Text

Revisions to Technical Requirements Manual (TRM)
	ML20125A213
Person / Time
Site:	Farley
Issue date:	04/28/2020
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML20125A201	List: ML20125A202; ML20125A204; ML20125A205; ML20125A206; ML20125A207; ML20125A208; ML20125A209; ML20125A210; ML20125A212; NL-20-0442, Revisions to Technical Requirements Manual (TRM);
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	NL-20-0442
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Technical Requirements Manual (TRM)

Joseph M. Farley Nuclear Plant Units 1 and 2

Farley Nuclear Plant Units 1 and 2 Technical Requirements Manual (TRM)

List of Effective Pages Page Version Page Version Page Version TRM Cover Page 13.3.4-1 .............. 24.0 13.7.4-1 ................ 8.0 13.3.4-2 .............. 45.0 13.7.5-1 .............. 29.0 Table of Contents 13.3.4-3 .............. 24.0 13.7.5-2 ................ 8.0 i .......................... 29.0 13.3.4-4 .............. 40.0 Section 13.8 Tab ii ......................... 30.0 13.3.5-1 ................ 8.0 13.3.6-1 .............. 45.0 13.8.1-1 .............. 24.0 iii......................... 29.0 13.3.6-2 .............. 46.0 13.8.1-2 .............. 29.0 Section 11.0 Tab 13.3.6-3 .............. 29.0 13.8.1-3 .............. 42.0 11.0-1 ................. 22.0 13.3.7-1 .............. 29.0 13.8.2-1 .............. 36.0 11.0-2 ................. 29.0 13.3.7-2 .............. 29.0 13.8.2-2 ................ 8.0 11.0-3 ................. 29.0 13.3.8-1 .............. 29.0 13.8.2-3 ................ 8.0 13.8.2-4 ................ 8.0 Section 13.0 Tab Section 13.4 Tab 13.8.2-5 ................ 8.0 13.0-1 ................. 29.0 13.4.1-1 .............. 29.0 13.8.3-1 ............. .30.0 13.0-2 ................. 29.0 13.4.1-2 ................ 8.0 Section 13.9 Tab 13.0-3 ................. 24.0 13.4.1-3 ................ 8.0 13.0-4 ................. 24.0 13.4.2-1 ................ 8.0 13.9.1-1 ................ 8.0 13.4.2-2 .............. 29.0 13.9.2-1 ................ 8.0 Section 13.1 Tab 13.4.3-1 .............. 29.0 13.9.3-1 .............. 24.0 13.1.1-1 ................ 8.0 13.4.3-2 .............. 12.0 13.9.3-2 .............. 24.0 13.1.2-1 .............. 24.0 13.4.4-1 .............. 24.0 13.9.4-1 ................ 8.0 13.1.2-2 .............. 24.0 13.4.5-1 ................ 8.0 13.9.5-1 ............. .37.0 13.1.3-1 .............. 29.0 13.4.5-2 ................ 8.0 13.9.5-2 .............. 37.0 13.1.3-2 .............. 24.0 13.9.6-1 ............. .44.0 Section 13.5 Tab 13.1.4-1 .............. 24.0 13.9.6-2 .............. 39.0 13.1.4-2 .............. 29.0 13.5.1-1 ................ 8.0 13.9.7-1 ................ 8.0 13.1.5-1 .............. 29.0 13.5.1-2 .............. 32.0 Section 13.12 Tab 13.1.5-2 ................ 9.0 13.5.1-3 .............. 17.0 13.1.6-1 .............. 24.0 13.12.1-1 ............ 24.0 Section 13.6 Tab 13.1.6-2 .............. 33.0 13.12.1-2 ............ 45.0 13.1.7-1 .............. 29.0 13.6.1-1 ................ 8.0 13.12.1-3 .............. 8.0 13.1.7-2 .............. 33.0 13.6.1-2 .............. 28.0 13.12.2-1 ............ 13.0 13.1.8-1 .............. 24.0 13.6.2-1 ................ 8.0 13.12.3-1 ........... .24.0 13.1.9-1 .............. 24.0 13.6.2-2 .............. 23.0 13.12.3-2 ........... .24.0 13.1.9-2 ................ 8.0 13.6.2-3 .............. 16.0 13.12.3-3 ........... .24.0 13.1.10-1 .............. 8.0 13.6.2-4 .............. 12.0 13.12.4-1 ............ 13.0 13.12.4-2 .............. 8.0 Section 13.3 Tab Section 13.7 Tab 13.3.1-1 .............. 34.0 13.7.1-1 ................ 8.0 Section 13.13 Tab 13.3.1-2 .............. 34.0 13.7.1-2 ................ 8.0 13.3.1-3 .............. 34.0 13.7.2-1 .............. 41.0 13.13.1-1 ............ 35.0 13.3.1-4 .............. 34.0 13.7.2-2 .............. 43.0 13.13.1-2 ............ 35.0 13.3.2-1 .............. 29.0 13.7.2-3 .............. 43.0 13.3.2-2 .............. 25.0 13.7.2-4 .............. 43.0 13.3.3-1 .............. 29.0 13.7.3-1 ................ 8.0 13.3.3-2 .............. 29.0 13.7.3-2 ................ 8.0 13.7.3-3 ................ 8.0 Farley Units 1 and 2 Page 1 of 1 Version 46.0 Technical Requirements

Table of Contents Note on section numbering: The TRM and TRM Bases numbering is intended to correspond to the associated ITS Specification. The numbering convention is to use the ITS Specification number, with the addition of a leading 1. For example, TRM spec 13.8, Electrical Power Systems, corresponds to ITS spec 3.8. Since all ITS specifications do not have associated TRM specifications, the TRM numbers do not run consecutively.

11.0 USE AND APPLICATION 11.1 Definitions ................................................................................................... 11.0-1 11.2 Logical Connectors ..................................................................................... 11.0-1 11.3 Completion Times....................................................................................... 11.0-1 11.4 Frequency................................................................................................... 11.0-1 11.5 Technical Requirement (TR) and Technical Requirement Surveillance (TRS) Implementation ............................................................ 11.0-1 11.6 Technical Requirement Manual Revisions ................................................. 11.0-2 11.7 Alternative Actions (e.g., Initiate a Condition Report, Continue Action to Restore, Determination of Alternate Course of Action) .............................. 11.0-2 13.0 TECHNICAL REQUIREMENT (TR) APPLICABILITY 13.0.1 .................................................................................................................... 13.0-1 13.0.2 .................................................................................................................... 13.0-1 13.0.3 .................................................................................................................... 13.0-1 13.0.4 .................................................................................................................... 13.0-1 13.0.5 .................................................................................................................... 13.0-2 13.0.7 .................................................................................................................... 13.0-2 13.0 TECHNICAL REQUIREMENT SURVEILLANCE (TRS) APPLICABILITY 13.0.1 .................................................................................................................... 13.0-3 13.0.2 .................................................................................................................... 13.0-3 13.0.3 .................................................................................................................... 13.0-3 13.0.4 .................................................................................................................... 13.0-3 13.1 REACTIVITY CONTROL SYSTEMS 13.1.1 SHUTDOWN MARGIN (SDM) - MODES 1and 2 ................................... 13.1.1-1 13.1.2 Boration Flow Path - Shutdown ............................................................... 13.1.2-1 13.1.3 Boration Flow Paths - Operating ............................................................. 13.1.3-1 13.1.4 Boration Pump - Shutdown...................................................................... 13.1.4-1 13.1.5 Charging Pumps - Operating ................................................................... 13.1.5-1 13.1.6 Borated Water Source - Shutdown .......................................................... 13.1.6-1 13.1.7 Borated Water Sources - Operating ........................................................ 13.1.7-1 13.1.8 Position Indication System - Shutdown ................................................... 13.1.8-1 13.1.9 Test Exception for Position Indication System - Shutdown ..................... 13.1.9-1 13.1.10 Rod Drop Time ...................................................................................... 13.1.10-1 13.3 INSTRUMENTATION 13.3.1 Movable Incore Detectors........................................................................ 13.3.1-1 13.3.2 High Energy Line Break Isolation Sensors .............................................. 13.3.2-1 13.3.3 Turbine Overspeed Protection................................................................. 13.3.3-1 (continued)

Farley Units 1 and 2 i Version 29.0 Technical Requirements

Table of Contents 13.3.4 Radiation Monitoring Instrumentation ...................................................... 13.3.4-1 13.3.5 Electric Hydrogen Recombiners Instrumentation and Control Circuits ........................................................................................ 13.3.5-1 13.3.6 Seismic Monitoring Instrumentation ........................................................ 13.3.6-1 13.3.7 Meteorological Monitoring Instrumentation.............................................. 13.3.7-1 13.3.8 Containment Hydrogen Monitors ............................................................. 13.3.8-1 13.4 REACTOR COOLANT SYSTEM (RCS) 13.4.1 Chemistry ................................................................................................ 13.4.1-1 13.4.2 Pressurizer .............................................................................................. 13.4.2-1 13.4.3 Reactor Vessel Head Vents .................................................................... 13.4.3-1 13.4.4 Safety Valves - Shutdown ....................................................................... 13.4.4-1 13.4.5 RCS Pressure Isolation Valve (PIV) Leakage ......................................... 13.4.5-1 13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 13.5.1 Emergency Core Cooling System (ECCS) .............................................. 13.5.1-1 13.6 CONTAINMENT SYSTEMS 13.6.1 Containment Ventilation System Leakage Rate ...................................... 13.6.1-1 13.6.2 Containment Isolation Valves .................................................................. 13.6.2-1 13.7 PLANT SYSTEMS 13.7.1 Steam Generator (SG) Pressure/Temperature Limitation ....................... 13.7.1-1 13.7.2 Snubbers ................................................................................................. 13.7.2-1 13.7.3 Sealed Source Contamination ................................................................. 13.7.3-1 13.7.4 The Ultimate Heat Sink (UHS) Support Structures.................................. 13.7.4-1 13.7.5 Area Temperature Monitoring (Unit 2 Only) ............................................ 13.7.5-1 13.8 ELECTRICAL POWER SYSTEMS 13.8.1 Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)............................................................................... 13.8.2-1 13.8.2 Emergency Diesel Generators (EDG) Maintenance and Inspection Requirements ......................................................................... 13.8.3-1 13.9 REFUELING OPERATIONS 13.9.1 Decay Time ............................................................................................. 13.9.1-1 13.9.2 Communications ...................................................................................... 13.9.2-1 13.9.3 Manipulator Crane ................................................................................... 13.9.3-1 13.9.4 Crane Travel - Spent Fuel Storage Building ........................................... 13.9.4-1 13.9.5 Spent Fuel Cask Crane ........................................................................... 13.9.5-1 13.9.6 Storage Pool Ventilation (fuel storage) .................................................... 13.9.6-1 13.9.7 Average Reactor Coolant Temperature................................................... 13.9.7-1 (continued)

Farley Units 1 and 2 ii Version 30.0 Technical Requirements

Table of Contents 13.12 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING (EGSTRAM) PROGRAM 13.12.1 Waste Gas Monitoring Instrumentation ................................................. 13.12.1-1 13.12.2 Liquid Holdup Tanks .............................................................................. 13.12.2-1 13.12.3 Waste Gas Monitoring ........................................................................... 13.12.3-1 13.12.4 Gas Storage Tanks................................................................................ 13.12.4-1 13.13 EMERGENCY RESPONSE FACILITIES 13.13.1 Emergency Response Facilities ............................................................ 13.13.1-1 Farley Units 1 and 2 iii Version 29.0 Technical Requirements

Use and Application 11.0 11.0 Use and Application 11.1 Definitions The definitions contained in the Technical Specifications Section 1.1, Definitions, apply to the Technical Requirements contained in this manual. In the Technical Requirements, defined terms are shown in all capital letters, consistent with the Technical Specifications. In addition, the following term is defined for the TRM and TRM Bases.

Functional/Functionality - Functionality is an attribute of Structures, Systems and Components (SSCs) that is not controlled by Technical Specifications (TSs). An SSC is functional or has functionality when it is capable of performing its specified function, as set forth in the Current Licensing Basis (CLB). Functionality does not apply to specified safety functions, but does apply to the ability of non-TS SSCs to perform other specified functions that have a necessary support function.

11.2 Logical Connectors The guidance provided for the use and application of logical connectors in Section 1.2, Logical Connectors, of the Technical Specifications is applicable to the Technical Requirements contained in this manual.

11.3 Completion Times The guidance provided for the use and application of Completion Times in Section 1.3, Completion Times, of the Technical Specifications is applicable to the Technical Requirements contained in this manual.

11.4 Frequency The guidance provided for the use and application of Frequency requirements in Section 1.4, Frequency, of the Technical Specifications is applicable to the Technical Requirements contained in this manual.

11.5 Technical Requirement (TR) and Technical Requirement Surveillance (TRS)

Implementation TRs and TRSs are implemented the same as Technical Specifications (see 13.0).

However, TRs and TRSs are treated as plant procedures and are not part of the Technical Specifications. Therefore the following exceptions apply:

a. Violations of the Action or Surveillance requirements in a TR are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72 or 10 CFR 50.73, unless specifically required by the TR.

(continued)

Farley Units 1 and 2 11.0 - 1 Version 22.0 Technical Requirements

Use and Application 11.0 11.0 Use and Application

b. Power reductions or plant shutdowns required to comply with the Actions of a TR or as a result of the application of TR 13.0.3 are not reportable per 10 CFR 50.72 or 10 CFR 50.73.

c. Violations of TR or TRS requirements, except as provided for in Section 13.0 of this manual, shall be treated the same as plant procedure violations.

11.6 Technical Requirement Manual Revisions Changes to this manual are controlled in accordance with 10 CFR 50.59.

11.7 Alternative Actions (e.g., Initiate a Condition Report, Continue Action to Restore, Determination of Alternate Course of Action)

Alternative Actions, such as initiating a condition report or management determination of alternate course of action are provided for selected TRs as alternatives to performing a plant shutdown if the nonfunctional TR cannot be restored within the allowed Completion Time. To ensure safe operation of the plant, priority should be on restoration of the nonfunctional TR to FUNCTIONAL within the allowed Completion Time. The alternative Actions to restoration of the TR to FUNCTIONAL are to provide allowances for a course of action that would continue to ensure the safe operation of the plant. Alternative Actions would allow for evaluation of the specific circumstances and plant conditions present at the time to determine if a safe alternative to a shutdown exists. Alternative Actions may be appropriate for situations where continued operation can be justified; for example, if the specified limits in the TR (e.g., RCS Chemistry or Pressurizer) were only slightly exceeded and sufficient margin is available, or if a Completion Time or Surveillance Frequency extension would allow the restoration of the limits or component FUNCTIONALITY, or if an alternate means for determining the FUNCTIONALITY of a component can be identified If the Alternative Action includes operation beyond the stated Completion Time, a plan for restoring the TR should be documented.

The plan for restoring the TR should consider:

The technical basis of the requirement,

The safety significance of continued operation beyond the stated Completion Time,

A qualitative or quantitative evaluation of the operational risk associated with the TR not being met (e.g., online or outage risk assessments or engineering technical justifications),

Farley Units 1 and 2 11.0 - 2 Version 29.0 Technical Requirements

Use and Application 11.0 11.0 Use and Application

If required, compensatory actions put in place during the time the TR is not met, and

Approval by the appropriate level of management prior to expiration of the Completion Time.

If the Alternate Action is taken it should be documented in a CR, ODMI, or other appropriate means and should contain the following:

The reason the TR could not be restored within the allowed Completion Time,

The results of the evaluation of operational risk,

Any compensatory measures, and

The operational conditions necessary to restore the TR to FUNCTIONAL.

The appropriate level of management is, as a minimum, the Shift Manager. However, the Shift Manager should consider the safety significance and operational risks associated with the nonfunctional TR and engage senior management in the decision to implement the alternative Action, as required.

Farley Units 1 and 2 11.0 - 3 Version 29.0 Technical Requirements

TR Applicability 13.0 13.0 Technical Requirement (TR) Applicability TR 13.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TR 13.0.2 and TR 13.0.7.

TR 13.0.2 Upon discovery of a failure to meet a TR, the Required Actions of the associated Conditions shall be met, except as provided in TR 13.0.5.

If the TR 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.

