2 TRM 3.8-6 Rev. 47 March 2022

Emergency Lighting System - Overcurrent Protective Devices TRM 3.8.2.3 TRM 3.8 ELECTRICAL POWER SYSTEMS TRM 3.8.2.3 Emergency Lighting System - Overcurrent Protective Devices TLCO 3.8.2.3 The Emergency Lighting System Overcurrent Protective Devices listed in Table T3.8.2.3-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTIONS

NOTE--------------------------------------

Separate Condition entry is allowed for each overcurrent protective device.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Open the associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months overcurrent protective circuit breaker.

devices inoperable.

AND A.2 Return the 7 days overcurrent protective device and the associated breaker to OPERABLE status.

B. Required Action and B.1 Complete IR 14 days associated Completion evaluation of the Time not met. degraded condition, including preplanned alternate methods of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channel to OPERABLE status.

NMP2 TRM 3.8-7 Rev. 39 October 2017

Emergency Lighting System - Overcurrent Protective Devices TRM 3.8.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.8.2.3.1 Test one-half of each type of circuit 48 months breaker on a rotating basis.

NMP2 TRM 3.8-8 Rev. 46 February 2022

Emergency Lighting System - Overcurrent Protective Devices TRM 3.8.2.3 TABLE T3.8.2.3-1 (page 1 of 1)

Emergency Lighting System Overcurrent Protective Devices Primary Circuit Breaker Backup Circuit Breaker Circuit Circuit Equipment Powered Circuit Circuit Breaker Breaker Breaker Breaker Location Position Location Position 2LAC*PNLE01 Main Division 1 Switchgear Diesel 2LAC*PNL100A 1 Generator Room and Remote Shutdown Room 2LAC*PNLE02 Main Division 2 Switchgear Diesel 2LAC*PNL300B 1 Generator Room and Remote Shutdown Room 2LAC*PNLE03 Main Division 3 Switchgear Diesel 2EHS*MCC201 10B Generator Room 2LAC*PNLE04 Main Relay Room 2LAC*PNL100A 2 2LAC*PNLE05 Main Relay Room 2LAC*PNL300B 2 2LAC*PNLE06 Main Control Room 2LAC*PNL100A 8 2LAC*PNLE07 Main Control Room 2LAC*PNL300B 8 NMP2 TRM 3.8-9 Rev. 2 November 2000

Decay Time TRM 3.9.2 TRM 3.9 REFUELING OPERATIONS TRM 3.9.2 Decay Time TLCO 3.9.2 The reactor shall be subcritical > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY: During movement of irradiated fuel assemblies within the reactor pressure vessel (RPV).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical A.1 Suspend all Immediately

< 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . operations involving movement of irradiated fuel assemblies within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.9.2.1 Verify reactor subcritical > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by Prior to movement verification of the date and time of of irradiated subcriticality. fuel assemblies within the RPV NMP2 TRM 3.9-1 Rev. 2 November 2000

Communications TRM 3.9.3 TRM 3.9 REFUELING OPERATIONS TRM 3.9.3 Communications TLCO 3.9.3 Direct communication shall be maintained between the control room and refueling floor personnel.

APPLICABILITY: During CORE ALTERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Direct communication A.1 Suspend CORE Immediately between the control ALTERATIONS.

room and refueling floor personnel not maintained.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.9.3.1 Verify direct communication between the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control room and refueling floor personnel.

NMP2 TRM 3.9-2 Rev. 2 November 2000

Refueling Platform TRM 3.9.4 TRM 3.9 REFUELING OPERATIONS TRM 3.9.4 Refueling Platform TLCO 3.9.4 The refueling platform shall be OPERABLE and used for moving fuel assemblies or control rods within the reactor pressure vessel.

APPLICABILITY: During movement of fuel assemblies or control rods within the reactor pressure vessel (RPV).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling platform A.1 Suspend use of any Immediately inoperable. inoperable refueling platform equipment from operations involving the movement of fuel assemblies or control rods within the RPV.

NMP2 TRM 3.9-3 Rev. 2 November 2000

Refueling Platform TRM 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.9.4.1 Verify operation of the overload cutoff on Once within 31 the main hoist when the load exceeds 1600 days prior to use

+100/-0 pounds.

TRSR 3.9.4.2 Verify operation of the overload cutoff on Once within 31 the frame mounted and monorail mounted days prior to use auxiliary hoists when the load exceeds 1000

+ 50 pounds.

TRSR 3.9.4.3 Verify operation of the main and auxiliary Once within 31 hoist uptravel stops when the grapple is days prior to use lower than or equal to 7 feet 33/4 inches below the platform tracks.

TRSR 3.9.4.4 Verify operation of the downtravel Once within 31 mechanical cutoff on the main hoist when days prior to use grapple hook down travel reaches 4 to 4.5 inches below fuel assembly handle.

TRSR 3.9.4.5 Verify operation of the slack cable cutoff Once within 31 on the main hoist when the load is less days prior to use than 60 + 10 pounds.

TRSR 3.9.4.6 Verify operation of the loaded interlock on Once within 31 the main hoist when the load exceeds 700 days prior to use

+50/-0 pounds.

TRSR 3.9.4.7 Verify operation of the redundant loaded Once within 31 interlock on the main hoist when the load days prior to use exceeds 700 +50/-0 pounds.

NMP2 TRM 3.9-4 Rev. 46 February 2022

Crane Travel - Spent Fuel Storage Pool TRM 3.9.5 TRM 3.9 REFUELING OPERATIONS TRM 3.9.5 Crane Travel - Spent Fuel Storage Pool TLCO 3.9.5 Loads > 1000 pounds shall not travel over fuel assemblies in the spent fuel storage pool racks unless handled by a single failure-proof handling system.

APPLICABILITY: With fuel assemblies in the spent fuel storage pool racks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend movement of Immediately TLCO not met. load over the spent fuel storage pool racks.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.9.5.1 Verify crane interlocks prevent crane 7 days during travel over fuel assemblies in the spent crane operation fuel storage pool racks.

TRSR 3.9.5.2 Visually inspect and verify OPERABLE the 7 days during single failure-proof lifting devices. crane operation over the spent fuel pool NMP2 TRM 3.9-5 Rev. 2 November 2000

Solid Radioactive Wastes TRM 3.11.1 TRM 3.11 RADIOACTIVE EFFLUENTS TRM 3.11.1 Solid Radioactive Wastes TLCO 3.11.1 Radioactive wastes shall be solidified or dewatered in accordance the Process Control Program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Solidification or A.1 Suspend shipment of Immediately dewatering not meeting the inadequately disposal site or processed wastes.

shipping and transportation AND Immediately requirements.

A.2 Initiate action to correct the Process Control Program, the procedures, and the Solid Waste System, as applicable, to prevent recurrence.

B. Solidification or B.1 Initiate action to Immediately dewatering not test the improperly performed in processed waste in accordance with the each container to Process Control ensure that it meets Program. burial ground and shipping requirements.

AND Immediately B.2 Initiate appropriate administrative action to prevent recurrence.

(continued)

NMP2 TRM 3.11-1 Rev. 2 November 2000

Solid Radioactive Wastes TRM 3.11.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Installed equipment C.1 Initiate action to Immediately incapable of meeting process wastes as the TLCO statement or necessary to satisfy declared inoperable. all applicable transportation and disposal requirements.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TRSR 3.11.1.1 Verify, in accordance with the Process In accordance Control Program, solidification of at least with the Process one representative test specimen from at Control Program least every tenth batch of each type of wet radioactive wastes.

a. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the Process Control Program, and a subsequent test verifies solidification.

Solidification of the batch may then be resumed using the alternative solidification parameters determined by the Process Control Program.

b. If the initial test specimen from a batch of waste fails to verify solidification, the Process Control Program shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The Process Control Program shall be modified as required to assure solidification of subsequent batches of waste.

NMP2 TRM 3.11-2 Rev. 2 November 2000

Primary Coolant Sources Outside Containment Program TRM 5.5.2 TRM 5.5 PROGRAMS TRM 5.5.2 Primary Coolant Sources Outside Containment Program Technical Specification 5.5.2, Primary Coolant Sources Outside Containment, is established, implemented, and maintained by:

NMP2-PRL-001, Description of a Program to Reduce Leakage from Systems Outside Containment that Would or Could Contain Highly Radioactive Fluids During a Serious Transient or Accident to As-Low-As-Practical Levels in satisfaction of NMPC commitments to USNRC related to NUREG-0737 Clarification of TMI Action Plan Item no. III.D.1.1 Primary Coolant Sources Outside the Containment for the Nine Mile Point, Unit 2 Nuclear Power Station as required by Technical Specification 5.5.2.

NMP2 TRM 5.5-1 Rev. 2 November 2000

Deleted TRM 5.5.3 TRM 5.5 PROGRAMS TRM 5.5.3 Deleted Deleted NMP2 TRM 5.5-2 Rev. 11 October 2002

Component Cyclic or Transient Limit TRM 5.5.5 TRM 5.5 PROGRAMS TRM 5.5.5 Component Cyclic or Transient Limit Technical Specification 5.5.5, Component Cyclic or Transient Limit, is established, implemented, and maintained by:

1. Nuclear Interface Procedure NIP-REL-06, Fatigue Monitoring Program, and

2. Updated Safety Analysis Report Table 3.9A-1 and Table 3.9B-1.

NMP2 TRM 5.5-3 Rev. 21 April 2006

Ventilation Filter Testing Program TRM 5.5.7 TRM 5.5 PROGRAMS TRM 5.5.7 Ventilation Filter Testing Program Technical Specification 5.5.7, Ventilation Filter Testing Program, is established, implemented, and maintained by:

1. Technical Surveillance Procedure N2-MSP-GTS-R@001, Testing and Analysis of Unit 2 Standby Gas Treatment System,

2. Technical Surveillance Procedure N2-TSP-HVC-R@001, Testing and Analysis of Unit 2 Control Room Outdoor Air Special Filter Train System, and

3. Surveillance Test Procedure N2-OSP-GTS-R@001, Standby Gas Treatment System Functional Test.

NMP2 TRM 5.5-4 Rev. 33 April 2016

Explosive Gas and Storage Tank Radioactivity Monitoring Program TRM 5.5.8 TRM 5.5 PROGRAMS TRM 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program Technical Specification 5.5.8, Explosive Gas and Storage Tank Radioactivity Monitoring Program, is established, implemented, and maintained by:

1. TRM Specification 3.3.11, Offgas System Explosive Gas Monitoring,

2. TRM Specification 3.7.7, Liquid Holdup Tanks, and

3. TRM Specification 3.7.8, Explosive Gas Mixture.

NMP2 TRM 5.5-5 Rev. 2 November 2000

Diesel Fuel Oil Testing Program TRM 5.5.9 TRM 5.5 PROGRAMS TRM 5.5.9 Diesel Fuel Oil Testing Program Technical Specification 5.5.9, Diesel Fuel Oil Testing Program, is established, implemented, and maintained by:

1. N2-CSP-EDG-@501, Incoming Diesel Fuel,

2. N2-CSP-EDG-M500, Emergency Diesel Fuel Monthly Particulate Surveillance, and

3. N2-CSP-EDG-A503, Emergency Diesel Generator Fuel Preservative Surveillance.

NMP2 TRM 5.5-6 Rev. 2 November 2000

Technical Specifications Bases Control Program TRM 5.5.10 TRM 5.5 PROGRAMS TRM 5.5.10 Technical Specifications Bases Control Program Technical Specification 5.5.10, Technical Specifications Bases Control Program, is established, implemented, and maintained by:

Procedure LS-AA-101-1000, License Amendment and Technical Specifications Change Request Process.