TR 13.0.3 When a TR is not met and the associated ACTIONS are not met or an associated ACTION is not provided, the unit shall be placed in a safe condition as determined by plant management. A Condition Report shall be initiated immediately.

TR 13.0.4 When a TR 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; (continued)

Farley Units 1 and 2 13.0 - 1 Version 29.0 Technical Requirements

TR Applicability 13.0 13.0 Technical Requirement (TR) Applicability TR 13.0.4 b. After performance of a risk assessment addressing nonfunctional (continued) 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 requirement are stated in the individual requirement, or

c. When an allowance is stated in the individual value, parameter, or other requirement.

This TR 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.

TR 13.0.5 Equipment removed from service or declared nonfunctional to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY or OPERABILITY of other equipment. This is an exception to TR 13.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.

TR 13.0.7 Test Exception TR 13.1.9 allows TR 13.1.8, Position Indication -

Shutdown to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TR requirements remain unchanged. Compliance with the Test Exception TR is optional. When the Test Exception TR is desired to be met but is not met, the ACTIONS of the Test Exception TR shall be met. When the Test Exception TR is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable TRs.

Farley Units 1 and 2 13.0 - 2 Version 29.0 Technical Requirements

TRS Applicability TRS 13.0 13.0 Technical Requirement Surveillance (TRS) Applicability TRS 13.0.1 TRSs shall be met during the MODES or other specified conditions in the Applicability for individual TRs, unless otherwise stated in the TRS.

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 TR. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the TR except as provided in TRS 13.0.3. Surveillances do not have to be performed on nonfunctional equipment or variables outside specified limits.

TRS 13.0.2 The specified Frequency for each TRS 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 requirement are stated in the individual TRSs.

TRS 13.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the TR 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 TR 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 TR must immediately be declared not met, and the applicable Condition(s) must be entered.

TRS 13.0.4 Entry into a MODE or other specified condition in the Applicability of a TR shall only be made when the TR's Surveillances have been met within (continued)

Farley Units 1 and 2 13.0-3 Version 24.0 Technical Requirements

TRS Applicability TRS 13.0 13.0 Technical Requirement Surveillance (TRS) Applicability TRS 13.0.4 their specified Frequency, except as provided by TRS 13.0.3. When a TR (continued) 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 TR 13.0.4.

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.

Farley Units 1 and 2 13.0-4 Version 24.0 Technical Requirements

SDM MODES 1 and 2 TR 13.1.1 13.1 Reactivity Control Systems TR 13.1.1 SHUTDOWN MARGIN (SDM) - MODES 1 AND 2 TR 13.1.1 SDM shall be within the limits provided in the COLR.

APPLICABILITY: MODE 1 and MODE 2 with keff 1.0 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore Immediately SDM to within limit.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.1.1 Verify SDM within limit with the control banks at the Prior to initial maximum insertion limit specified in the COLR and operation above 5%

considering the following factors: RTP after each fuel loading.

1) RCS boron concentration,

2) Control rod position,

3) RCS average temperature,

4) Fuel burnup based on gross thermal energy generation,

5) Xenon concentration, and

6) Samarium concentration Farley Units 1 and 2 13.1.1 - 1 Version 8.0 Technical Requirements

Boration Flow Path - Shutdown TR 13.1.2 13.1 Reactivity Control Systems TR 13.1.2 Boration Flow Path - Shutdown TR 13.1.2 One of the following boron injection flow paths shall be FUNCTIONAL:

a. A flow path from a FUNCTIONAL boric acid storage tank via a boric acid transfer pump and a charging pump to the Reactor Coolant System, or

b. In MODE 6 only, a flow path from a FUNCTIONAL boric acid storage tank via a boric acid transfer pump through an idle charging pump to the Reactor Coolant System, or

c. A flow path from the FUNCTIONAL Refueling Water Storage Tank via a charging pump to the Reactor Coolant System.

APPLICABILITY: MODE 5, MODE 6 with any valve used to isolate an unborated water source not secured in the closed position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Flow Path A.1 Suspend CORE Immediately nonfunctional. ALTERATIONS.

AND A.2 Suspend positive reactivity Immediately changes.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.2.1 ---------------------------------NOTE--------------------------------

Only required to be performed when a flow path from the boric acid storage tanks is required FUNCTIONAL and the ambient air temperature of the auxiliary building is < 65 °F.

Verify that the temperature of the flow path is 65 °F. 7 days Farley Units 1 and 2 13.1.2 - 1 Version 24.0 Technical Requirements

Boration Flow Path - Shutdown TR 13.1.2 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.2.2 Verify that each manual, power operated, or automatic 31 days valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

TRS 13.1.2.3 ---------------------------------NOTE--------------------------------

Only required to be performed when the boric acid transfer pump is required FUNCTIONAL.

Verify that, on recirculation flow, the boric acid transfer 31 days pump develops a discharge pressure of 100 psig.

Farley Units 1 and 2 13.1.2 - 2 Version 24.0 Technical Requirements

Boration Flow Paths - Operating TR 13.1.3 13.1 Reactivity Control Systems TR 13.1.3 Boration Flow Paths - Operating TR 13.1.3 Two of the following three boron injection flow paths shall be FUNCTIONAL.

a. The flow path from the boric acid storage tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System.

b. Two flow paths from the Refueling Water Storage Tank via charging pumps to the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required flow path A.1 Restore at least two required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months nonfunctional in MODE 1 flow paths to FUNCTIONAL or 2. status.

B. One required flow path B.1 Restore at least two required 7 days nonfunctional in MODE 3 flow paths to FUNCTIONAL or 4. status.

C. Required Actions and C.1 Initiate a Condition Report. Immediately associated Completion Times not met. AND C.2 Continue action to restore Immediately the required flow path to FUNCTIONAL status.

Farley Units 1 and 2 13.1.3 - 1 Version 29.0 Technical Requirements

Boration Flow Paths - Operating TR 13.1.3 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.3.1 ---------------------------------NOTE--------------------------------

Only required to be performed when a flow path from the boric acid storage tanks is required FUNCTIONAL and the ambient air temperature of the auxiliary building is < 65 °F.

Verify that the temperature of the flow path from the 7 days boric acid tanks is 65 °F.

TRS 13.1.3.2 Verify that each manual, power operated, or automatic 31 days valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

TRS 13.1.3.3 ---------------------------------NOTE--------------------------------

Only required to be performed when the boric acid transfer pump is required FUNCTIONAL.

Verify that, on recirculation flow, the boric acid transfer 31 days pump develops a discharge pressure of 100 psig.

TRS 13.1.3.4 Verify required flow path from boric acid storage tanks While proceeding to delivers 30 gpm to the Reactor Coolant System. or in MODE 5 if not performed in the previous 12 months Farley Units 1 and 2 13.1.3 - 2 Version 24.0 Technical Requirements

Boration Pump - Shutdown TR 13.1.4 13.1 Reactivity Control Systems TR 13.1.4 Boration Pump - Shutdown TR 13.1.4 The required boration pump (charging or boric acid transfer) in the boron injection flow path required by TR 13.1.2 shall be FUNCTIONAL and capable of being powered from an OPERABLE emergency bus.

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

The boric acid transfer pump may only be used in place of the charging pump in MODE 6 consistent with flow path b. in TR 13.1.2.

APPLICABILITY: MODE 5, MODE 6 with any valve used to isolate an unborated water source not secured in the closed position.

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

The requirement to have only one charging pump FUNCTIONAL is only applicable when one or more of the RCS cold legs is 180°F; however, while in this condition, two charging pumps may be capable of injecting into the RCS during pump swap operations for a period of no more than 15 minutes provided that the RCS is in a non-water solid condition and both RHR relief valves are OPERABLE or the RCS is vented via an opening of no less than 5.7 square inches in area.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required charging pump A.1 Suspend CORE Immediately nonfunctional. ALTERATIONS.

AND A.2 Suspend operations Immediately involving positive reactivity changes.

Farley Units 1 and 2 13.1.4 - 1 Version 24.0 Technical Requirements

Boration Pump - Shutdown TR 13.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. More than one charging B.1 Initiate action to render all Immediately pump capable of injecting but the above required into the RCS, except as FUNCTIONAL pump allowed during pump inoperable as specified in swap operations. Technical Specifications SR 3.4.12.1.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.4.1 ---------------------------------NOTE--------------------------------

Not required to be performed when the RCS is in a water solid condition.

Verify that, on recirculation flow, the charging pump In Accordance with required by TR 13.1.2 develops a differential pressure the Inservice Testing of 2323 psid. Program TRS 13.1.4.2 TRS 13.1.2.3. is applicable when the boric acid transfer In accordance with pump is required FUNCTIONAL. TRS 13.1.2.3 Farley Units 1 and 2 13.1.4 - 2 Version 29.0 Technical Requirements

Charging Pumps - Operating TR 13.1.5 13.1 Reactivity Control Systems TR 13.1.5 Charging Pumps - Operating TR 13.1.5 Two charging pumps shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required charging A.1 Restore at least two 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump nonfunctional in charging pumps to MODE 1 or 2. FUNCTIONAL status.

B. One required charging B.1 Restore at least two 7 days pump nonfunctional in charging pumps to MODE 3 or 4. FUNCTIONAL status.

C. Required Action and C.1 Initiate a Condition Report. Immediately associated Completion Time not met. AND C.2 Continue action to restore Immediately the required charging pump to FUNCTIONAL status.

Farley Units 1 and 2 13.1.5 - 1 Version 29.0 Technical Requirements

Charging Pumps - Operating TR 13.1.5 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.5.1 Verify that, on recirculation flow, each required charging In Accordance with pump develops a differential pressure of 2323 psid. the Inservice Testing Program Farley Units 1 and 2 13.1.5 - 2 Version 9.0 Technical Requirements

Borated Water Source - Shutdown TR 13.1.6 13.1 Reactivity Control Systems TR 13.1.6 Borated Water Source - Shutdown TR 13.1.6 One of the following borated water sources shall be FUNCTIONAL:

a. A boric acid storage system, or

b. The refueling water storage tank (RWST)

APPLICABILITY: MODE 5, MODE 6 with any valve used to isolate an unborated water source not secured in the closed position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required borated water A.1 Suspend CORE Immediately source nonfunctional. ALTERATIONS AND A.2 Suspend positive reactivity Immediately changes.

TECHNICAL REQUIREMENT SURVEILLANCES

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

1. TRS 13.1.6.1, TRS 13.1.6.2, and TRS 13.1.6.3 are only required to be performed when the RWST is the required borated water source.

2. TRS 13.1.6.4, TRS 13.1.6.5, and TRS 13.1.6.6 are only required to be performed when the boric acid storage tank is the required borated water source.

Farley Units 1 and 2 13.1.6 - 1 Version 24.0 Technical Requirements

Borated Water Source - Shutdown TR 13.1.6 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.6.1 --------------------------------NOTE---------------------------------

Only required to be performed when the outside air temperature is 35 F.

Verify RWST solution temperature is 35 F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRS 13.1.6.2 Verify the RWST boron concentration is 2,300 ppm. 7 days TRS 13.1.6.3 Verify RWST borated water volume is 30,000 gallons. 7 days TRS 13.1.6.4 Verify the boric acid storage tank solution temperature 7 days is 65 F.

TRS 13.1.6.5 Verify the boron concentration of the boric acid tank 31 days solution is between 7,000 ppm and 7,700 ppm.

TRS 13.1.6.6 Verify the contained borated water volume in the boric 7 days acid storage tank is 2,000 gallons.

Farley Units 1 and 2 13.1.6 - 2 Version 33.0 Technical Requirements

Borated Water Sources - Operating TR 13.1.7 13.1 Reactivity Control Systems TR 13.1.7 Borated Water Sources - Operating TR 13.1.7 The following borated water source(s) shall be FUNCTIONAL as required by TR 13.1.3:

a. A Boric acid storage system, and

b. The refueling water storage tank (RWST).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required boric acid A.1 Restore boric acid storage 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months storage system system to FUNCTIONAL nonfunctional in MODE 1 status.

or 2.

B. Required boric acid B.1 Restore the boric acid 7 days storage system storage system to nonfunctional in MODE 3 FUNCTIONAL status.

or 4.

C. Required Actions and C.1 Initiate a Condition Report. Immediately associated Completion Times of Condition A or B AND not met.

C.2 Continue action to restore Immediately the boric acid storage system to FUNCTIONAL status.

Farley Units 1 and 2 13.1.7 - 1 Version 29.0 Technical Requirements

Borated Water Sources - Operating TR 13.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. RWST nonfunctional. D.1 Enter applicable Conditions Immediately of RWST Technical Specification 3.5.4.

TECHNICAL REQUIREMENT SURVEILLANCES

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

1. TRS 13.1.7.1 is only required to be performed when the RWST is the required borated water source.

2. TRS 13.1.7.2, TRS 13.1.7.3, and TRS 13.1.7.4 are only required to be performed when the boric acid storage tank is the required borated water source.

SURVEILLANCE FREQUENCY TRS 13.1.7.1 When the RWST is required to be FUNCTIONAL, the In accordance with SRs of Technical Specification 3.5.4 are applicable. applicable SRs.

TRS 13.1.7.2 Verify the boric acid storage system solution 7 days temperature is 65 F.

TRS 13.1.7.3 Verify the boron concentration of the boric acid storage 31 days system solution is between 7,000 ppm and 7,700 ppm.

TRS 13.1.7.4 Verify the contained borated water volume in the boric 7 days acid storage system is 11,336 gallons.

Farley Units 1 and 2 13.1.7 - 2 Version 33.0 Technical Requirements

Position Indication System - Shutdown TR 13.1.8 13.1 Reactivity Control Systems TR 13.1.8 Position Indication System - Shutdown TR 13.1.8 One digital rod position indication (DRPI) channel (excluding demand position indication) shall be FUNCTIONAL and capable of determining the control rod position within +/- 12 steps for each shutdown or control rod not fully inserted.

APPLICABILITY: When the reactor trip breakers are closed and Rod Control System capable of rod withdrawal in MODES 3, 4, or 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required DRPI channel A.1 Open the reactor trip system Immediately for one or more shutdown breakers.

or control rods nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.8.1 For each DRPI channel required FUNCTIONAL, verify 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the demand position indication system and the DRPI channels agree to within +/- 12 steps.

Farley Units 1 and 2 13.1.8 - 1 Version 24.0 Technical Requirements

Test Exception for Position Indication System - Shutdown TR 13.1.9 13.1 Reactivity Control Systems TR 13.1.9 Test Exception for Position Indication System - Shutdown TR 13.1.9 The requirements of TR 13.1.8, Position Indication System - Shutdown, may be suspended during the performance of individual shutdown and control rod drop time measurements provided:

a. Only one shutdown or control bank is withdrawn from the fully inserted position at a time, and

b. The DRPI is FUNCTIONAL during the withdrawal of the rods.

APPLICABILITY: During performance of rod drop time measurements in MODES 3, 4, or 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Open the reactor trip Immediately DRPI nonfunctional during breakers.

rod withdrawal.

OR More than one bank of rods withdrawn.

Farley Units 1 and 2 13.1.9 - 1 Version 24.0 Technical Requirements

Test Exception for Position Indication System - Shutdown TR 13.1.9 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.9.1 Verify the demand position indication system and the Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior rod position indication system agree: to initiation of rod drop time

a. Within 12 steps when the rods are stationary, and measurements

b. Within 24 steps during rod motion. AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Farley Units 1 and 2 13.1.9 - 2 Version 8.0 Technical Requirements

Rod Drop Time TR 13.1.10 13.1 Reactivity Control Systems TR 13.1.10 Rod Drop Time TR 13.1.10 The individual rod drop time of each rod affected by maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods shall be within limits.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rods, A.1 Restore rod drop time to Prior to reactor affected by maintenance within limits. criticality on or modification to the control rod drive system which could affect the drop time, with rod drop time not within limits TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.10.1 Verify, for specifically affected individual rods, rod drop Prior to reactor time of each rod, from the fully withdrawn position, is criticality, following 2.7 seconds from the beginning of decay of stationary maintenance on or gripper coil voltage to dashpot entry, with: modification to the control rod drive

a. Tavg 541 °F; and system which could affect the drop time

b. All reactor coolant pumps operating. of those specific rods Farley Units 1 and 2 13.1.10 - 1 Version 8.0 Technical Requirements

Movable Incore Detectors TR 13.3.1 13.3 Instrumentation TR 13.3.1 Movable Incore Detectors TR 13.3.1 The movable incore detection system shall be FUNCTIONAL with:

1.1 38 detector thimbles, with 2 detector thimbles per quadrant as identified in Figure 13.3.1-1, OR 1.2 32 and < 38 detector thimbles, with 3 detector thimbles per quadrant as identified in Figures 13.3.1-1 and 13.3.1-2, OR 1.3 25 and < 32 detector thimbles, with 4 detector thimbles per quadrant as identified in Figures 13.3.1-1 and 13.3.1-2.