NMP2 TRM 5.5-7 Rev. 33 April 2016

Safety Function Determination Program TRM 5.5.11 TRM 5.5 PROGRAMS TRM 5.5.11 Safety Function Determination Program Technical Specification 5.5.11, Safety Function Determination Program, is established, implemented, and maintained by:

Procedure OP-NM-108-115-1003, Safety Function Determination Program.

NMP2 TRM 5.5-8 Rev. 33 April 2016

10 CFR 50 Appendix J Testing Program Plan TRM 5.5.12 TRM 5.5 PROGRAMS TRM 5.5.12 10 CFR 50 Appendix J Testing Program Plan Technical Specification 5.5.12, 10 CFR 50 Appendix J Testing Program Plan, is established, implemented, and maintained by:

NMP2-APPJ-001, 10 CFR 50 Appendix J Testing Program Plan.

NMP2 TRM 5.5-9 Rev. 2 November 2000

Augmented Snubber Inservice Inspection Program TRM 5.5.13 TRM 5.5 PROGRAMS TRM 5.5.13 The Snubber Program The Snubber Program is in accordance with the ASME OM Code, Section IST, Current Code of Record, and is implemented in accordance with the Snubber Program Plan NMP2 TRM 5.5-10 Rev. 41 March 2019

Snubber Program TRM 5.5.13 This page intentionally left blank.

NMP2 TRM 5.5-11 Rev. 41 March 2019

Snubber Program TRM 5.5.13 This page intentionally left blank.

NMP2 TRM 5.5-12 Rev. 41 March 2019

Snubber Program TRM 5.5.13 This page intentionally left blank.

NMP2 TRM 5.5-13 Rev. 41 March 2019

Snubber Program TRM 5.5.13 This page intentionally left blank.

NMP2 TRM 5.5-14 Rev. 41 March 2019

Control Room Envelope Habitability Program TRM 5.5.14 TRM 5.5 PROGRAMS TRM 5.5.14 Control Room Envelope Habitability Program Technical Specification 5.5.13, Control Room Envelope Habitability Program, is established, implemented, and maintained by:

1. NIP-CRH-01, Control Room Integrity Program,

2. NEP-CRH-01, Control Room Integrity Program Review, and

3. NEP-CRH-02, Control Room Integrity Program Self-Assessment.

NMP2 TRM 5.5-15 Rev. 28 March 2010

TRM Control Program TRM 5.5.15 TRM 5.5 PROGRAMS TRM 5.5.15 Technical Requirements Manual Control Program A. PURPOSE The purpose of this Program is to provide guidance for identifying, processing, and implementing changes to the Technical Requirements Manual (TRM). This Program is applicable to the preparation, review, implementation, and distribution of changes to the TRM. This Program also provides guidance for preparing TRM Change Packages for distribution.

B. DEFINITIONS AND/OR ACRONYMS 10 CFR 50.59 REVIEW - A written regulatory evaluation which provides the basis for the determination that a change does, or does not, require NRC approval pursuant to 10 CFR 50.59. The scope of the evaluation should be commensurate with the potential safety significance of the change, but must address the relevant safety concerns included in the Safety Analysis Report and other owner controlled documents. The depth of the evaluation must be sufficient to determine whether or not NRC approval is required prior to implementation. Depending upon the significance of the change, the evaluation may be brief; however, a simple statement of conclusion is not sufficient.

EDITORIAL CHANGE - Editorial changes include correction of punctuation, insignificant word or title changes, style or format changes, typographical errors, or correction of reference errors that do not change the intent, outcome, results, functions, processes, responsibilities, or performance requirements of the item being changed. Changes in numerical values shall not be considered as editorial changes. Editorial changes do not constitute a change to the TRM and therefore do not require further 10 CFR 50.59 Reviews. If the full scope of this proposed change is encompassed by one or more of the below, then the change is considered editorial.

- Rewording or format changes that do not result in changing actions to be accomplished.

- Deletion of cycle-specific information that is no longer applicable.

- Addition of clarifying information, such as:

- Spelling, grammar, or punctuation changes

- Changes to references

- Name or title references (continued)

NMP2 TRM 5.5-16 Rev. 40 April 2018

TRM Control Program TRM 5.5.15 TRM 5.5.15 Technical Requirements Manual Control Program C. PROGRAM DESCRIPTION

1. A Licensee may make changes to the TRM without prior NRC approval provided the changes do not require NRC approval pursuant to 10 CFR 50.59.

2. Changes that require NRC approval pursuant to 10 CFR 50.59 shall be submitted to the NRC pursuant to 10 CFR 50.90 and reviewed and approved by the NRC prior to implementation.

3. The TRM is part of the Updated Final Safety Analysis Report (UFSAR) by reference and shall be maintained consistent with the remainder of the UFSAR.

4. If a change to the TRM is not consistent with the remainder of the UFSAR, then the cognizant Engineer shall prepare and submit a UFSAR Change Package when the TRM Change Request is submitted to Regulatory Assurance (RA) for processing.

5. Changes to the TRM that do not require prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e), as modified by approved exemptions.

6. TRM changes associated with a Technical Specifications (TS) Amendment shall be implemented consistent with the implementation requirements of the TS Amendment.

D. PROGRAM IMPLEMENTATION

1. TRM Change Requestor identifies the need for a revision and completes items 2 through 6 of Attachment A, "Technical Requirements Manual Change Request Form." A copy of the proposed TRM changes are attached, signs and dates as requestor, and forwards to the Regulatory Assurance Licensing Engineer (RA LE).

This process mirrors the USAR change process described in LS-AA-107-1001.

TRM Change Requestor provides a 10 CFR 50.59 REVIEW for the TRM changes in accordance with appropriate plant procedures. An exception to this requirement applies when the changes are being requested in order to reflect an approved NRC Safety Evaluation (SE) associated with a site-specific operating license or TS change. The NRC SE is sufficient to support the changes provided it has been determined that the changes are consistent with and entirely bounded by the NRC SE. Refer to the 10 CFR 50.59 Resource Manual for processing guidance.

2. RA LE reviews the change and determines if the change is needed and consistent with the information and level of detail contained in the TRM, signing item 8. If the change is inappropriate, return to the originator for correction or cancel the change.

A TRM Change Request Number log is maintained.

(continued)

NMP2 TRM 5.5-17 Rev. 40 April 2018

TRM Control Program TRM 5.5.15 TRM 5.5.15 Technical Requirements Manual Control Program Attachment A Technical Requirements Manual Change Request Form

1. Change Request #:

2. Affected TRM Section(s):

3. Description of changes:

4. Reason for changes (attach all supporting documentation):

5. Schedule Requirements: Outage Related (check one) ( ) No ( ) Yes, Outage #

Other (explain)

6. Check one:

( ) 10 CFR 50.59 REVIEW Attached, 10 CFR 50.59 REVIEW #:

( ) NRC SE Attached, Changes consistent with and entirely bounded by NRC SE

( ) EDITORIAL CHANGE, No 10 CFR 50.59 REVIEW required

7. Requestor: / /

Signature) (Date) (Department)

8. Regulatory Assurance Approval:

/

(Signature) (Date)

NMP2 TRM 5.5-18 Rev. 40 April 2018

TLCO and TRSR Applicability TRM B3.0 TRM B3.0 TLCO AND TRSR APPLICABILITY BASES See the Bases of the associated Technical Specification for each Technical Requirements Manual TLCO 3.0 and TRSR 3.0 Specification, except for TLCO 3.0.3.

TLCO 3.0.3 establishes the actions that must be implemented when a TLCO is not met and:

a. An associated Required Action and Completion Time is not met and no other Condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit.

The Corrective Action Program (CAP) assures that degraded conditions receive proper attention regarding reportability, operability/functionality determinations, cause analysis, and compensatory and corrective actions in a timely manner. TLCO 3.0.3 is not intended as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable/non-functional. This specification is also not intended to be entered voluntarily to extend Completion Times for Conditions defined in the TRM Specifications. This Specification shall not be used as an alternative Required Action for a Condition specifically defined within the TRM Specifications solely because the requirements of TLCO 3.0.3 are preferable to those defined for the Condition. This Specification does not supersede any requirements included in the current Operability Determination/Functionality Assessment procedure.

The requirements of TLCO 3.0.3 shall be completed if the Specification is entered.

NMP2 TRM B3.0-1 Rev. 32 August 2012

Control Rod Scram Times < 800 psig TRM B3.1.4 TRM B3.1 REACTIVITY CONTROL SYSTEMS TRM B3.1.4 Control Rod Scram Times < 800 psig BASES See Bases for Technical Specification SR 3.1.4.3.

NMP2 TRM B3.1-1 Rev. 2 November 2000

Reactor Protection System (RPS) Response Time TRM B3.3.1.1 TRM B3.3 INSTRUMENTATION TRM B3.3.1.1 Reactor Protection System (RPS) Response Time BASES See Bases for Technical Specification SR 3.3.1.1.17.

NMP2 TRM B3.3-1 Rev. 2 November 2000

RPS Shorting Links TRM B3.3.1.2 TRM B3.3 INSTRUMENTATION TRM B3.3.1.2 Reactor Protection System (RPS) Shorting Links BASES Removing the shorting links places the RPS circuitry in the non-coincidence mode. The SRM channel high flux scram (with shorting links removed) provides an uncredited backup in MODE 5.

NMP2 TRM B3.3-2 Rev. 2 November 2000

Control Rod Block Instrumentation TRM B3.3.2 TRM B3.3 INSTRUMENTATION TRM B3.3.2 Control Rod Block Instrumentation BASES See Technical Specification 3.3.1.1, RPS Instrumentation, for an instrumentation description. The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.

The scram discharge volume water level-high Allowable Value is referenced to a scram discharge volume instrument zero level at elevation 263 feet 10 inches.

NMP2 TRM B3.3-3 Rev. 2 November 2000

Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation TRM B3.3.3.1 TRM B3.3 INSTRUMENTATION TRM B3.3.3.1 Non-Type A, Non-Category 1 Post Accident Monitoring Instrumentation BASES See USAR Section 7.5.2.

Technical Specifications (TS) Amendment No. 124 revised the TS by deleting requirements related to hydrogen and oxygen analyzers as part of the rule making changes that revised 10 CFR 50.44. 10 CFR 50.44 no longer defines a design-basis LOCA hydrogen release and eliminated requirements for hydrogen control systems. With this elimination, both the hydrogen and oxygen analyzers are no longer required to mitigate design-basis accidents. Therefore, both the hydrogen and oxygen analyzers no longer meet the definition of a safety-related component as defined in 10 CFR 50.2.

As part of the rulemaking to revise 10 CFR 50.44, the NRC concluded that Category 3, as defined in Regulatory Guide (RG) 1.97, was an appropriate categorization for the hydrogen analyzers, and that Category 2, as defined in RG 1.97, was an appropriate categorization for the oxygen analyzers.

The inclusion of both the PAM hydrogen and oxygen analyzers in the TRM is a result of commitments made in TS Amendment No. 124 to the NRC to maintain both a hydrogen and oxygen monitoring system capable of diagnosing beyond design -basis accidents.