AND

2. Sufficient movable detectors, drives, and readout equipment to map these thimbles.

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

1. 38 detector thimbles, with 2 detector thimbles per quadrant as identified in Figure 13.3.1-1 are required during initial startup after a refueling outage up to and including performance of the first flux map at 100% RTP. An exception is discussed in the Bases for TR 13.3.1 for recalibration of the excore neutron flux detection system and for monitoring QPTR. However, a flux map with 38 detector thimbles, with 2 detector thimbles per quadrant as identified in Figure 13.3.1-1 is still required prior to reaching 50% RTP to detect a core misload event.

2. If a detector thimble is located on either the major axes of Figure 13.3.1-1 or minor axes of Figure 13.3.1-2, the detector thimble can be included in both quadrants that are divided by the axis for the purpose of determining the minimum number of detector thimbles per core quadrant.

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the excore neutron flux detection system, or

b. Monitoring the Quadrant Power Tilt Ratio (QPTR), or

c. Measurement of FNH , FQ (Z) and Fxy .

Farley Units 1 and 2 13.3.1 - 1 Version 34.0 Technical Requirements

Movable Incore Detectors TR 13.3.1 ACTIONS

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

1. TR 13.0.3 is not applicable.

2. TR 13.0.4c is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Movable incore detection A.1 Restore the movable incore Prior to using the system nonfunctional. detection system to system for the above FUNCTIONAL status. listed monitoring and calibration functions.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.1.1 Verify movable incore system FUNCTIONALITY by During use when normalizing each required detector output. required for the above listed monitoring and calibration functions Farley Units 1 and 2 13.3.1 - 2 Version 34.0 Technical Requirements

Movable Incore Detectors TR 13.3.1 Figure 13.3.1-1 Movable Incore Detector Locations in Major Axes Quadrants Farley Units 1 and 2 13.3.1 - 3 Version 34.0 Technical Requirements

Movable Incore Detectors TR 13.3.1 Figure 13.3.1-2 Movable Incore Detector Locations in Minor Axes Quadrants (For use with TR 13.3.1 option for 25 and < 38 thimbles)

Farley Units 1 and 2 13.3.1 - 4 Version 34.0 Technical Requirements

High Energy Line Break Isolation Sensors TR 13.3.2 13.3 Instrumentation TR 13.3.2 High Energy Line Break Isolation Sensors TR 13.3.2 The high energy line break isolation instrumentation channels listed in Table 13.3.2-1 shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2 and 3.

ACTIONS

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

Separate Condition entry is allowed for each isolation Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required high A.1 Restore the nonfunctional 7 days energy line break isolation channel to FUNCTIONAL instrumentation channels status.

nonfunctional.

B. Required Action and B.1 Initiate a Condition Report. Immediately associated Completion Time of Condition A not AND met.

B.2 Continue action to restore Immediately the required channel(s) to FUNCTIONAL status.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.2.1 Perform a COT on each required instrument channel In accordance with listed in Table 13.3.2-1. Table 13.3.2-1.

Farley Units 1 and 2 13.3.2 - 1 Version 29.0 Technical Requirements

High Energy Line Break Isolation Sensors TR 13.3.2 Table 13.3.2-1 High-Energy Line Break Isolation Instrumentation Instrument Channel Sensor Location Required Surveillance Channels Frequency

1. Pressure Switches

a. PDSH 3367 A,B RHR Heat Exchanger Room El. 83 ft. 1

b. PSH 2850 A,D Auxiliary Feedwater Pump Room El. 100 ft. 1 B,F Equipment Room El. 100 ft. 1 C,E Auxiliary Feedwater Pump Room Corridor El. 1 100 ft.

c. PSH 2851 A,F Recycle Holdup Tank Room El. 121 ft. 1 B,C Moderating Heat Exchanger Room El. 121 ft. 1 D,E Moderating Heat Exchanger Valve Room El. 1 121 ft.

d. PSH 2852 A,H Piping Penetration Room El. 100 ft. 1 B,C, Letdown Heat Exchanger Room El. 100 ft. 1 18 months D,E Recycle Holdup Tank Room El. 121 ft. 1 F,G

e. PSH 2853 A,B Piping Penetration Room El. 121 ft. 1 C,D Blowdown Heat Exchanger Room El. 130 ft. 1 E,F Corridor El. 121 ft. (Unit 1) / Recycle Evaporator 1 Room El. 121 ft. (Unit 2)

f. PSH 2853 G,H Recycle Evaporator Room El. 121 ft. 1 I,J Corridor El. 121 ft. (I) and 1 Sluice Filter Room El. 121 ft. (J - Unit 1) /

Blowdown Surge Tank Room El. 130 ft. (J -

Unit 2)

2. Flooding Detectors

a. LSH 2828 Main Steam Room El. 127 ft. 2 36 months A,B,C Main Steam Room El. 127 ft. 2

b. LSH 2829 A,B,C Farley Units 1 and 2 13.3.2 - 2 Version 25.0 Technical Requirements

Turbine Overspeed Protection TR 13.3.3 13.3 Instrumentation TR 13.3.3 Turbine Overspeed Protection TR 13.3.3 At least one turbine overspeed protection system shall be FUNCTIONAL.

APPLICABILITY: MODE 1 MODES 2 and 3 except when all main steam line isolation valves and associated bypass valves are closed and all other steam flow paths to the turbine are isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One stop valve or one A.1 Restore nonfunctional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months governor valve on one or valve(s) to FUNCTIONAL more high pressure status.

turbine steam lines nonfunctional. OR A.2 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months steampath(s).

OR A.3 Plant management to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months determine an alternate course of action that continues to assure the safe operation of the plant.

Farley Units 1 and 2 13.3.3 - 1 Version 29.0 Technical Requirements

Turbine Overspeed Protection TR 13.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One reheat stop valve or B.1 Restore nonfunctional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reheat intercept valve valve(s) to FUNCTIONAL on one or more low status.

pressure turbine steam lines nonfunctional. OR B.2 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months steampath(s).

OR B.3 Plant management to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months determine an alternate course of action that continues to assure the safe operation of the plant.

C. Required Action and C.1 Isolate the turbine from the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion steam supply.

Time of Condition A or B not met. OR OR C.2 Plant management to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months determine an alternate Turbine overspeed course of action that protection system continues to assure the safe nonfunctional for reasons operation of the plant.

other than Condition A or B.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.3.1 The provisions of TRS 13.0.4 are not applicable. N/A Farley Units 1 and 2 13.3.3 - 2 Version 29.0 Technical Requirements

Radiation Monitoring Instrumentation TR 13.3.4 13.3 Instrumentation TR 13.3.4 Radiation Monitoring Instrumentation TR 13.3.4 The radiation monitoring instrumentation channels listed in Table 13.3.4-1 shall be FUNCTIONAL with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 13.3.4-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radiation A.1 Adjust the setpoint(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months monitoring channel(s) with within the limit.

alarm/trip setpoint exceeding limit. OR A.2 DecIare the channel(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months nonfunctional.

B. The fuel storage pool area B.1 ------------NOTE-----------------

(R-5) radiation monitoring The first performance of TRS channel nonfunctional. 13.3.4.1 is not required to be completed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after R-5 is declared nonfunctional.

Initiate action to perform Immediately TRS 13.3.4.1 and continue at required frequency until the fuel storage pool area (R-5) radiation monitoring channel is returned to FUNCTIONAL status.

Farley Units 1 and 2 13.3.4 - 1 Version 24.0 Technical Requirements

Radiation Monitoring Instrumentation TR 13.3.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. The plant vent stack C.1 Initiate the preplanned 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months effluent (R-29B) radiation alternate method of monitoring monitoring channel the appropriate parameter(s).

nonfunctional.

OR AND One or more main steam C.2 Restore the nonfunctional 7 days line (R-60A, B or C) channel(s) to FUNCTIONAL radiation monitoring status.

channels nonfunctional.

OR One or more turbine building ventilation exhaust (R-15 B or C) radiation monitoring channel(s) nonfunctional.

D. Required Action and D.1 Initiate a Condition Report. Immediately associated Completion Time of Condition C not AND met.

D.2 Continue action to restore the Immediately radiation monitoring channel(s) to FUNCTIONAL status.

Farley Units 1 and 2 13.3.4 - 2 Version 45.0 Technical Requirements

Radiation Monitoring Instrumentation TR 13.3.4 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.4.1 ------------------------------NOTE-----------------------------------

Only required to be performed when the fuel storage pool area radiation monitoring channel (R-5) is nonfunctional.

Perform area surveys of the monitored area with portable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months monitoring instrumentation.

TRS 13.3.4.2 ----------------------------NOTE-------------------------------------

Refer to Table 13.3.4-1 to determine which SRs apply for each radiation monitor channel.

Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TRS 13.3.4.3 ----------------------------NOTE-------------------------------------

Refer to Table 13.3.4-1 to determine which SRs apply for each radiation monitor channel.

Perform a COT. 92 days TRS 13.3.4.4 ----------------------------NOTE-------------------------------------

Refer to Table 13.3.4-1 to determine which SRs apply for each radiation monitor channel.

Perform a CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 13.3.4 - 3 Version 24.0 Technical Requirements

Radiation Monitoring Instrumentation TR 13.3.4 Table 13.3.4-1 Radiation Monitoring Instrumentation Radiation Monitoring Applicable Alarm/Trip Required Technical Instrument Channel Modes or Setpoint Channels Requirement Other Surveillance specified Conditions

1. Area Monitors

a. Fuel Storage Pool With fuel in 15 mr/hr 1 TRS 13.3.4.1(Note 1)

Area (R-5) the storage TRS 13.3.4.2 pool TRS 13.3.4.3 TRS 13.3.4.4

2. Process Monitors (Noble Gas Effluent Monitors)

a. Plant Vent Stack 1, 2, 3, 4 N/A 1 TRS 13.3.4.2 Effluent Monitor TRS 13.3.4.4 (R-29B)

b. Main Steam 1, 2, 3 N/A 3 TRS 13.3.4.2 Line (R-60A, B, C) TRS 13.3.4.4

c. Turbine Building 1, and N/A 2 TRS 13.3.4.2 Ventilation With vacuum TRS 13.3.4.4 Exhaust in the (includes condenser condenser air ejector exhaust)

(R-15 B and C)

Note 1: Only required to be performed when the fuel storage pool area radiation monitoring channel (R-5) is nonfunctional.

Farley Units 1 and 2 13.3.4 - 4 Version 40.0 Technical Requirements

Electric Hydrogen Recombiners Instrumentation and Control Circuits TR 13.3.5 13.3 Instrumentation TR 13.3.5 Electric Hydrogen Recombiners Instrumentation and Control Circuits TR 13.3.5 The electric hydrogen recombiner instrumentation and control circuits shall be in calibration.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more electric A.1 Initiate action to restore the Immediately hydrogen recombiner circuit(s) to within calibration instrumentation or control limits.

circuit(s) not in calibration.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.5.1 Perform a CHANNEL CALIBRATION of all recombiner 18 months instrumentation and control circuits.

Farley Units 1 and 2 13.3.5 - 1 Version 8.0 Technical Requirements

Seismic Monitoring Instrumentation TR 13.3.6 13.3 Instrumentation TR 13.3.6 Seismic Monitoring Instrumentation TR 13.3.6 The seismic monitoring instrumentation shown in Table 13.3.6-1 shall be FUNCTIONAL.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Initiate action to restore the Immediately seismic monitoring seismic monitoring instrument channels instrument channel(s) to nonfunctional. FUNCTIONAL status.

B. One or more seismic B.1 Initiate action to retrieve and Immediately monitoring instruments analyze data from the actuated during a seismic actuated seismic monitoring event. instruments to determine the magnitude of the vibratory ground motion.

AND B.2 Restore affected seismic 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months monitoring instruments to FUNCTIONAL status.

AND B.3 Perform a CHANNEL 5 days CALIBRATION on the actuated seismic monitoring instruments.

Farley Units 1 and 2 13.3.6 - 1 Version 45.0 Technical Requirements

Seismic Monitoring Instrumentation TR 13.3.6 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.6.1 Perform a CHANNEL CHECK. 184 days TRS 13.3.6.2 Perform a CHANNEL OPERATIONAL TEST. 184 days TRS 13.3.6.3 Perform a CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 13.3.6 - 2 Version 46.0 Technical Requirements

Seismic Monitoring Instrumentation TR 13.3.6 Table 13.3.6-1 Seismic Monitoring Instrumentation Instrumentation Sensor Location Measurement Range Required Channels Number Strong Motion Triaxial Accelographs 1A Containment Base(1) .5g full scale 1 1B Containment(1) 1.0g full scale 1 1C Free Field .5g full scale 1 2 Pond Intake Structure .5g full scale 1 3 Diesel Generator Building .5g full scale 1 Notes:

(1) Sensor located in Unit 1.

Farley Units 1 and 2 13.3.6 - 3 Version 29.0 Technical Requirements

Meteorological Monitoring Instrumentation TR 13.3.7 13.3 Instrumentation TR 13.3.7 Meteorological Monitoring Instrumentation TR 13.3.7 The meteorological monitoring instrumentation shown in Table 13.3.7-1 shall be FUNCTIONAL.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Initiate action to restore the Immediately meteorological monitoring meteorological monitoring instrument channels instrument channel(s) to nonfunctional. FUNCTIONAL status.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.7.1 Perform a CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRS 13.3.7.2 ----------------------------NOTE-------------------------------------

CHANNEL CALIBRATIONS for the wind speed instruments shall be performed according to the manufacturers recommendations.

Perform a CHANNEL CALIBRATION. 184 days Farley Units 1 and 2 13.3.7 - 1 Version 29.0 Technical Requirements

Meteorological Monitoring Instrumentation TR 13.3.7 Table 13.3.7-1 Meteorological Monitoring Instrumentation Instrument Required Channels

1. WINDSPEED

a. Meteorological tower, 10 m/32.8 ft 1 of 2

b. Meteorological tower, 45.7 m/150 ft 1 of 2

2. WIND DIRECTION

a. Meteorological tower, 10 m/32.8 ft 1 of 2

b. Meteorological tower, 45.7 m/150 ft 1 of 2

3. AIR TEMPERATURE DIFFERENCE

a. Meteorological tower, 60 m 10 m (196.9 ft to 32.8 ft) 1 of 2 Notes:

All heights are nominal above ground level (AGL).

There are two channels of each of the instruments listed in the table above (the second channel is mounted at the same height).

Farley Units 1 and 2 13.3.7 - 2 Version 29.0 Technical Requirements

Containment Hydrogen Monitors TR 13.3.8 13.3 Instrumentation TR 13.3.8 Containment Hydrogen Monitors TR 13.3.8 Two containment hydrogen monitor instrumentation channels shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Initiate action to restore the Immediately hydrogen monitor containment hydrogen instrument channels monitor instrument nonfunctional. channel(s) to FUNCTIONAL status.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.8.1 Perform a CHANNEL CHECK. 31 days TRS 13.3.8.2 Perform a CHANNEL CALIBRATION. 18 months Farley Units 1 and 2 13.3.8 - 1 Version 29.0 Technical Requirements

RCS Chemistry TR 13.4.1 13.4 Reactor Coolant System (RCS)

TR 13.4.1 Chemistry TR 13.4.1 Reactor Coolant System chemistry shall be maintained within the limits specified in Table 13.4.1-1.

APPLICABILITY: At all times, except for dissolved oxygen when Tavg 250 °F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more chemistry A.1 Restore parameter to within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters > steady- steady-state limit.

state limit and transient limit in MODES 1, 2, 3, or 4.

B. One or more chemistry B.1 Plant management to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months parameters > transient determine an alternate limit in MODES 1, 2, 3, or course of action that

4. continues to assure the safe operation of the plant.