NMP2 TRM B3.3-4 Rev. 36 September 2017

Remote Shutdown System TRM B3.3.3.2 TRM B3.3 INSTRUMENTATION TRM B3.3.3.2 Remote Shutdown System BASES See Bases for Technical Specification 3.3.3.2.

NMP2 TRM B3.3-5 Rev. 2 November 2000

EOC-RPT SYSTEM RESPONSE TIME TRM B3.3.4 TRM B3.3 INSTRUMENTATION TRM B3.3.4 End of Cycle Recirculation Pump Trip (EOC-RPT) SYSTEM RESPONSE TIME BASES See Bases for Technical Specification SR 3.3.4.1.5.

NMP2 TRM B3.3-6 Rev. 2 November 2000

Emergency Core Cooling System (ECCS) Instrumentation TRM B3.3.5 TRM B3.3 INSTRUMENTATION TRM B3.3.5 Emergency Core Cooling System (ECCS) Instrumentation BASES See USAR Section 6.3.2.8.

NMP2 TRM B3.3-7 Rev. 2 November 2000

Primary Containment ISOLATION SYSTEM RESPONSE TIME TRM B3.3.6.1 TRM B3.3 INSTRUMENTATION TRM B3.3.6.1 Primary Containment ISOLATION SYSTEM RESPONSE TIME BASES See the Bases for Technical Specification SR 3.3.6.1.7.

NMP2 TRM B3.3-8 Rev. 2 November 2000

Primary Containment Isolation Instrumentation TRM B3.3.6.2 TRM B3.3 INSTRUMENTATION TRM B3.3.6.2 Primary Containment Isolation Instrumentation BASES The RCIC Drywell Pressure - High Function isolates the RCIC turbine exhaust vacuum breaker isolation valves (the Group 11 valves--

2ICS*MOV148 and 2ICS*MOV164) coincident with a RCIC Steam Supply Pressure - Low signal. The RCIC Drywell Pressure - High signal is from the LPCS/RHR initiation circuitry.

One trip system isolates 2ICS*MOV148; the other trip system isolates 2ICS*MOV164. The closure of either valve isolates the line. There are two channels per trip system for both Drywell Pressure - High and RCIC Steam Supply Pressure - Low. The logic is arranged such that, for each trip system, one of the two channels of Drywell Pressure - High must actuate coincident with one of the two channels of RCIC Steam Supply Pressure - Low to isolate the associated valve.

Isolation capability for this penetration flow path is the ability to automatically close either 2ICS*MOV148 or 2ICS*MOV164 on a valid isolation signal. Therefore, isolation capability is maintained or restored if the channels in either trip system are either OPERABLE or in the tripped condition such that the isolation will occur on a valid signal.

NMP2 TRM B3.3-9 Rev. 2 November 2000

Area Radiation Monitoring Instrumentation TRM B3.3.7.1 TRM B3.3 INSTRUMENTATION TRM B3.3.7.1 Area Radiation Monitoring Instrumentation BASES The OPERABILITY of the Area Radiation Monitoring Instrumentation ensures that: (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm is initiated when the radiation level Alarm Setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10CFR50, Appendix A, General Design Criteria (GDC) 19, 61, 63, and 64.

NMP2 TRM B3.3-10 Rev. 2 November 2000

Seismic Monitoring Instrumentation TRM B3.3.7.2 TRM B3.3 INSTRUMENTATION TRM B3.3.7.2 Seismic Monitoring Instrumentation BASES The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the ground motion effects of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12, Instrumentation for Earthquakes, April 1974.

NMP2 TRM B3.3-11 Rev. 2 November 2000

Traversing In-Core Probe (TIP) System TRM B3.3.7.3 TRM B3.3 INSTRUMENTATION TRM B3.3.7.3 Traversing In-Core Probe (TIP) System BASES The OPERABILITY of the traversing in-core probe (TIP) system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

An OPERABLE TIP system consists of five subsystems, each with:

a. A movable detector, drive and readout equipment to map the core, and

b. Indexing equipment to allow each detector to be calibrated in a common location.

The TIP system OPERABILITY is demonstrated by normalizing all probes (i.e., detectors) before performing an LPRM function calibration.

Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core; thus, all detectors may not be required to be OPERABLE. The OPERABILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector(s) output with data obtained during the previous LPRM calibrations.

NMP2 TRM B3.3-12 Rev. 2 November 2000

Deleted TRM B3.3.7.4 TRM B3.3 INSTRUMENTATION TRM B3.3.7.4 Deleted NMP2 TRM B3.3-13 Rev. 19 February 2006

Service Water System Instrumentation TRM B3.3.9 TRM B3.3 INSTRUMENTATION TRM B3.3.9 Service Water System Instrumentation BASES The Service Water System Instrumentation is provided to ensure the proper operation of the service water system during normal and accident conditions.

Recently irradiated fuel is fuel that has occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NMP2 TRM B3.3-14 Rev. 27 September 2008

Meteorological Monitoring Instrumentation TRM B3.3.10 TRM B3.3 INSTRUMENTATION TRM B3.3.10 Meteorological Monitoring Instrumentation BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of RG 1.23 Onsite Meteorological Programs, February 1972.

NMP2 TRM B3.3-15 Rev. 2 November 2000

Offgas System Explosive Gas Monitoring TRM B3.3.11 TRM B3.3 INSTRUMENTATION TRM B3.3.11 Offgas System Explosive Gas Monitoring BASES This instrumentation provides for monitoring and controlling the concentrations and potentially explosive gas mixtures in the Offgas system.

The Offgas System Explosive Gas Monitoring system consists of Hydrogen Monitor Train A (2OFG-AT16A) and Hydrogen Monitor Train B (2OFG-AT16B).

In single train operation, readings provided by REQUIRED ACTIONS A.1 and A.2 are direct indication of hydrogen concentration throughout the Offgas system.