OR OR Required Action and associated Completion B.2.1 Be in Mode 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Time of Condition A not met. AND B.2.2 Be in Mode 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Farley Units 1 and 2 13.4.1 - 1 Version 29.0 Technical Requirements

RCS Chemistry TR 13.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE------------ C.1 Initiate action to reduce the Immediately All Required Actions must pressurizer pressure to be completed whenever 500 psig.

this Condition is entered.

AND Chloride or fluoride C.2 Perform an engineering Prior to increasing concentration > steady- evaluation to determine the pressurizer pressure state limit for > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months effects of the out-of-limit > 500 psig.

in any condition other than condition on the structural MODES 1, 2, 3, or 4. integrity of the Reactor OR Coolant System.

OR Prior to entering MODE 4.

Chloride or fluoride concentration > transient limit in any condition other AND than MODES 1, 2, 3, or 4.

C.3 Determine that the Reactor Prior to increasing Coolant System remains pressurizer pressure acceptable for continued > 500 psig.

operation.

OR Prior to entering MODE 4.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.1.1 ---------------------------------NOTE--------------------------------

Not required to be performed for dissolved oxygen when Tavg 250 °F.

Verify Reactor Coolant System chemistry within limits 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months specified on Table 3.4.1-1.

Farley Units 1 and 2 13.4.1 - 2 Version 8.0 Technical Requirements

RCS Chemistry TR 13.4.1 Table 13.4.1-1 Reactor Coolant System Chemistry Limits PARAMETER STEADY-STATE LIMIT TRANSIENT LIMIT Dissolved Oxygen (a) 0.10 ppm 1.00 ppm Chloride 0.15 ppm 1.50 ppm Fluoride 0.15 ppm 1.50 ppm (a)

Limits not applicable when Tavg 250 °F.

Farley Units 1 and 2 13.4.1 - 3 Version 8.0 Technical Requirements

Pressurizer TR 13.4.2 13.4 Reactor Coolant System TR 13.4.2 Pressurizer TR 13.4.2 The pressurizer temperature shall be limited to:

a. A maximum heatup of 100 °F in any 1-hour period,

b. A maximum cooldown of 200 °F in any 1-hour period, and

c. A maximum spray water temperature differential of 320 °F.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1 Restore pressurizer 30 minutes All Required Actions must temperature to within limits.

be completed whenever this Condition is entered. AND A.2 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Pressurizer temperature evaluation to determine the not within limits. effects of the out-of-limit condition on the structural integrity of the pressurizer.

AND A.3 Determine that the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pressurizer remains acceptable for continued operation.

Farley Units 1 and 2 13.4.2 - 1 Version 8.0 Technical Requirements

Pressurizer TR 13.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Plant management to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion determine an alternate Time not met. course of action that continues to assure the safe operation of the plant.

OR B.2.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2.2 Reduce pressurizer pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months to < 500 psig.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.2.1 --------------------------------NOTE---------------------------------

Only required to be performed during system heatup and cooldown.

Verify pressurizer heatup and cooldown rates are within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits.

TRS 13.4.2.2 ---------------------------------NOTE--------------------------------

Only required to be performed during auxiliary spray operation.

Verify the spray water temperature differential is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limit.

Farley Units 1 and 2 13.4.2 - 2 Version 29.0 Technical Requirements

Reactor Vessel Head Vents TR 13.4.3 13.4 Reactor Coolant System (RCS)

TR 13.4.3 Reactor Vessel Head Vents TR 13.4.3 At least one of the two reactor vessel head vent system paths, consisting of two valves in series powered from the Auxiliary Building D. C. Distribution System, shall be FUNCTIONAL and closed.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Both reactor vessel head A.1 Initiate action to maintain the Immediately vent system paths nonfunctional vent paths nonfunctional. closed with power removed from the valve actuators of all valves in the nonfunctional vent paths.

AND A.2 Restore the at least one vent 30 days path to FUNCTIONAL status.

B. Required Action and B.1 Initiate a Condition Report. Immediately associated Completion Time not met. AND B.2 Continue action to restore Immediately the required vent path(s) to FUNCTIONAL status.

Farley Units 1 and 2 13.4.3 - 1 Version 29.0 Technical Requirements

Reactor Vessel Head Vents TR 13.4.3 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.3.1 Verify each valve in the vent system operates through 18 months one complete cycle of full travel from the control room during MODE 5 or 6.

TRS 13.4.3.2 Verify flow through the reactor vessel head vent 18 months systems by venting during MODE 5 or 6.

Farley Units 1 and 2 13.4.3 - 2 Version 12.0 Technical Requirements

Safety Valves - Shutdown TR 13.4.4 13.4 Reactor Coolant System (RCS)

TR 13.4.4 Safety Valves - Shutdown TR 13.4.4 A minimum of one pressurizer code safety valve shall be FUNCTIONAL with a lift setting of 2485 psig +/- 1%.

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

The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

APPLICABILITY: MODE 4 ACTIONS

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

TR 13.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required pressurizer code A.1 Suspend all operations Immediately safety valve involving positive reactivity nonfunctional. changes AND A.2 Initiate action to place an Immediately FUNCTIONAL RHR loop into operation in the shutdown cooling mode.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.4.1 Verify requirements of the Inservice Testing Plan are In Accordance with met for the required pressurizer code safety valve. the Inservice Testing Program Farley Units 1 and 2 13.4.4 - 1 Version 24.0 Technical Requirements

RCS Pressure Isolation Valve (PIV) Leakage TR 13.4.5 13.4 Reactor Coolant System (RCS)

TR 13.4.5 RCS Pressure Isolation Valve (PIV) Leakage TR 13.4.5 Leakage from each RCS PIV shall be within the limit of Table 13.4.5-1 following maintenance, repair or replacement work on the valve affecting the seating capability of the valve.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS

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

Separate Condition entry is allowed for each flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS A.1 Restore leakage to within Prior to returning pressure isolation valves limit. valve to service (PIVs) with leakage in excess of limit following maintenance, repair or replacement work on the valve affecting the seating capability of the valve.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.5.1 Verify PIV leakage within limits of Table 13.4.5-1 Prior to returning following maintenance, repair or replacement work on valve to service the valve affecting the seating capability of the valve.

Farley Units 1 and 2 13.4.5 - 1 Version 8.0 Technical Requirements

RCS Pressure Isolation Valve (PIV) Leakage TR 13.4.5 Table 13.4.5-1 Reactor Coolant System Pressure Isolation Valves Valve Number Description Maximum Allowable Leakage Q1/2E11V001A 12 Gate 5.000 gpm Q1/2E11V001B 12 Gate 5.000 gpm Q1/2E11V016A 12 Gate 5.000 gpm Q1/2E11V016B 12 Gate 5.000 gpm Q1/2E11V021A 6 Check 3.000 gpm Q1/2E11V021B 6 Check 3.000 gpm Q1/2E11V021C 6 Check 3.000 gpm Q1/2E21V032A 12 Check 5.000 gpm Q1/2E21V032B 12 Check 5.000 gpm Q1/2E21V032C 12 Check 5.000 gpm Q1/2E21V037A 12 Check 5.000 gpm Q1/2E21V037B 12 Check 5.000 gpm Q1/2E21V037C 12 Check 5.000 gpm Q1/2E11V042A 10 Check 5.000 gpm Q1/2E11V042B 10 Check 5.000 gpm Q1/2E21V076A 6 Check 3.000 gpm Q1/2E21V076B 6 Check 3.000 gpm Q1/2E21V077A 6 Check 3.000 gpm Q1/2E21V077B 6 Check 3.000 gpm Q1/2E21V077C 6 Check 3.000 gpm Note: See TS 3.4.14 for applicable Actions and Surveillance Requirements Farley Units 1 and 2 13.4.5 - 2 Version 8.0 Technical Requirements

ECCS TR 13.5.1 13.5 Emergency Core Cooling System TR 13.5.1 Emergency Core Cooling System (ECCS)

TR 13.5.1 The ECCS subsystems required OPERABLE in accordance with Technical Specifications 3.5.2 and 3.5.3 shall be maintained with:

a. Unrestricted containment sump suctions,

b. Throttle valves in correct position, and

c. Flow balanced.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ECCS A.1 Refer to Technical Immediately subsystems inoperable. Specification 3.5.2 or 3.5.3, as applicable, and associated Required Actions.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.5.1.1 Perform a visual inspection of accessible areas of Once prior to entry containment (or those areas affected by a into MODE 4 from containment entry during MODES 1-4) to verify that MODE 5 no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the AND containment sump and cause restriction of the pump suctions during LOCA conditions. Thereafter at the completion of each containment entry.

Farley Units 1 and 2 13.5.1 - 1 Version 8.0 Technical Requirements

ECCS TR 13.5.1 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.5.1.2 Verify correct position of each mechanical position Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months stop for the following ECCS throttle valves: following completion of each valve CVC-V-8991 A/B/C stroking operation or CVC-V-8989 A/B/C maintenance on the CVC-V-8996 A/B/C valve when the CVC-V-8994 A/B/C ECCS subsystems are required to be OPERABLE.

TRS 13.5.1.3 Verify that the mechanical stops are intact for the Prior to entry into following low head safety injection valves: MODE 3 from MODE 4.

RHR-HV-603 A/B TRS 13.5.1.4 Perform a flow balance test, during shutdown, and Once following verify the following flow rates: completion of modifications to the a) For HHSI System - single pump that provides the ECCS subsystem(s) greatest flow: that alter the subsystem(s) flow t 193 gpm for each cold leg injection line, and characteristics.

t 183 gpm for each hot leg injection line Verify that the developed head of the other HHSI pumps is greater than or equal to the limits in Table 13.5.1-1 and within 580 feet of the developed head of the HHSI pump that provides the greatest flow.

b) For LHSI System - single pump:

t 3911 gpm (total injection)

Farley Units 1 and 2 13.5.1 - 2 Version 32.0 Technical Requirements

ECCS TR 13.5.1 Table 13.5.1-1 Minimum Allowable HHSI Pump Performance PUMP FLOW PUMP HEAD (gpm) (ft) 0 5420 125 5320 225 5220 260 5120 305 4920 390 4420 460 3920 520 3420 580 2920 635 2420 700 1770 Farley Units 1 and 2 13.5.1 - 3 Version 17.0 Technical Requirements

Containment Ventilation System Leakage Rate TR 13.6.1 13.6 Containment Systems TR 13.6.1 Containment Ventilation System Leakage Rate TR 13.6.1 The containment ventilation system leakage rate shall be within limits.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Indications of excess A.1 Perform an engineering Prior to entering valve degradation (for the evaluation to determine what MODE 4 following containment purge supply corrective action, if any, is the next entry into and exhaust penetrations) necessary. MODE 5 if the based on comparison of existing leakage is the leakage rate for each determined during containment purge supply testing per Technical and exhaust penetration Specification SR to the previously 3.6.3.5 measured leakage rate.

OR Prior to entering MODE 4 if excess leakage is determined during MODE 5 per SR 3.6.3.5 Farley Units 1 and 2 13.6.1 - 1 Version 8.0 Technical Requirements

Containment Ventilation System Leakage Rate TR 13.6.1 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY Prior to entering TRS 13.6.1.1 Compare the leakage rate for each containment purge MODE 4 from supply and exhaust penetration to the previously MODE 5 if not measured leakage rate (for the containment purge performed in the supply and exhaust penetrations) to detect excess valve previous 92 days degradation.

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

This surveillance is performed to address excess valve degradation concerns.

TRS 13.6.1.2 Replace the resilient material valve seals of the 48-inch 9 Years and the 8-inch containment purge supply and exhaust isolation valves.

Farley Units 1 and 2 13.6.1 - 2 Version 28.0 Technical Requirements

Containment Isolation Valves TR 13.6.2 13.6 Containment Systems TR 13.6.2 Containment Isolation Valves TR 13.6.2 The containment isolation valves in Table 13.6.2-1 shall be verified to have isolation times within the limits listed in Table 13.6.2-1 after maintenance, repair or replacement work is performed on the valve(s) or its associated actuator, control or power circuit.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTIONS

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

Penetration flow path(s) except for 48 inch purge valve flow paths may be unisolated intermittently under administrative controls.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Restore the isolation time of Prior to returning the isolation valve(s) with the valve(s) to within the valve(s) to service isolation times exceeding limit.

the limit.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.6.2.1 -------------------------------NOTE----------------------------------

Only required after maintenance, repair or replacement work is performed on a valve or its associated actuator, control or power circuit.

Perform a cycling test and verify the isolation time of the Prior to returning the affected valve(s) is within the limit(s) listed in Table valve(s) to service 13.6.2-1.

Farley Units 1 and 2 13.6.2 - 1 Version 8.0 Technical Requirements

Containment Isolation Valves TR 13.6.2 Table 13.6.2-1 (Page 1 of 3)

Containment Isolation Valves Isolation Time Valve Number Function (sec)

A. Phase A Isolation

1. CVC-HV-8871 Accum. Test Line to RWST Iso. Valve 10

2. CVC-HV-8961 Accum. Test Line to RWST Iso. Valve 10

3. CVC-HV-8880 N2 Supply to Isolation Accum. 10

4. RC-HV-8047 Pressurizer Relief Tank N2 Supply 10

5. RC-HV-8033 Pressurizer Relief Tank N2 Supply 10

6. RC-HV-8028 Reactor Makeup Water to PRT Iso. Valve 10

7. LWP-LCV-1003 Reactor Coolant Drain Tank LCV 10

8. LWP-HV-7136 RCDT Pumps Discharge Line Iso. 10

9. CBV-MOV-3318A CTMT Differential Press. Iso. Valve 15

10. CBV-MOV-3318B CTMT Differential Press. Iso. Valve 15

11. CVC-HV-8152 Letdown Line CTMT Iso. Valve 10

12. CVC-HV-8149A Letdown Orifice Isolation Valve 45 gpm 10

13. CVC-HV-8149B Letdown Orifice Isolation Valve 60 gpm 10

14. CVC-HV-8149C Letdown Orifice Isolation Valve 60 gpm 10

15. CVC-MOV-8100 RCP Seal Water Return Iso. Valve 10 (a)

16. CVC-MOV-8112 RCP Seal Water Return Iso. Valve 15

17. SS-HV-3104 Pressurizer Steam Sample Iso. Valve 10

18. SS-HV-3331 Pressurizer Steam Sample Iso. Valve 10

19. SS-HV-3103 Pressurizer Liquid Sample Iso. Valve 10

20. SS-HV-3332 Pressurizer Liquid Sample Iso. Valve 10

21. SS-HV-3765 Reactor Loops 2 and 3 Sample Iso. Valve 10

22. SS-HV-3333 Reactor Loops 2 and 3 Sample Iso. Valve 10

23. CBV-HV-3657 Containment Air Sample Iso. Valve 10

24. CBV-MOV-3660 Containment Air Sample Iso. Valve 15

25. CBV-HV-3658 Containment Air Sample Iso. Valve 10

26. CBV-HV-3198A Containment Purge Exhaust Iso. Valve 5

27. CBV-HV-3198D Containment Purge Supply Iso. Valve 5

28. LWP-HV-3376 Containment Sump Discharge Valve 10

29. LWP-HV-3377 Containment Sump Discharge Valve 10

30. CCW-HV-3095 CCW to Excess Letdown/RCDT HXs. 10

31. CCW-HV-3443 CCW from Excess Letdown/RCDT HXs 10 (a) In accordance with MDC 1090703801, Unit 1 CVC-MOV-8100 isolation time has been changed to 15 s.

(continued)

Farley Units 1 and 2 13.6.2 - 2 Version 23.0 Technical Requirements

Containment Isolation Valves TR 13.6.2 Table 13.6.2-1 (Page 2 of 3)

Containment Isolation Valves Isolation Time Valve Number Function (sec)

A. Phase A Isolation (continued)

32. CCW-HV-3067 CCW from Exc. Letdown / RCDT HXs 10

33. CVC-HV-8860 Accum. Fill Line Isolation 10

34. SS-HV-3766 Accum. Tanks Sample Iso. Valve 10

35. SS-HV-3334 Accum. Tanks Sample Iso. Valve 10

36. LWP-HV-7126 RCDT Vent Line Iso. Valve 10

37. LWP-HV-7150 RCDT Vent Line Iso. Valve 10

38. LWP-HV-3380 CTMT Sump Recirculation Valve 10

39. CTS-HV-3659 Demin. Water to Reactor HD Storage 10

40. CBV-HV-3196 CTMT Purge Exhaust Iso. Valve 5

41. CBV-HV-3197 CTMT Purge Supply Iso. Valve 5

42. CBV-HV-2867C CTMT Mini-Purge Exhaust Iso. Valve 5

43. CBV-HV-2867D CTMT Mini-Purge Exhaust Iso. Valve 5

44. CBV-HV-2866C CTMT Mini-Purge Supply Iso. Valve 5

45. CBV-HV-2866D CTMT Mini-Purge Supply Iso. Valve 5 B. Phase B Isolation

1. CCW-MOV-3052 CCW to RCP Coolers < 15

2. CCW-MOV-3046 CCW from RCP Oil Coolers < 36 for Unit 1

< 15 for Unit 2

3. CCW-MOV-3182 CCW from RCP Oil Coolers < 15

4. CCW-HV-3184 CCW from RCP Thermal Barrier < 10

5. CCW-HV-3045 CCW from RCP Thermal Barrier < 10

6. IA-HV-3611 CTMT Instrument Air Supply Valve < 10

7. IA-HV-2228 Pressurizer PORV Backup Air/N2 < 10 Supply Valve C. Safety Injection Signal

1. CVC-MOV-8107 Charging Pumps to Regenerative HX < 10

2. CVC-MOV-8108 Charging Pumps to Regenerative HX < 10

3. SW-MOV-3135 SW to RCP Motor Air Coolers < 36

4. SW-MOV-3131 SW From RCP Motor Air Coolers < 36

5. SW-MOV-3134 SW From RCP Motor Air Coolers < 36 (continued)

Farley Units 1 and 2 13.6.2 - 3 Version 16.0 Technical Requirements

Containment Isolation Valves TR 13.6.2 Table 13.6.2-1 (Page 3 of 3)

Containment Isolation Valves Isolation Time Valve Number Function (sec)

D. Manual

1. Q1/2G31V012 Refueling Cavity Supply N/A

2. Q1/2G21V005 Reactor Coolant Drain Tank N/A

3. RHR-MOV-8701A Reactor Coolant LP C to RHR Pump A < 120

4. RHR-MOV-8702A Reactor Coolant LP A to RHR Pump B < 120

5. Q1/2P18V001 Service Air N/A

6. Q1/2P18V002 Service Air N/A

7. CBV-MOV-3238 CTMT Leak Rate Test Valve N/A

8. CBV-MOV-3239 CTMT Leak Rate Test Valve N/A

9. RHR-MOV-8811A CTMT Sump to RHR Pump A < 17

10. RHR-MOV-8811B CTMT Sump to RHR Pump B < 17

11. RHR-MOV-8812A CTMT Sump to RHR Pump A < 17

12. RHR-MOV-8812B CTMT Sump to RHR Pump B < 17

13. CS-MOV-8826A CS Pump A CTMT Sump Suction Iso. < 17

14. CS-MOV-8826B CS Pump B CTMT Sump Suction Iso. < 17

15. CS-MOV-8827A CS Pump A CTMT Sump Suction Iso. < 17

16. CS-MOV-8827B CS Pump B CTMT Sump Suction Iso. < 17

17. Q1/2B13V026B Pressurizer Pressure Generator N/A

18. CBV-MOV-3528A CTMT Post-LOCA Sampling Valve 1 N/A

19. CBV-MOV-3528B CTMT Post-LOCA Sampling Valve 2 N/A

20. CBV-MOV-3528C CTMT Post-LOCA Sampling Valve 3 N/A

21. CBV-MOV-3528D CTMT Post-LOCA Sampling Valve 4 N/A

22. CBV-MOV-3739A CTMT Post-LOCA Sampling Iso. Valve N/A

23. CBV-MOV-3739B CTMT Post-LOCA Sampling Iso. Valve N/A

24. CBV-MOV-3745A CTMT Post-LOCA Sampling Rtn. Valve N/A

25. CBV-MOV-3745B CTMT Post-LOCA Sampling Rtn. Valve N/A

26. CBV-MOV-3835A CTMT Post-LOCA Sampling Rtn. Valve N/A

27. CBV-MOV-3835B CTMT Post-LOCA Sampling Rtn. Valve N/A

28. CBV-MOV-3740 CTMT Post-LOCA Vent Iso. Valve N/A

29. CBV-MOV-3530 CTMT Post-LOCA Vent Iso. Valve N/A

30. Q2P18V004 Breathing Air (Service Air) (Unit 2 Only) N/A

31. Q2P18V005 Breathing Air (Service Air) (Unit 2 Only) N/A

32. Q1/2P19V1099 HV2228 Bypass Manual Isolation Valve N/A Farley Units 1 and 2 13.6.2 - 4 Version 12.0 Technical Requirements

Steam Generator Pressure/Temperature Limitation TR 13.7.1 13.7 Plant Systems TR 13.7.1 Steam Generator (SG) Pressure/Temperature Limitation TR 13.7.1 The temperatures of the primary coolant and feedwater shall be > 70 °F when the pressure of either coolant in the steam generator is > 200 psig.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1 Reduce the SG pressure of 30 minutes All Required Actions must the applicable side to 200 be completed whenever psig.

this Condition is entered.

AND SG temperatures not A.2 Perform an engineering Prior to increasing within limits. evaluation to determine the the SG coolant effect of the over- temperatures >

pressurization on the 200 °F structural integrity of the SG.

AND A.3 Determine that the SG Prior to increasing remains acceptable for the SG coolant continued operation. temperatures >

200 °F Farley Units 1 and 2 13.7.1 - 1 Version 8.0 Technical Requirements

Steam Generator Pressure/Temperature Limitation TR 13.7.1 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.7.1.1 ------------------------------NOTE-----------------------------------

Only required to be performed when the temperature of either the primary coolant or feedwater is < 70 °F.

Verify the pressure in each side of the SG is < 200 psig. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Farley Units 1 and 2 13.7.1 - 2 Version 8.0 Technical Requirements

Snubbers TR 13.7.2 13.7 Plant Systems TR 13.7.2 Snubbers TR 13.7.2 All required snubbers utilized on safety-related systems shall be FUNCTIONAL.

Snubbers utilized on non-safety-related systems shall be FUNCTIONAL if the failure of that snubber or the non-safety-related system would have an adverse effect on any safety-related system.

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

MODES 5 and 6 for snubbers located on systems required FUNCTIONAL in those MODES.

ACTIONS

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

1. Separate Condition entry is allowed for each affected system.

2. Removal of a snubber from supported system does not result in the snubber becoming nonfunctional.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Refer to the requirements of Immediately snubbers removed from Technical Specification LCO supported system. 3.0.8.

OR One or more required snubbers inoperable while in place.

B. One or more required B.1 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months snubbers nonfunctional. evaluation on the supported component in accordance with the OM Code version as indicated in the IST Snubber Program Plan.

C. Required Action and C.1 Declare supported system Immediately associated Completion nonfunctional or inoperable Time of Condition B not as appropriate.

met.

Farley Units 1 and 2 13.7.2 - 1 Version 41.0 Technical Requirements

Snubbers TR 13.7.2 TECHNICAL REQUIREMENT SURVEILLANCES

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

Each snubber shall be demonstrated FUNCTIONAL by performance of an inservice examination and testing inspection program in accordance with the OM Code version as indicated in the IST Snubber Program Plan.

SURVEILLANCE FREQUENCY TRS 13.7.2.1 Perform visual examinations of each snubber in In accordance with accordance with ASME OM Code. ASME OM Code and ASME OM Preservice Examinations shall be in accordance with Code Case OMN-13 ASME OM Code. as applicable.

Inservice Examinations shall be in accordance with ASME OM Code.

TRS 13.7.2.2 Perform a functional test on a representative sample of Each fuel Cycle snubbers in accordance with ASME OM Code.

Preservice Examinations shall be in accordance with ASME OM Code.

Inservice Examinations shall be in accordance with ASME OM Code.

TRS 13.7.2.3 Snubber service life will be monitored in accordance Each fuel Cycle with ASME OM Code.

Farley Units 1 and 2 13.7.2 - 2 Version 43.0 Technical Requirements

Snubbers TR 13.7.2 Table 13.7.2-1 Visual Examinations

1. Visual Examinations shall be performed in accordance with the ASME OM Code, Subsection ISTD.

2 Visual Examinations interval may be extended in accordance with ASME Code Case OMN-13.

3. Preservice and Inservice Examinations shall be performed using the visual examination method described in the OM Code version as indicated in the IST Snubber Program Plan.

Farley Units 1 and 2 13.7.2 - 3 Version 43.0 Technical Requirements

Snubbers TR 13.7.2 Table 13.7.2-2 Functional Tests Snubbers shall be selected in accordance with a specified sampling plan and functionally tested in accordance with the requirements of ASME OM Code. The tests may be done either in place or in a test bench. One of the sampling plans described in Subsection ISTD shall be used to select the snubbers to be tested.

Farley Units 1 and 2 13.7.2 - 4 Version 43.0 Technical Requirements

Sealed Source Contamination TR 13.7.3 13.7 Plant Systems TR 13.7.3 Sealed Source Contamination TR 13.7.3 The removable contamination shall be < 0.005 microcuries for each sealed source containing radioactive material >100 microcuries of beta and/or gamma emitting material or > 5 microcuries of alpha emitting material.

APPLICABILITY: At all times.

ACTIONS

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

TR 13.0.3 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. Sealed source removable A.1 Remove sealed source from Immediately contamination not within use.

limit.

AND A.2.1 Decontaminate and repair Prior to returning the the sealed source sealed source to use OR A.2.2 Dispose of sealed source in In accordance with accordance with Commission Commission regulations. regulations Farley Units 1 and 2 13.7.3 - 1 Version 8.0 Technical Requirements

Sealed Source Contamination TR 13.7.3 TECHNICAL REQUIREMENT SURVEILLANCES

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

1. The licensee, or other persons specifically authorized by the Commission or an Agreement State, shall perform the Technical Requirement Surveillances.

2. The test methods shall have a detection sensitivity of at least 0.005 microcuries per test sample.

SURVEILLANCE FREQUENCY TRS 13.7.3.1 -------------------------------NOTES--------------------------------

1. Not applicable to startup sources and fission detectors previously subjected to core flux.

2. Only applicable to sources in use with:

a. Half-lives > 30 days, excluding Hydrogen 3, and

b. In any form other than gas.

Verify removable contamination is within limit for each 6 months sealed source.

TRS 13.7.3.2 ---------------------------------NOTES------------------------------

1. Only applicable to stored sources not in use.

2. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

Verify the removable contamination is within limit for Within 6 months each sealed source and fission detector. prior to use or transfer to another licensee.

Farley Units 1 and 2 13.7.3 - 2 Version 8.0 Technical Requirements

Sealed Source Contamination TR 13.7.3 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.7.3.3 --------------------------------NOTE---------------------------------

Only applicable to sealed startup sources and fission detectors not in use.

Verify the removable contamination is within limit for Within 31 days prior each sealed startup source and fission detector. to being subjected to core flux or being installed in the core.

AND Following repair or maintenance to the source.

Farley Units 1 and 2 13.7.3 - 3 Version 8.0 Technical Requirements

The Ultimate Heat Sink (UHS) Support Structures TR 13.7.4 13.7 Plant Systems TR 13.7.4 The Ultimate Heat Sink (UHS) Support Structures TR 13.7.4 The Ultimate Heat Sink (UHS) support structures shall be maintained in accordance with applicable maintenance requirements.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Ultimate A.1 Initiate action to return Immediately Heat Sink (UHS) support support structure to structures in degraded compliance with related condition. maintenance requirements.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.7.4.1 Verify the spillway channel and adjacent areas are free After each storm that of erosion damage. raises the pond level 187 ft., mean sea level TRS 13.7.4.2 Verify the spillway channel and structure are intact. 2 years TRS 13.7.4.3 Verify the ground water seepage from the pond to be < 5 years 15 cfs.

Farley Units 1 and 2 13.7.4 - 1 Version 8.0 Technical Requirements

Area Temperature Monitoring (Unit 2 Only)

TR 13.7.5 13.7 Plant Systems TR 13.7.5 Area Temperature Monitoring (Unit 2 Only)

TR 13.7.5 The temperature of each area shown in Table 13.7.5-1 shall be maintained within the limits indicated in Table 13.7.5-1.

APPLICABILITY: Whenever the equipment in an affected area is required to be FUNCTIONAL or OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more areas not A.1 Declare the equipment in the Immediately within limits for more than area nonfunctional or 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . inoperable and apply the appropriate Required Action(s) for the nonfunctional/inoperable equipment.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months A.2 Perform an engineering evaluation to determine the effects of the out of limit temperature on the service life of the equipment located in the area.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.7.5.1 Verify the temperature in each of the areas in Table 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 13.7.5-1 is within limits.

Farley Unit 2 13.7.5 - 1 Version 29.0 Technical Requirements

Area Temperature Monitoring (Unit 2 Only)

TR 13.7.5 Table 13.7.5-1 Area Temperature Monitoring Area Temperature Limit (°F)

1. ESF Pump Rooms

a. RHR Pump 2A 150 °F

b. RHR Pump 2B 150 °F

c. AFW Pump 2A 150 °F

d. AFW Pump 2B 150 °F

e. CCW Pump Room 150 °F

f. Containment Spray Pump 2A 150 °F

g. Containment Spray Pump 2B 150 °F

h. Charging Pump Room 2A 150 °F

i. Charging Pump Room 2B 150 °F

j. Charging Pump Room 2C 150 °F

2. Electrical Areas

k. MCC 2A Room 150 °F

l. MCC 2B Room 150 °F

m. 600 Volt Load Center 2D Room 150 °F

n. 600 Volt Load Center 2E Room 150 °F

o. Battery Charger Room A 120 °F

p. Battery Charger Room B 120 °F

q. Battery Room A 120 °F

r. Battery Room B 120 °F

s. Diesel Generator Rooms 150 °F

t. Diesel Generator Switchgear Rooms 150 °F Farley Unit 2 13.7.5 - 2 Version 8.0 Technical Requirements

Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)

TR 13.8.1 13.8 Electrical Power Systems TR 13.8.1 Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)

TR 13.8.1 Each required penetration conductor overcurrent protective device shall be FUNCTIONAL for each containment penetration provided with required penetration conductor overcurrent protection. Required circuits for all other containment penetrations shall be deenergized unless energized under administrative control.

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

ACTIONS

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

TR 13.0.4c is applicable to overcurrent devices in circuits which are deenergized.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Restore the protective 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment penetration device(s) to FUNCTIONAL conductor overcurrent status.

protective device(s) nonfunctional. OR A.1.2 Deenergize the circuit(s). 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One or more containment B.1 Deenergize the circuit(s). 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months penetration circuit(s),

which are required to be deenergized, energized.

Farley Unit 2 13.8.1 - 1 Version 24.0 Technical Requirements

Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)

TR 13.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Initiate a Condition Report. Immediately associated Completion Time not met. AND C.2 Continue action to restore Immediately the required protective device(s) to FUNCTIONAL status or deenergize the circuits which are required to be deenergized.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.8.1.1 -------------------------------NOTE----------------------------------

Only required to be performed on one reactor coolant pump circuit every 18 months provided that all reactor coolant pump circuits are demonstrated FUNCTIONAL at least once per 54 months.

Verify FUNCTIONALITY of at least one 4.16 kV reactor 18 months coolant pump circuit, by performance of:

a. A CHANNEL CALIBRATION of the associated protective relays, and

b. An integrated system functional test which includes simulated automatic actuation of the system and verification that each relay and associated circuit breakers and control circuits function as designed, and

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

Farley Unit 2 13.8.1 - 2 Version 29.0 Technical Requirements

Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)

TR 13.8.1 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.8.1.2 --------------------------------NOTES-------------------------------

1. Circuit breakers selected for functional testing shall be selected on a rotating basis.

2. The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

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

Perform a functional test on a representative sample of 18 months 10% of each type of lower voltage circuit breakers.

TRS 13.8.1.3 Inspect and perform preventive maintenance on each 72 months circuit breaker in accordance with procedures prepared in conjunction with its manufacturers recommendations.

TRS 13.8.1.4 Verify power sources feeding circuits required to be 31 days deenergized are interrupted by an open breaker or removed fuse.