In dual train operation, REQUIRED ACTION B.1 requires additional actions because direct readings may not be representative of the actual hydrogen concentration throughout the Offgas system. In the event one required channel is not operable, the inoperable trains hydrogen concentration can be calculated using system train flows and the common hydrogen concentration. In the event that both required channels are inoperable, the hydrogen concentration can be verified to be <4% by calculating the maximum hydrogen concentration possible with the system flows and common hydrogen concentration.

NMP2 TRM B3.3-16 Rev. 4 March 2001

RCS Chemistry TRM B3.4.1 TRM B3.4 REACTOR COOLANT SYSTEM TRM B3.4.1 Reactor Coolant System (RCS) Chemistry BASES The water chemistry limits of the reactor water coolant system are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during power operation. During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.

During the noble metal chemical addition (NMCA) process, conductivity and pH limits, as well as certain Completion Times, are modified due to interaction of noble metal chemicals with the reactor coolant system.

Notes are added to certain Conditions and Required Actions that allow the continuation of NMCA when the normal (non-NMCA) chemistry limits are exceeded (Table T3.4.1-1), provided pH and conductivity remain within analyzed parameters. Should these parameters be exceeded, NMCA must be immediately suspended and the parameters restored to within limits.

Additionally, an evaluation is required to determine the impact of exceeding the limits. The use of the phrase during NMCA includes the application period of noble metal chemicals as well as the post-injection cleanup activities.

Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions.

When the conductivity is within limits, the pH, chlorides and other impurities affecting conductivity must also be within their acceptable limits. With the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.

The Surveillance Requirements or other Required Actions provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

Concerning the Completion Times associated with Required Action A.3, if either:

a. RCS chloride concentration, conductivity, or pH exceeds the limits in MODE 1 for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in one continuous time interval, or

b. RCS conductivity or chloride concentration exceeds the limits in MODE 1 for more than a cumulative total of 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months in the past 365 days, then Condition B must be entered and the plant placed in MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NMP2 TRM B3.4-1 Rev. 2 November 2000

Structural Integrity TRM B3.4.2 TRM B3.4 REACTOR COOLANT SYSTEM TRM B3.4.2 Structural Integrity BASES The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.

The inservice inspection program for ASME Code Class 1, 2, and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a except where relief or an alternative has been granted by the NRC.

Affected components are as described in the inservice inspection program documents and the USAR.

NMP2 TRM B3.4-2 Rev. 21 April 2006

Pressure Isolation Valves TRM B3.4.6 TRM B3.4 REACTOR COOLANT SYSTEM TRM B3.4.6 Pressure Isolation Valves BASES See Bases for Technical Specification 3.4.6, RCS PIV Leakage.

NMP2 TRM B3.4-3 Rev. 2 November 2000

RCS Specific Activity TRM B3.4.8 TRM B3.4 REACTOR COOLANT SYSTEM TRM B3.4.8 Reactor Coolant System (RCS) Specific Activity BASES See Bases for Technical Specification 3.4.8, RCS Specific Activity.

NMP2 TRM B3.4-4 Rev. 2 November 2000

ECCS RESPONSE TIME TRM B3.5.1 TRM B3.5 EMERGENCY CORE COOLING SYSTEMS TRM B3.5.1 Emergency Core Cooling Systems (ECCS) RESPONSE TIME BASES See Bases for Technical Specifications SR 3.5.1.8 and SR 3.5.2.8.

NMP2 TRM B3.5-1 Rev. 40 April 2018

Primary Containment Isolation Valves TRM B3.6.1 TRM B3.6 CONTAINMENT SYSTEMS TRM B3.6.1 Primary Containment Isolation Valves BASES See the Bases for Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation, and Technical Specification 3.6.1.3, Primary Containment Isolation Valves.

NMP2 TRM B3.6-1 Rev. 2 November 2000

Secondary Containment TRM B3.6.4.1 TRM B3.6 CONTAINMENT SYSTEMS TRM B3.6.4.1 Secondary Containment BASES See the Bases for Technical Specifications SR 3.6.4.1.2 and SR 3.6.4.1.3.

NMP2 TRM B3.6-2 Rev. 2 November 2000

Secondary Containment Isolation Valves TRM B3.6.4.2 TRM B3.6 CONTAINMENT SYSTEMS TRM B3.6.4.2 Secondary Containment Isolation Valves BASES See the Bases for Technical Specifications SR 3.6.4.2.1, SR 3.6.4.2.2, and SR 3.6.4.2.3.

NMP2 TRM B3.6-3 Rev. 2 November 2000

Standby Gas Treatment System TRM B3.6.4.3 TRM B3.6 CONTAINMENT SYSTEMS TRM B3.6.4.3 Standby Gas Treatment System BASES See the Ventilation Filter Testing Program (Technical Specification 5.5.7).

NMP2 TRM B3.6-4 Rev. 2 November 2000

Service Water (SW) System - Shutdown TRM B3.7.1 TRM B3.7 PLANT SYSTEMS TRM B3.7.1 Service Water (SW) System - Shutdown BASES The heat load during MODES 4, 5 and when moving recently irradiated fuel (i.e., fuel that has occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) in the secondary containment can vary significantly, depending on the time since plant shutdown and the equipment/heat loads that are required to be in service. As a result, the number of SW pumps required to be OPERABLE or in operation can vary. In addition, service water is only required to be OPERABLE for the equipment which is required to be OPERABLE for the current plant conditions (e.g., Control Room Air Conditioning (CRAC), Residual Heat Removal Shutdown Cooling, etc.).

See the Bases for Technical Specification 3.7.1, Service Water System and Ultimate Heat Sink, for additional information.

The TRSRs in this specification directly correlate to the SRs in Technical Specification 3.7.1. The Bases discussions for those Technical Specifications SRs are applicable to the associated TRSRs.