Farley Unit 2 13.8.1 - 3 Version 42.0 Technical Requirements

Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 13.8 Electrical Power Systems TR 13.8.2 Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 The thermal overload protection devices, integral with the motor starter, of each valve listed in Table 13.8.2-1 shall be FUNCTIONAL.

APPLICABILITY: Whenever the motor operated valve is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Declare the affected valve(s) Immediately nonfunctional thermal inoperable and enter the overload protection appropriate Technical device(s). Specification Condition and follow the applicable Required Actions for the affected valve(s).

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.8.2.1 -------------------------------NOTE----------------------------------

CHANNEL CALIBRATION must be performed on each thermal overload device at least once per 12 years.

Verify the required thermal overload protection devices 36 months FUNCTIONAL by performance of a CHANNEL CALIBRATION of a representative sample of at least 25% of all thermal overload devices.

Farley Unit 2 13.8.2 - 1 Version 36.0 Technical Requirements

Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 Table 13.8.2-1 (Page 1 of 4)

Motor Operated Valves Thermal Overload Protection Devices (Note 1)

Valve Number Function Bypass Device MOV-3052 CCW to RCP Coolers No MOV-3046 CCW from RCP Coolers No MOV-3182 CCW from RCP Coolers No MOV-3019A SW to Coolers (SI open) No MOV-3019B SW to Coolers (SI open) No MOV-3019C SW to Coolers (SI open) No MOV-3019D SW to Coolers (SI open) No MOV-3441A SW from Coolers No MOV-3441B SW from Coolers No MOV-3441C SW from Coolers No MOV-3441D SW from Coolers No MOV-3024A SW from Coolers No MOV-3024B SW from Coolers No MOV-3024C SW from Coolers No MOV-3024D SW from Coolers No MOV-3149 SW to Blowdown Hx No MOV-3150 SW from Blowdown Hx No MOV-3135 RCP Air Cooler SW Isolation No MOV-3134 RCP Air Cooler SW Isolation No MOV-3131 RCP Air Cooler SW Isolation No MOV-3764A MD Discharge Isolation (AFW) No MOV-3764B MD Discharge Isolation (AFW) No MOV-3764C MD Discharge Isolation (AFW) No MOV-3764D MD Discharge Isolation (AFW) No MOV-3764E MD Discharge Isolation (AFW) No MOV-3764F MD Discharge Isolation (AFW) No MOV-3350A AFW Header Isolation No MOV-3350B AFW Header Isolation No MOV-3350C AFW Header Isolation No MOV-3209A Service Water for AFW Suction No MOV-3209B Service Water for AFW Suction No MOV-3210A Service Water for AFW Suction No MOV-3210B Service Water for AFW Suction No MOV-3216 Service Water for AFW Suction No MOV-3660 CTMT Rad Monitor Isolation No MOV-3318A CTMT Differential Pressure Isolation No MOV-3318B CTMT Differential Pressure Isolation No MOV-2768A Control Room Vent. Damper No MOV-2768B Control Room Vent. Damper No (continued)

Farley Unit 2 13.8.2 - 2 Version 8.0 Technical Requirements

Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 Table 13.8.2-1 (Page 2 of 4)

Motor Operated Valves Thermal Overload Protection Devices (Note 1)

Valve Number Function Bypass Device MOV-2769A Control Room Vent. Damper No MOV-2769B Control Room Vent. Damper No MOV-3478A Control Room Vent. Damper No MOV-3478B Control Room Vent. Damper No MOV-3872A Hydrogen Dilution Fan Damper No MOV-3872B Hydrogen Dilution Fan Damper No MOV-8106 Charging Pump Mini Flow Isolation No MOV-8826A CTMT Spray Suction from CTMT Sump No MOV-8826B CTMT Spray Suction from CTMT Sump No MOV-8827A CTMT Spray Suction from CTMT Sump No MOV-8827B CTMT Spray Suction from CTMT Sump No MOV-8817A CTMT Spray Suction from RWST No MOV-8817B CTMT Spray Suction from RWST No MOV-8820A Discharge to Spray Ring No MOV-8820B Discharge to Spray Ring No MOV-8803A BIT Inlet No MOV-8803B BIT Inlet No MOV-8886 Charging Pump Discharge to Hot Leg No MOV-8884 Charging Pump Discharge to Hot Leg No MOV-8885 Charging Pump Discharge to Cold Leg No MOV-8808A SIS Accumulator Outlet No MOV-8808B SIS Accumulator Outlet No MOV-8808C SIS Accumulator Outlet No MOV-8811A RHR Suction from CTMT Sump No MOV-8811B RHR Suction from CTMT Sump No MOV-8812A RHR Suction from CTMT Sump No MOV-8812B RHR Suction from CTMT Sump No MOV-8809A RHR Suction from RWST No MOV-8809B RHR Suction from RWST No MOV-8887A RHR Discharge Crossconnect No MOV-8887B RHR Discharge Crossconnect No FCV-602A RHR Pump Mini Flow No FCV-602B RHR Pump Mini Flow No MOV-8889 RHR Discharge to Hot Leg No MOV-8888A RHR Discharge to Cold Leg No MOV-8888B RHR Discharge to Cold Leg No MOV-8706A RHR Discharge to Charging Pump Suction No (continued)

Farley Unit 2 13.8.2 - 3 Version 8.0 Technical Requirements

Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 Table 13.8.2-1 (Page 3 of 4)

Motor Operated Valves Thermal Overload Protection Devices (Note 1)

Valve Number Function Bypass Device MOV-8706B RHR Discharge to Charging Pump Suction No MOV-8112 Seal Water Return CTMT Isolation No MOV-8100 Seal Water Return CTMT Isolation No QSP25V513 RW to Pond Isolation No QSP25V514 RW to Pond Isolation No QSP25V517 RW to Wet Pit Isolation No QSP25V518 RW to Wet Pit Isolation No MOV-3536 CTMT Air Purge Isolation No MOV-3530 Post LOCA Vent Isolation No MOV-3740 Post LOCA Vent Isolation No MOV-3528A CTMT Air Sample Isolation No MOV-3528B CTMT Air Sample Isolation No MOV-3528C CTMT Air Sample Isolation No MOV-3528D CTMT Air Sample Isolation No MOV-3739A CTMT Air Sample Isolation No MOV-3739B CTMT Air Sample Isolation No MOV-3745A CTMT Air Sample Isolation No MOV-3745B CTMT Air Sample Isolation No MOV-3835A CTMT Air Sample Isolation No MOV-3835B CTMT Air Sample Isolation No MOV-3362A Penetration Room Vent Damper No MOV-3362B Penetration Room Vent Damper No MOV-3361A Penetration Room Vent Damper No MOV-3361B Penetration Room Vent Damper No MOV-3406 Turbine Trip and Throttle No MOV-3232A Feedwater Isolation No MOV-3232B Feedwater Isolation No MOV-3232C Feedwater Isolation No Q2P16V514 Turbine Building Isolation No Q2P16V515 Turbine Building Isolation No Q2P16V516 Turbine Building Isolation No Q2P16V517 Turbine Building Isolation No Q2P16V538 Pond Recirculation No Q2P16V539 Pond Recirculation No LCV-115C Charging Pump Suction from VCT No LCV-115E Charging Pump Suction from VCT No LCV-115B Charging Pump Suction from RWST No LCV-115D Charging Pump Suction from RWST No MOV-8131A Charging Pump Suction Crossconnect No (continued)

Farley Unit 2 13.8.2 - 4 Version 8.0 Technical Requirements

Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

TR 13.8.2 Table 13.8.2-1 (Page 4 of 4)

Motor Operated Valves Thermal Overload Protection Devices (Note 1)

Valve Number Function Bypass Device MOV-8131B Charging Pump Suction Crossconnect No MOV-8130A Charging Pump Suction Crossconnect No MOV-8130B Charging Pump Suction Crossconnect No MOV-8132A Charging Pump Discharge Crossconnect No MOV-8132B Charging Pump Discharge Crossconnect No MOV-8133A Charging Pump Discharge Crossconnect No MOV-8133B Charging Pump Discharge Crossconnect No MOV-8107 Charging Line Isolation No MOV-8108 Charging Line Isolation No MOV-8109A Charging Pump Mini Flow Isolation No MOV-8109B Charging Pump Mini Flow Isolation No MOV-8109C Charging Pump Mini Flow Isolation No Note 1: Licensee may delete valves from this table provided the thermal overload protection devices are permanently bypassed.

Farley Unit 2 13.8.2 - 5 Version 8.0 Technical Requirements

Emergency Diesel Generators (EDGs) Maintenance and Inspection Requirements TR 13.8.3 13.8 Electrical Power Systems TR 13.8.3 Emergency Diesel Generators (EDGs) Maintenance and Inspection Requirements TR 13.8.3 The Emergency Diesel Generators (EDGs) shall be maintained in accordance with applicable maintenance and inspection requirements.

APPLICABILITY: When associated EDG is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EDG A.1 Initiate action to restore Immediately maintenance or inspection compliance with requirements not met. maintenance and inspection requirements.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.8.3.1 Verify that the following EDG lockout features prevent 18 months the EDGs from starting only when required:

a. Oil Temperature High (OTH)

b. Coolant Temperature High (CTH)

c. Coolant Pressure Low (CPL)

d. Crankcase Pressure High (CCPH)

TRS 13.8.3.2 Verify that the permanently connected and auto- 18 months on a connected loads to each EDG do not exceed the 2000- STAGGERED TEST hour rating of 4353 kw for the 4075 kw generators and BASIS 3100 kw for the 2850 kw generator.

Farley Units 1 and 2 13.8.3 - 1 Version 30.0 Technical Requirements

Decay Time TR 13.9.1 13.9 Refueling Operations TR 13.9.1 Decay Time TR 13.9.1 The Reactor shall be subcritical for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

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

TR 13.0.3 is not applicable.

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

< 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months . involving movement of irradiated fuel in the reactor pressure vessel.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.1.1 Verify the reactor has been subcritical for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months Prior to movement of by confirming the date and time of subcriticality. irradiated fuel in the reactor pressure vessel.

Farley Units 1 and 2 13.9.1 - 1 Version 8.0 Technical Requirements

Communications TR 13.9.2 13.9 Refueling Operations TR 13.9.2 Communications TR 13.9.2 Direct Communications shall be maintained between the control room and personnel at the refueling station.

APPLICABILITY: During CORE ALTERATIONS

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

TR 13.0.3 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Direct communications A.1 Suspend all CORE Immediately between control room and ALTERATIONS.

refueling station not maintained.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.2.1 Verify direct communication exists between control Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months room and refueling station. prior to start of CORE ALTERATIONS AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter during CORE ALTERATIONS Farley Units 1 and 2 13.9.2 - 1 Version 8.0 Technical Requirements

Manipulator Crane TR 13.9.3 13.9 Refueling Operations TR 13.9.3 Manipulator Crane TR 13.9.3 The manipulator crane and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be FUNCTIONAL with:

a. The manipulator crane used for movement of fuel assemblies having:

1) A minimum capacity of 3250 pounds, and

2) An overload cut off limit less than or equal to 2850 pounds.

b. The auxiliary hoist used for movement of control rods having:

1) A minimum capacity of 700 pounds, and

2) Load indicators which shall be used to assure that loads in excess of 600 pounds are not lifted.

APPLICABILITY: During movement of drive rods or fuel assemblies within the reactor pressure vessel.

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

TR 13.0.3 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Manipulator crane A.1 Suspend use of manipulator Immediately nonfunctional. crane from operations involving the movement of fuel assemblies within the reactor pressure vessel.

Farley Units 1 and 2 13.9.3 - 1 Version 24.0 Technical Requirements

Manipulator Crane TR 13.9.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Auxiliary hoist B.1 Suspend use of auxiliary Immediately nonfunctional. hoist from operations involving the movement of control rods within the reactor pressure vessel.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.3.1 Verify manipulator crane FUNCTIONALITY by: Once within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the

a. Performing a load test of 3250 pounds, and start of movement of fuel assemblies

b. Demonstrating operation of the automatic load within the reactor cutoff when the crane load exceeds 2850 pressure vessel pounds.

TRS 13.9.3.2 Verify auxiliary hoist and associated load indicator Once within 100 FUNCTIONAL by performance of a load test 700 hours prior to the pounds. start of movement of drive rods within the reactor pressure vessel Farley Units 1 and 2 13.9.3 - 2 Version 24.0 Technical Requirements

Crane Travel - Spent Fuel Storage Building TR 13.9.4 13.9 Refueling Operations TR 13.9.4 Crane Travel - Spent Fuel Storage Building TR 13.9.4 Loads > 3000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

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

TR 13.0.3 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Technical Requirement A.1 Place the crane load in a Immediately not met. safe condition.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.4.1 Verify loads 3000 pounds. Prior to movement over irradiated fuel assemblies in the storage pool Farley Units 1 and 2 13.9.4 - 1 Version 8.0 Technical Requirements

Spent Fuel Cask Crane TR 13.9.5 13.9 Refueling Operations TR 13.9.5 Spent Fuel Cask Crane TR 13.9.5 The spent fuel cask crane shall be FUNCTIONAL.

APPLICABILITY: When handling the spent fuel cask.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Ambient air temperature A.1 --------------------------------------

less than the cold proof TR 13.0.3 is not applicable test temperature AND --------------------------------------

material testing has not been performed. Perform cold proof test at the Immediately established lower temperature OR perform material testing as prescribed in the UFSAR Section 9.1.4.4.

B. Lifting components not B.1 Suspend lifting of loads with Immediately meeting any of the criteria the main hoist until the of TRS 13.9.5.2. degraded components are repaired or replaced.

Farley Units 1 and 2 13.9.5 - 1 Version 37.0 Technical Requirements

Spent Fuel Cask Crane TR 13.9.5 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.5.1 Perform a cold proof test at 125% of rated load As needed pursuant to ANSI-B.30.2.0 OR perform Material Testing as described in UFSAR 9.1.4.4.

TRS 13.9.5.2 Perform testing and inspection of the lifting components As needed pursuant to ANSI-B.30.2.0 and the manufacturers recommendations.

Farley Units 1 and 2 13.9.5 - 2 Version 37.0 Technical Requirements

Storage Pool Ventilation (fuel storage)

TR 13.9.6 13.9 Refueling Operations TR 13.9.6 Storage Pool Ventilation (fuel storage)

TR 13.9.6 One penetration room filtration system shall be FUNCTIONAL and aligned to the spent fuel pool.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

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

TR 13.0.3 is not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required penetration A.1 Suspend all operations Immediately room filtration system involving movement of nonfunctional. recently irradiated fuel within the storage pool until required penetration room filtration system is restored to FUNCTIONAL status.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.6.1 Verify a penetration room filtration system is aligned to Once within 12 the spent fuel pool room. hours prior to storage of fuel in the spent fuel pool AND 7 days thereafter while fuel is stored in the storage pool Farley Units 1 and 2 13.9.6 - 1 Version 44.0 Technical Requirements

Storage Pool Ventilation (fuel storage)

TR 13.9.6 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.6.2 Initiate, from the control room, flow through the HEPA 92 days filters and charcoal adsorbers of the penetration room filtration system and verify that the system operates for at least 15 minutes in its fuel handling accident alignment.

TRS 13.9.6.3 Perform required penetration room filtration system filter In accordance with testing in accordance with the Ventilation Filter Testing the VFTP Program (VFTP).

TRS 13.9.6.4 Verify that the normal spent fuel pool ventilation system 18 months isolates upon the receipt of either:

a. The spent fuel pool ventilation low differential pressure test signal, or

b. A spent fuel pool high radiation test signal.

Farley Units 1 and 2 13.9.6 - 2 Version 39.0 Technical Requirements

Average Reactor Coolant Temperature TR 13.9.7 13.9 Refueling Operations TR 13.9.7 Average Reactor Coolant Temperature TR 13.9.7 The average reactor coolant temperature shall be 140 °F.

APPLICABILITY: MODE 6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Average reactor coolant A.1 Initiate action to restore Immediately temperature > 140 °F. average reactor coolant temperature to within limit.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.7.1 Verify average reactor coolant temperature 140 °F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Farley Units 1 and 2 13.9.7 - 1 Version 8.0 Technical Requirements

Waste Gas Monitoring Instrumentation TR 13.12.1 13.12 Explosive Gas and Storage Tank Radioactivity Monitoring (EGSTRAM) Program TR 13.12.1 Waste Gas Monitoring Instrumentation TR 13.12.1 The following waste gas monitoring instrumentation channels shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of TR 13.12.3 are not exceeded:

a. One hydrogen monitor per recombiner, and

b. Two oxygen monitors per recombiner.

APPLICABILITY: During recombiner operation.

ACTIONS

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

1. TR 13.0.3 is not applicable.

2. TR 13.0.4c is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------------NOTE------------ A.1 Isolate the oxygen supply to Immediately Not applicable during the affected recombiner(s).

testing of oxygen monitors.

One oxygen monitor for one or more recombiners nonfunctional.

B. Both oxygen monitors for B.1 Analyze grab samples from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months one or more recombiners the affected on-service waste nonfunctional. decay tank during addition of waste gas.

AND (continued)

Farley Units 1 and 2 13.12.1 - 1 Version 24.0 Technical Requirements

Waste Gas Monitoring Instrumentation TR 13.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify oxygen concentration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months remains less than 1 percent.

C. Required hydrogen C.1 Analyze grab samples from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months monitor for one or more the affected on-service waste recombiners decay tank during addition of nonfunctional. waste gas.

AND C.2 Verify oxygen concentration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months remains less than 1 percent.

D. Required Actions and D.1 Suspend addition of waste Immediately associated Completion gas to the system.

Times of Conditions A, B or C not met.

Farley Units 1 and 2 13.12.1 - 2 Version 45.0 Technical Requirements

Waste Gas Monitoring Instrumentation TR 13.12.1 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE REQUIREMENTS FREQUENCY TRS 13.12.1.1 -------------------------------NOTE----------------------------------

Only required to be performed during recombiner operation.

Perform CHANNEL CHECK 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRS 13.12.1.2 -------------------------------NOTE----------------------------------

Only required to be performed during recombiner operation.

Perform COT 31 days TRS 13.12.1.3 -------------------------------NOTES--------------------------------

1. Only required to be performed during recombiner operation.

2. For the hydrogen monitors, the CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturers recommendations.

3. For the oxygen monitors, the CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturers recommendations. In addition, a standard gas sample of nominally four volume percent oxygen, balance nitrogen shall be used for inlet oxygen monitor linearity check.

Perform CHANNEL CALIBRATION 92 days Farley Units 1 and 2 13.12.1 - 3 Version 8.0 Technical Requirements

Liquid Holdup Tanks TR 13.12.2 13.12 Explosive Gas and Storage Tank Radioactivity Monitoring (EGSTRAM) Program TR 13.12.2 Liquid Holdup Tanks TR 13.12.2 The quantity of radioactive material contained in any outside temporary tank, excluding liners being used to solidify radioactive wastes, shall be limited to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTIONS

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

1. TR 13.0.3 is not applicable.

2. TR 13.0.4c is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend addition of Immediately material in any outside radioactive material to the temporary tank, excluding tank.

liners being used to solidify radioactive AND wastes, in excess of limit.

A.2 Reduce the tank contents to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months within limit.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.2.1 Verify quantity of radioactive material contained in 7 days when each outdoor temporary tank, excluding liners being radioactive materials used to solidify radioactive wastes, to be less than the are being added to a limit by analyzing a representative sample of the tank tank.

contents.

Farley Units 1 and 2 13.12.2 - 1 Version 13.0 Technical Requirements

Waste Gas Monitoring TR 13.12.3 13.12 Explosive Gas and Storage Tank Radioactivity Monitoring (EGSTRAM) Program TR 13.12.3 Waste Gas Monitoring TR 13.12.3 The concentration of oxygen in any portion of the gaseous radwaste treatment system shall be limited to:

A. 2% by volume whenever the hydrogen concentration in that portion of the gaseous radwaste treatment system exceeds 4% by volume and the hydrogen and oxygen monitors required by TR 13.12.1 are FUNCTIONAL; or B. 1% by volume whenever the hydrogen concentration in that portion of the gaseous radwaste treatment system exceeds 4% by volume and the hydrogen and oxygen monitors required by TR 13.12.1 are not FUNCTIONAL.

APPLICABILITY: At all times.

ACTIONS

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

1. TR 13.0.3 is not applicable.

2. TR 13.0.4c is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Monitors in TR 13.12.1 A.1 Reduce oxygen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months FUNCTIONAL. concentration to 2% by volume.

AND Concentration of oxygen in the gaseous radwaste treatment system > 2% by volume but 4% by volume.

Farley Units 1 and 2 13.12.3 - 1 Version 24.0 Technical Requirements

Waste Gas Monitoring TR 13.12.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Monitors in TR 13.12.1 not B.1 Analyze grab samples from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months FUNCTIONAL. the affected on-service waste decay tank during AND addition of waste gas.

Concentration of oxygen in AND the gaseous radwaste treatment system > 1% by B.2 Reduce oxygen 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months volume but 4% by concentration to 1% by volume. volume.

C. Required Actions and C.1 Suspend addition of waste Immediately associated Completion gas to the system.

Times of Conditions A or B not met.

D. Concentration of oxygen in D.1 Suspend all additions of Immediately the gaseous radwaste waste gases to the system.

treatment system > 4% by volume. AND D.2 Reduce oxygen 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months concentration to 4%.

AND D.3 Reduce oxygen 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months concentration to within limit.

Farley Units 1 and 2 13.12.3 - 2 Version 24.0 Technical Requirements

Waste Gas Monitoring TR 13.12.3 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.3.1 Verify concentration of hydrogen or oxygen in the During addition of gaseous radwaste treatment system to be less than waste gases to the the limit by monitoring the waste gases in the gaseous gaseous radwaste radwaste treatment system. treatment system:

by use of the hydrogen and/or oxygen monitors required by TR 13.12.1, when FUNCTIONAL OR by analyzing grab samples from the affected waste decay tank at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Farley Units 1 and 2 13.12.3 - 3 Version 24.0 Technical Requirements

Gas Storage Tanks TR 13.12.4 13.12 Explosive Gas and Storage Tank Radioactivity Monitoring (EGSTRAM) Program TR 13.12.4 Gas Storage Tanks TR 13.12.4 The quantity of radioactivity contained in each gas storage tank shall be limited to 70,500 curies of noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTIONS

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

1. TR 13.0.3 is not applicable.

2. TR 13.0.4c is applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.1 Quantity of radioactive A.1 Suspend all additions of Immediately material in any gas radioactive material to the storage tank exceeding tank.

limit.

AND A.2 Reduce the tank contents to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months within the limit.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.4.1 Verify quantity of radioactive material contained in Once per 7 days each gas storage tank to be less than the limit. when radioactive materials have been added to the tank during the previous 7 days.

Farley Units 1 and 2 13.12.4 - 1 Version 13.0 Technical Requirements

Gas Storage Tanks TR 13.12.4 TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.4.2 In the event of confirmed major fuel failure (> 1%), Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months verify quantity of radioactive material contained in when radioactive each waste gas storage tank to be less than the limit. materials have been added to the tank during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Farley Units 1 and 2 13.12.4 - 2 Version 8.0 Technical Requirements

Emergency Response Facilities TR 13.13.1 13.13 Emergency Response Facilities TR 13.13.1 Emergency Response Facilities TR 13.13.1 The Technical Support Center, the Operations Support Center, and the Emergency Operations Facility shall be FUNCTIONAL.

APPLICABILITY: At all times.

ACTIONS

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

1. Separate condition entry is allowed for each Emergency Response Facility (ERF).

2. TR 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more emergency A.1 Restore emergency 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months facilities nonfunctional. facilities to FUNCTIONAL status.

AND A.2 Verify availability of Immediately alternate locations for performing ERF functions.

B. Required Action A and B.1 Initiate compensatory Immediately associated Completion actions, as necessary, to Time not met. provide emergency response functions.

AND (continued)

Farley Units 1 and 2 13.13.1 - 1 Version 35.0 Technical Requirements

Emergency Response Facilities TR 13.13.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Review NMP-AD-031 for Immediately potential reporting criteria.

AND B.3 Proceed with actions to Immediately return ERFs to FUNCTIONAL status with a high priority.

TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.13.1.1 Perform testing to ensure FUNCTIONALITY of an In accordance with ERF. applicable procedures.

TRS 13.13.1.2 Perform inventory to ensure FUNCTIONALITY of an In accordance with ERF. applicable procedures.

Farley Units 1 and 2 13.13.1 - 2 Version 35.0 Technical Requirements

Technical Requirements Manual (TRM) Bases Joseph M. Farley Nuclear Plant Units 1 and 2

Farley Nuclear Plant Units 1 and 2 Technical Requirements Manual (TRM) Bases List of Effective Pages Page Version Page Version TRM Bases Cover Page Table of Contents Section B 13.7 i ............................ 7.0 B 13.7-1................ 9.0 ii ........................... 8.0 B 13.7-2................ 6.0 Section B 13.0 B 13.7-3................ 9.0 B 13.0-1 ............... 9.0 Section B 13.8 B 13.0-2 ............. 13.0 B 13.8-1................ 9.0 B 13.0-3 ............. 13.0 B 13.8-2.............. 11.0 B 13.0-4 ............. 13.0 B 13.0-5 ............... 9.0 Section B 13.9 B 13.0-6 ............... 9.0 B 13.9-1.............. 19.0 B 13.0-7 ............. 13.0 B 13.9-2.............. 19.0 B 13.0-8 ............... 9.0 Section B 13.12 B 13.0-9 ............... 9.0 B 13.12-1.............. 9.0 B 13.0-10 ............. 9.0 B 13.0-11 ............. 9.0 B 13.0-12 ............. 4.0 Section B 13.13 Section B 13.1 B 13.13.1-1......... 16.0 B 13.13.1-2......... 16.0 B 13.1-1 ............... 9.0 B 13.13.1-3........... 8.0 B 13.1-2 ............. 18.0 B 13.13.1-4......... 12.0 B 13.1-3 ............... 9.0 B 13.13.1-5......... 16.0 Section B 13.3 B 13.3-1 ............. 13.0 B 13.3-2 ............. 13.0 B 13.3-3 ............. 13.0 Section B 13.4 B 13.4-1 ............... 3.0 B 13.4-2 ............. 15.0 Section B 13.5 B 13.5-1 ............... 9.0 Section B 13.6 B 13.6-1 ............... 9.0 Farley Units 1 and 2 Page 1 of 1 Version 19.0 Technical Requirements Bases

Table of Contents Note on section numbering: The TRM and TRM Bases numbering is intended to correspond to the associated ITS Specification. The numbering convention is to use the ITS Specification number, with the addition of a leading 1. For example, TRM spec 13.8, Electrical Power Systems, corresponds to ITS spec 3.8. Since all ITS specifications do not have associated TRM specifications, the TRM numbers do not run consecutively.

B 13.0 TECHNICAL REQUIREMENT (TR) Applicability B 13.0.1 Modes ......................................................................................... B 13.0-1 B 13.0.2 Required Actions ........................................................................ B 13.0-1 B 13.0.3 Completion Times ....................................................................... B 13.0-2 B 13.0.4 Mode Changes ........................................................................... B 13.0-4 B 13.0.5 Operability Determination ........................................................... B 13.0-6 B 13.0.7 Test Exceptions .......................................................................... B 13.0-7 B 13.0 TECHNICAL REQUIREMENT SURVEILLANCES (TRS) Applicability B 13.0.1 Modes ......................................................................................... B 13.0-8 B 13.0.2 Required Actions ........................................................................ B 13.0-9 B 13.0.3 Completion Times ..................................................................... B 13.0-10 B 13.0.4 Mode Changes ......................................................................... B 13.0-11 B 13.1 REACTIVITY CONTROL SYSTEMS B 13.1.1 Shutdown Margin ........................................................................ B 13.1-1 B 13.1.2 Boration Flow Path- Shutdown ................................................... B 13.1-1 B 13.1.3 Boration Flow Paths- Operating.................................................. B 13.1-1 B 13.1.4 Boration Pump- Shutdown .......................................................... B 13.1-1 B 13.1.5 Charging Pumps- Operating ....................................................... B 13.1-1 B 13.1.6 Borated Water Source- Shutdown .............................................. B 13.1-1 B 13.1.7 Borated Water Sources- Operating ............................................ B 13.1-1 B 13.1.8 Position Indication System- Shutdown ....................................... B 13.1-3 B 13.1.9 Test Exception for Position Indication System- Shutdown ......... B 13.1-3 B 13.1.10 Rod Drop Time ........................................................................... B 13.1-3 B 13.3 INSTRUMENTATION B 13.3.1 Movable Incore Detectors ........................................................... B 13.3-1 B 13.3.2 High Energy Line Break Sensors................................................ B 13.3-1 B 13.3.3 Turbine Overspeed Protection .................................................... B 13.3-1 B 13.3.4 Radiation Monitoring Instrumentation ......................................... B 13.3-1 B 13.3.5 Combustible Gas Control............................................................ B 13.3-2 B 13.4 REACTOR COOLANT SYSTEM B 13.4.1 Chemistry.................................................................................... B 13.4-1 B 13.4.2 Pressurizer.................................................................................. B 13.4-1 B 13.4.3 Reactor Vessel Head Vents........................................................ B 13.4-2 B 13.4.4 Safety Valves- Shutdown............................................................ B 13.4-2 B 13.4.5 RCS Pressure Isolation Valve (PIV) Leakage ............................ B 13.4-2 (continued)

Farley Units 1 and 2 i Version 7.0 Technical Requirements Bases

Table of Contents B 13.5 EMERGENCY CORE COOLING SYSTEMS B 13.5.1 ECCS Subsystems ..................................................................... B 13.5-1 B 13.6 CONTAINMENT SYSTEMS B 13.6.1 Containment Ventilation System Leakage Rate ......................... B 13.6-1 B 13.6.2 Containment Isolation Valves ..................................................... B 13.6-1 B 13.7 PLANT SYSTEMS B 13.7.1 Steam Generator Pressure/Temperature Limitation ................... B 13.7-1 B 13.7.2 Snubbers .................................................................................... B 13.7-1 B 13.7.3 Sealed Source Contamination .................................................... B 13.7-2 B 13.7.4 Ultimate Heat Sink (UHS) Support Structures ............................ B 13.7-3 B 13.7.5 Temperature Monitoring (Unit 2 Only) ........................................ B 13.7-3 B 13.8 ELECTRICAL POWER SYSTEMS B 13.8.1 Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only) ................................................. B 13.8-1 B 13.8.2 Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)................................................. B 13.8-1 B 13.8.3 Emergency Diesel Generator (EDG) Maintenance and Inspection Requirements ..................................................... B 13.8-1 B 13.9 REFUELING OPERATIONS B 13.9.1 Decay Time................................................................................. B 13.9-1 B 13.9.2 Communications ......................................................................... B 13.9-1 B 13.9.3 Manipulator Crane ...................................................................... B 13.9-1 B 13.9.4 Crane Travel- Spent Fuel Storage Building ................................ B 13.9-1 B 13.9.5 Spent Fuel Cask Crane .............................................................. B 13.9-1 B 13.9.6 Fuel Storage ............................................................................... B 13.9-2 B 13.9.7 Average Reactor Coolant Temperature ...................................... B 13.9-2 B 13.12 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING (EGSTRAM) PROGRAM B 13.12.1 Waste Gas Monitoring Instrumentation .................................... B 13.12-1 B 13.12.2 Liquid Holdup Tanks ................................................................. B 13.12-1 B 13.12.3 Waste Gas Monitoring .............................................................. B 13.12-1 B 13.12.4 Gas Storage Tanks ................................................................... B 13.12-1 B 13.13 EMERGENCY RESPONSE FACILITIES B 13.13.1 Emergency Response Facilities ............................................ B 13.13.1-1 Farley Units 1 and 2 ii Version 8.0 Technical Requirements Bases

TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES TR 13.0.1 through TR 13.0.7 establish the general requirements applicable to all Technical Requirements and apply at all times, unless otherwise stated.

13.0.1 MODES TR 13.0.1 establishes the Applicability statement within each individual Technical Requirement as the requirement for when the TR is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Technical Requirement).