NMP2 TRM B3.7-1 Rev. 27 September 2008

Control Room Envelope Filtration System TRM B3.7.2 TRM B3.7 PLANT SYSTEMS TRM B3.7.2 Control Room Envelope Filtration System BASES See the Ventilation Filter Testing Program (Technical Specification 5.5.7).

NMP2 TRM B3.7-2 Rev. 2 November 2000

Snubbers TRM B3.7.3 TRM B3.7 PLANT SYSTEMS TRM B3.7.3 Snubbers BASES All snubbers are required to be functional to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this TLCO are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

Condition A applies to a snubber from the start of its removal from the supported system until a replacement snubber has been installed. Condition A is typically utilized when a snubber is removed from its supported system for bench testing as part of inservice inspection. Either Actions A.1 or A.2 may be chosen in response to Condition A. If Action A.2 is utilized, refer to Technical Specification 3.0.8 and its Bases for proper development of the risk-informed evaluation necessary to determine if a 12 or 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is appropriate.

Condition B applies when a snubber is found non-functional during bench testing after a replacement snubber has been installed on the supported system. Either Actions B.1 or B.2 may be chosen in response to Condition B. If this Condition is entered, either Actions B.1.2 or B.2 shall be completed, even if the non-functional snubber is repaired prior to completing the engineering evaluation of the supported system. If Action B.2 is utilized, refer to Technical Specification 3.0.8 and its Bases for proper development of the risk-informed evaluation necessary to determine if a 12 or 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is appropriate.

Condition C applies to snubbers found non-functional during normal operations or during in-situ inservice inspection. Condition C is not entered if Conditions A or B apply. Either Actions C.1 or C.2 may be chosen in response to Condition C.

If Action C.1 is utilized, Action C.1.2 must be completed, even if the snubber is declared functional prior to completion of the engineering evaluation for the supported system. If Action C.2 is utilized, refer to Technical Specification 3.0.8 and its Bases for proper development of the risk-informed evaluation necessary to determine if a 12 or 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is appropriate.

Condition D is utilized when the Completion Times, other than immediately, of Conditions A, B, or C are not met.

(continued)

NMP2 TRM B3.7-3 Rev. 41 March 2019

Snubbers TRM B3.7.3 BASES (continued)

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NMP2 TRM B3.7-4 Rev. 41 March 2019

Sealed Source Contamination TRM B3.7.4 TRM B3.7 PLANT SYSTEMS TRM B3.7.4 Sealed Source Contamination BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, and surveillance requirements are commensurate with the probability of damage to a source in that group. Those sources that are frequently handled are required to be tested more often than those that are not. Sealed sources that are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

NMP2 TRM B3.7-5 Rev. 2 November 2000

Main Turbine Bypass System TRM B3.7.5 TRM B3.7 PLANT SYSTEMS TRM B3.7.5 Main Turbine Bypass System BASES See Bases for Technical Specification SR 3.7.5.2.

NMP2 TRM B3.7-6 Rev. 2 November 2000

Revetment-Ditch Structure TRM B3.7.6 TRM B3.7.6 Revetment-Ditch Structure BASES The purpose of the revetment-ditch structure is to protect the plant fill and foundation from wave erosion, expected during the probable maximum windstorm for a maximum still water elevation of 254 feet.

The revetment-ditch structure is Seismic Category I and is designed to withstand the impact of waves. So long as the fill is in place, waves cannot impact Category I structures because of the lack of sufficient depth of water to sustain such waves.

The revetment-ditch structure can sustain a high degree of damage and still perform its function, protecting the site fill from erosion.

Thus, the OPERABILITY condition for operation of the revetment-ditch structure has been written to ensure that severe damage to the structure will not go undetected for a substantial period of time and to provide for prompt corrective action and NRC notification.

NMP2 TRM B3.7-7 Rev. 2 November 2000

Liquid Holdup Tanks TRM B3.7.7 TRM B3.7 PLANT SYSTEMS TRM B3.7.7 Liquid Holdup Tanks BASES The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system, such as temporary tanks.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10CFR20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

NMP2 TRM B3.7-10 Rev. 2 November 2000

Explosive Gas Mixture TRM B3.7.8 TRM B3.7 PLANT SYSTEMS TRM B3.7.8 Explosive Gas Mixture BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the GASEOUS RADWASTE TREATMENT SYSTEM is maintained below the flammability limits of hydrogen and oxygen. Manual control features are utilized to prevent the hydrogen concentrations from reaching these flammability limits. These manual control features include injection of dilutants to reduce concentrations below flammability limits. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of GDC 60 of Appendix A to 10CFR50.

NMP2 TRM B3.7-11 Rev. 10 August 2002

AC Circuits Inside Primary Containment TRM B3.8.2.1 TRM B3.8 ELECTRICAL POWER SYSTEMS TRM B3.8.2.1 AC Circuits Inside Primary Containment BASES While in MODES 1, 2, and 3, except during entry into the drywell (as modified by the Applicability Note), the AC circuits inside primary containment that are not provided with primary and backup containment penetration conductor overcurrent protective devices are required to be deenergized, except for those penetration assemblies that are capable of withstanding the maximum current available because of an electrical fault inside containment. Those AC Circuits Inside Primary Containment that are required to be deenergized are listed in Table T3.8.2.1-1.

The primary containment electrical penetrations and penetration conductors subject to this specification are protected by de-energizing circuits not required during reactor operation.

NMP2 TRM B3.8-1 Rev. 17 January 2005

Primary Containment Penetration Conductor Overcurrent Protective Devices TRM B3.8.2.2 TRM B3.8 ELECTRICAL POWER SYSTEMS TRM B3.8.2.2 Primary Containment Penetration Conductor Overcurrent Protective Devices BASES Primary containment electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.

The Surveillance Requirements applicable to lower voltage circuit breakers provides assurance of breaker reliability by testing at least one representative sample of each manufacturers brand of circuit breaker. Each manufacturers molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturers brand of circuit breakers, it is necessary to divide that manufacturers breakers into groups and treat each group as a separate type of breaker for surveillance purposes.

For TRSR 3.8.2.2.3, testing of metal case circuit breakers shall consist of injecting a current with a value equal to 300% of the pickup of the long time delay trip element and 150% of the pickup of the short time delay trip element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested by injecting a current in excess of the pickup value of the element and verifying that the circuit breaker trips instantaneously with no intentional time delay.

For TRSR 3.8.2.2.3, testing of molded case circuit breakers shall consist of injecting a current with a value equal to 300% of the pickup of the long time delay trip element and verifying that the circuit breaker operates with a time delay that is less than or equal to the maximum trip time provided in NEMA Standards Publication AB 4-2009. The instantaneous element shall be tested by injecting a current in excess of the pickup value of the element and verifying that the circuit breaker trips instantaneously with no intentional time delay. If a molded case circuit breaker does not meet either of these requirements, the molded case circuit breaker shall be replaced with a circuit breaker that does meet these requirements.

If the molded case circuit breaker does not meet the long time delay criteria specified above, the affected phase(s) of the molded case circuit breaker shall be tested by injecting the current values specified in Table TB3.8.2.2-1 to determine if the circuit breakers primary containment penetration conductor overcurrent protective function is maintained. If the circuit breaker does not operate at or below the requirements specified in Table TB3.8.2.2-1, the circuit breaker is inoperable and the requirements of TRSR 3.8.2.2.3, Note 2 apply.

NMP2 TRM B3.8-2 Rev. 29 April 2010

Primary Containment Penetration Conductor Overcurrent Protective Devices TRM B3.8.2.2 Table TB3.8.2.2 (Page 1 of 1)

Molded Case Circuit Breaker Long Time Delay Test Requirements BREAKER SIZE TEST CURRENT ACCEPTANCE CRITERIA (ALL TYPES) (AMPS) (SECONDS) 30A 90 200 200 30 300 10 70A 210 200 400 40 700 10 100A 300 200 700 30 1000 10 NMP2 TRM B3.8-3 Rev. 29 April 2010

Emergency Lighting System - Overcurrent Protective Devices TRM B3.8.2.3 TRM B3.8 ELECTRICAL POWER SYSTEMS TRM B3.8.2.3 Emergency Lighting System - Overcurrent Protective Devices BASES The Emergency Lighting System Overcurrent Protective Devices ensure that a failure of the non-Class 1E portion of the circuit will not affect the operation of the remaining portions of the Class 1E circuits that are necessary for safe shutdown. The list of these overcurrent protective devices is contained in Table T3.8.2.3-1.

For TRSR 3.8.2.3.1, testing of these circuit breakers shall consist of injecting a current with a value equal to 300% of the pickup of the time delay element. The measured response time shall be compared with the manufacturers data to ensure that it is less than or equal to a value specified by the manufacturer. The instantaneous element shall be tested by injecting a current in excess of the nominal instantaneous pickup setting and verifying that circuit breaker trips instantaneously with no intentional time delay.

NMP2 TRM B3.8-4 Rev. 29 April 2010

Decay Time TRM B3.9.2 TRM B3.9 REFUELING OPERATIONS TRM B3.9.2 Decay Time BASES The minimum requirement for reactor subcriticality before fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

NMP2 TRM B3.9-1 Rev. 2 November 2000

Communications TRM B3.9.3 TRM B3.9 REFUELING OPERATIONS TRM B3.9.3 Communications BASES The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.

NMP2 TRM B3.9-2 Rev. 2 November 2000

Refueling Platform TRM B3.9.4 TRM B3.9 REFUELING OPERATIONS TRM B3.9.4 Refueling Platform BASES The OPERABILITY requirements ensure that (1) the refueling platform will be used for handling control rods and fuel assemblies within the reactor pressure vessel, (2) each crane and hoist has sufficient load capacity for handling fuel assemblies and control rods, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

Suspension of movement of fuel assemblies or control rods shall not preclude completion of movement of the fuel assembly or control rod to a safe position.

NMP2 TRM B3.9-3 Rev. 2 November 2000

Crane Travel - Spent Fuel Storage Pool TRM B3.9.5 TRM B3.9 REFUELING OPERATIONS TRM B3.9.5 Crane Travel - Spent Fuel Storage Pool BASES The restriction on movement of loads in excess of the nominal weight of a fuel assembly over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.

Suspension of load movement shall not preclude moving the load to a safe position.

NMP2 TRM B3.9-4 Rev. 2 November 2000

Offgas System Explosive Gas Monitoring TRM B3.11.1 TRM B3.11 RADIOACTIVE EFFLUENTS TRM B3.11.1 Solid Radioactive Waste BASES This specification implements the requirements of 10CFR50.36a and GDC 60 of Appendix A to 10CFR50. The process parameters included in establishing the Process Control Program may include, but are not limited to, waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

Solidified waste is liquid or setliquid waste that has been combined with an approved stabilization media to meet the requirements of 10CFR Part 61 for waste form stability for disposal.

Dewatered waste is wet waste that has been processed by means other than solidification or encapsulation to meet the free standing liquid requirements of 10CFR Part 61.

For Required Action B.2, typical appropriate administrative actions are to stop processing of waste, initiate a CR, perform an investigation, and institute appropriate corrective actions (e.g., PCP revision, procedure revisions, etc.).

For TRSR 3.11.1.1, examples of the types of wet radioactive wastes include filter sludges, spent resins, evaporator bottoms, and sodium sulfate solutions.

NMP2 TRM B3.11-1 Rev. 23 December 2007

ML22292A119

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