13.0.2 REQUIRED ACTIONS TR 13.0.2 establishes that upon discovery of a failure to meet a TR, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a TR are not met. This Technical Requirement establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Technical Requirement; and

b. Completion of the Required Actions is not required when a TR is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the TR must be met. This time limit is the Completion Time to restore an nonfunctional system or component to FUNCTIONAL status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Technical Requirement is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.) The second type of Required Action specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.

Completing the Required Actions is not required when a TR is met or is no longer applicable, unless otherwise stated in the individual Technical Requirements.

(continued)

Farley Units 1 and 2 B 13.0-1 Version 9.0 Technical Requirements Bases

TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual TR's ACTIONS specify the Required Actions where this is the case.

An example of this is in TR 13.4.2, "Pressurizer Pressure and Temperature (P/T) Limits."

The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into ACTIONS would result in redundant equipment being nonfunctional, alternatives should be used instead. Doing so limits the time both subsystems/trains of a safety function are nonfunctional and limits the time conditions exist which may result in TR 13.0.3 being entered. Individual Technical Requirements may specify a time limit for performing a TRS when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Technical Requirement becomes applicable. In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new Technical Requirement becomes applicable, and the ACTIONS Condition(s) are entered.

13.0.3 COMPLETION TIMES TR 13.0.3 establishes the actions that must be implemented when a TR 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. Sometimes, possible combinations of Conditions are such that entering TR 13.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that TR 13.0.3 be entered immediately.

This Technical Requirement specifies that the unit shall be placed in a safe condition as determined by plant management and that a Condition Report shall be initiated immediately.

The Actions required to ensure the unit is placed in a safe condition may include a unit shutdown as determined by plant management. It is not intended to be used 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 nonfunctional.

(continued)

Farley Units 1 and 2 B 13.0-2 Version 13.0 Technical Requirements Bases

TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES Actions initiated in accordance with TR 13.0.3 may be terminated and TR 13.0.3 exited if any of the following occurs:

a. The TR is now met.

b. A Condition exists for which the Required Actions have now been performed.

c. ACTIONS exist that do not have expired Completion Times. These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time TR 13.0.3 is exited.

(continued)

Farley Units 1 and 2 B 13.0-3 Version 13.0 Technical Requirements Bases

TR Applicability B 13.0 BASES Exceptions to TR 13.0.3 are provided in instances where the Technical Requirement already provides the appropriate remedial measures to ensure the continued safe operation of the unit as required by TR 13.0.3. An example of this is in TR 13.9.6, "Storage Pool Ventilation (fuel storage)." TR 13.9.6 has an Applicability of "Whenever irradiated fuel is in the fuel storage pool." Therefore, this TR can be applicable in any or all MODES. If the TR and the Required Actions of TR 13.9.6 are not met , the Required Action of TR 13.9.6 of "Suspend all operations involving movement of fuel within the storage pool until required penetration room filtration system is restored to FUNCTIONAL status" is the appropriate Required Action to complete in order to ensure the safe operation of the unit in any operating MODE. These exceptions are addressed in the individual Technical Requirements.

13.0.4 MODE CHANGES TR 13.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when a TR is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the TR would not be met, in accordance with TR 13.0.4a, TR 13.0.4b, or TR 13.0.4c.

TR 13.0.4a allows entry into a MODE or other specified condition in the Applicability with the TR not met 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. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change.

Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions. TR 13.0.4b allows entry into a MODE or other specified condition in the Applicability with the TR not met after performance of a risk assessment addressing nonfunctional 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.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities be assessed and managed. The risk assessment, for the purposes of TR 13.0.4b, must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants."

Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These (continued)

Farley Units 1 and 2 B 13.0-4 Version 13.0 Technical Requirements Bases

TR Applicability B 13.0 BASES documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the TR would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

TR 13.0.4b may be used with single, or multiple systems and components unavailable.

NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The TR 13.0.4b risk assessments do not have to be documented.

The Technical Requirements allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the TR, the use of the TR 13.0.4b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there maybe a small subset of systems and components that have been determined to be more important to risk and use of the TR 13.0.4b allowance is prohibited.

The TRs governing these systems and components contain Notes prohibiting the use of TR 13.0.4b by stating that TR 13.0.4b is not applicable.

TR 13.0.4c allows entry into a MODE or other specified condition in the Applicability with the TR not met based on a Note in the requirement which states TR 13.0.4c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a requirement. The risk assessments performed to justify the use of TR 13.0.4b usually only consider systems and components. For this reason, TR 13.0.4c is typically applied to requirements which describe values and parameters (e.g., Containment Air Temperature, Containment Pressure, Moderator Temperature Coefficient), and may be applied to other requirements based on NRC plant-specific approval.

The provisions of this requirement should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to FUNCTIONAL status before entering an associated MODE or other specified condition in the Applicability.

(continued)

Farley Units 1 and 2 B 13.0-5 Version 9.0 Technical Requirements Bases

TR Applicability B 13.0 BASES The provisions of TR 13.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of TR 13.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.

In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Upon entry into a MODE or other specified condition in the Applicability with the TR not met, TR 13.0.1 and TR 13.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the TR is met, or until the unit is not within the Applicability of the Technical Requirements.

Surveillances do not have to be performed on the associated nonfunctional equipment (or on variables outside the specified limits), as permitted by TRS 13.0.1. Therefore, utilizing TR 13.0.4 is not a violation of TRS 13.0.1 or TRS 13.0.4 for any Surveillances that have not been performed on nonfunctional equipment. However, TRSs must be met to ensure FUNCTIONALITY prior to declaring the associated equipment FUNCTIONAL (or variable within limits) and restoring compliance with the affected TR.

13.0.5 OPERABILITY DETERMINATION / FUNCTIONALITY ASSESSMENT Regulatory Issues Summary (RIS) 2005-020 revised the Operability Determination (OD) guidelines (Inspection Manual, Part 9900) previously issued under Generic Letter 91 -18. The new guidelines introduced the concept of "Functionality" as applicable to Systems, Structures, and Components (SSCs) outside of the Technical Specifications (TS). Operability is now applied only to TS SSCs. Functionality is an attribute of SSCs that is not controlled by the TS.

However, when the Technical Requirements Manual (TRM) refers to TS equipment, it remains appropriate to refer to these SSCs as either operable or inoperable. The definition of operability assumes that an SSC described in TS can perform its specified function when all necessary support systems are capable of performing their related support functions.

Functionality Assessments are applied to those SSCs not described in the TS, specifically those SSCs that perform specified functions described in the Updated Final Safely Analysis (UFSAR),

TRM, Emergency Plan, Fire Protection Plan, regulatory commitments, or other elements of the Current Licensing Basis.

Operability Determinations are performed for those SSCs described in the TS. This includes those SSCs that are explicitly required to be operable by the TS as well as those that are not explicitly required to be operable by the TS, but that perform required support functions (as specified by the TS definition of operability) for SSCs that are required to be operable by the TS.

Note that for SSCs not explicitly required to be operable by the TS but that support SSCs that are explicitly required to be operable by the TS, degraded conditions are subject to Functionality Assessments. However, these Functionality Assessments provide input to an Operability Determination for the impacted supported TS SSCs.

(continued)

Farley Units 1 and 2 B 13.0-6 Version 9.0 Technical Requirements Bases

TR Applicability B 13.0 BASES TR 13.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared nonfunctional to comply with ACTIONS. The sole purpose of this Technical Requirement is to provide an exception to TR 13.0.2 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of required testing to demonstrate:

a. The FUNCTIONALITY of the equipment being returned to service; or

b. The FUNCTIONALITY or OPERABILITYof other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate FUNCTIONALITY. This Technical Requirement does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the FUNCTIONALITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the required testing.

An example of demonstrating the FUNCTIONALITY or OPERABILITY of other equipment is taking a nonfunctional channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the FUNCTIONALITY or OPERABILITY of other equipment is taking a nonfunctional channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

13.0.7 TEST EXCEPTIONS There are certain special tests and operations required to be performed at various times over the life of the unit. These special tests and operations are necessary to demonstrate select unit performance characteristics, to perform special maintenance activities, and to perform special evolutions. Test Exception TR 13.1.9 allows specified Technical Requirements (TRs) to be changed to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with the requirements of these TRs. Unless otherwise specified, all the other TRM requirements remain unchanged. This will ensure all appropriate requirements of the MODE or other specified condition not directly associated with or required to be changed to perform the special test or operation will remain in effect.

The Applicability of a Test Exception TR represents a condition not necessarily in compliance with the normal requirements of the TRM. Compliance with Test Exception TRs is optional. A special operation may be performed either under the provisions of the appropriate Test Exception TR or under the other applicable TRM requirements. If it is desired to perform the special operation under the provisions of the Test Exception TR, the requirements of the Test Exception TR shall be followed.

Farley Units 1 and 2 B 13.0-7 Version 13.0 Technical Requirements Bases

TRS Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT SURVEILLANCES (TRS) Applicability BASES TRS 13.0.1 through TRS 13.0.4 establish the general requirements applicable to all Technical Requirements and apply at all times, unless otherwise stated.

TRS 13.01 MODES TRS 13.0.1 establishes the requirement that TRSs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the TR apply, unless otherwise specified in the individual TRSs. This Technical Requirement is to ensure that Surveillances are performed to verify the FUNCTIONALITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with TRS 13.0.2, constitutes a failure to meet a TR.

Systems and components are assumed to be FUNCTIONAL when the associated TRSs have been met. Nothing in this Technical Requirement, however, is to be construed as implying that systems or components are FUNCTIONAL when:

a. The systems or components are known to be nonfunctional, although still meeting the TRSs; or

b. The requirements of the Surveillance(s) are known not to be met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated TR are not applicable, unless otherwise specified. The TRSs associated with a test exception are only applicable when the test exception is used as an allowable exception to the requirements of a Technical Requirement.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given TRS. In this case, the unplanned event may be credited as fulfilling the performance of the TRS. This allowance includes those TRSs whose performance is normally precluded in a given MODE or other specified condition.

Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on nonfunctional equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with TRS 13.0.2, prior to returning equipment to FUNCTIONAL status.

(continued)

Farley Units 1 and 2 B 13.0-8 Version 9.0 Technical Requirements Bases

TRS Applicability B 13.0 BASES Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment FUNCTIONAL. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with TRS 13.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered FUNCTIONAL provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function.

This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

TRS 13.0.2 REQUIRED ACTIONS TRS 13.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per . . ." interval.

TRS 13.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the TRSs. The exceptions to TRS 13.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Technical Requirements.

As stated in TRS 13.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per ..." basis. The 25%

extension applies to each performance after the initial performance. The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25%

extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the nonfunctional equipment in an alternative manner.

The provisions of TRS 13.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

Farley Units 1 and 2 B 13.0-9 Version 9.0 Technical Requirements Bases

TRS Applicability B 13.0 BASES TRS 13.0.3 COMPLETION TIMES TRS 13.0.3 establishes the flexibility to defer declaring affected equipment nonfunctional or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of 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, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with TRS 13.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Surveillances that have been missed.

This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.

When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance. However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.

TRS 13.0.3 provides a time limit for, and allowances for the performance of, Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions.

Failure to comply with specified Frequencies for TRSs is expected to be an infrequent occurrence. Use of the delay period established by TRS 13.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the limit of the specified Frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity. The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance. This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." The Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation (continued)

Farley Units 1 and 2 B 13.0-10 Version 9.0 Technical Requirements Bases

TRS Applicability B 13.0 BASES may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed Surveillances for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the licensee's Corrective Action Program.

If a Surveillance is not completed within the allowed delay period, then the equipment is considered nonfunctional or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable TR Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is nonfunctional, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable TR Conditions begin immediately upon the failure of the Surveillance.

Completion of the Surveillance within the delay period allowed by this Technical Requirement, or within the Completion Time of the ACTIONS, restores compliance with TRS 13.0.1.

TRS 13.0.4 MODE CHANGES TRS 13.0.4 establishes the requirement that all applicable TRSs must be met before entry into a MODE or other specified condition in the Applicability.

This requirement ensures that system and component FUNCTIONALITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this requirement should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to FUNCTIONAL status before entering an associated MODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when a TR is not met due to Surveillance not being met in accordance with TR 13.0.4.

However, in certain circumstances, failing to meet a TRS will not result in TR 13.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is nonfunctional or outside its specified limits, the associated TRS(s) are not required to be performed, per TRS 13.0.1, which states that surveillances do not have to be performed on nonfunctional equipment. When equipment is nonfunctional, TRS 13.0.4 does not apply to the associated TRS(s) since the requirement for the TRS(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in a TRS 13.0.4 restriction to changing MODES or other specified conditions in the Applicability. However, since the TR is not met in this instance, TR 13.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.

(continued)

Farley Units 1 and 2 B 13.0-11 Version 9.0 Technical Requirements Bases

TRS Applicability B 13.0 BASES TRS 13.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the TR not met has been delayed in accordance with TRS 13.0.3.

The provisions of TRS 13.0.4 shall not prevent entering into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of TRS 13.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

The precise requirements for performance of TRSs are specified such that exceptions to TRS 13.0.4 are not necessary. The specific time frames and conditions necessary for meeting the TRSs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated TR prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the TRs Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of TRSs' annotation is found in Section 11.4, Frequency.

Farley Units 1 and 2 B 13.0-12 Version 4.0 Technical Requirements Bases

Reactivity Control Systems B 13.1 B 13.1 REACTIVITY CONTROL SYSTEMS BASES SHUTDOWN MARGIN TR 13.1.1 Shutdown Margin A sufficient SHUTDOWN MARGIN ensures that:

1) the reactor can be made subcritical from all operating conditions,

2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and

3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN as specified in the COLR is required to control the reactivity transient.

Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions.

BORATION SYSTEMS TR 13.1.2 Boration Flow Path- Shutdown TR 13.1.3 Boration Flow Paths- Operating TR 13.1.4 Charging Pump- Shutdown TR 13.1.5 Charging Pumps- Operating TR 13.1.6 Borated Water Source- Shutdown TR 13.1.7 Borated Water Sources- Operating The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, and 5) an emergency power supply from OPERABLE diesel generators. With the RCS average temperature above 200°F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths nonfunctional. The boration capability of either flow path is sufficient to provide the required SHUTDOWN MARGIN from expected operating conditions after xenon decay and cooldown to 200°F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 11,336 gallons of 7000 ppm borated water from the boric acid storage tanks or 44,826 gallons of 2300 ppm borated water from the refueling water storage tank.

(continued)

Farley Units 1 and 2 B 13.1-1 Version 9.0 Technical Requirements Bases

Reactivity Control Systems B 13.1 B 13.1 REACTIVITY CONTROL SYSTEMS BASES With the RCS temperature below 200°F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes nonfunctional.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Technical Specification Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 180°F provides assurance that a mass addition pressure transient can be relieved by the operation of a single RHR relief valve. Two charging pumps may be capable of injecting into the RCS for a short time to allow the pumps to be swapped. This allows seal injection flow to be continually maintained, thus, minimizing the potential for RCP number one seal damage by reducing pressure transients on the seal and by preventing RCS water from entering the seal. Particles in the RCS water may cause wear on the seal surfaces and loss of seal injection pressure may cause the seal not to fully reseat when pressure is reapplied. Low temperature overpressure protection is most critical during shutdown when the RCS is water solid. Mass input transients can cause a very rapid increase in RCS pressure allowing little time for operator action to mitigate the event. For these reasons, more than one pump should be made capable of injecting into the RCS only when the RCS is in a non water solid condition and when both RHR relief valves are OPERABLE or the RCS is vented via an opening of at least 5.7 square inches. A 5.7 square inch opening is equivalent to the throat size area of two RHR relief valves.

The boron capability required below 200°F is sufficient to provide a SHUTDOWN MARGIN as specified in the COLR after xenon decay and cooldown from 200°F to 140°F. This condition requires either 2,000 gallons of 7000 ppm borated water from the boric acid storage tanks or 7,750 gallons of 2300 ppm borated water from the refueling water storage tank.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 10.5 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The FUNCTIONALITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

Operability is applied only to TS SSCs. Functionality is an attribute of SSCs that is not controlled by the TS. However, when the Technical Requirements Manual (TRM) refers to TS equipment, it remains appropriate to refer to these SSCs as either operable or inoperable.)

Farley Units 1 and 2 B 13.1-2 Version 18.0 Technical Requirements Bases

Reactivity Control Systems B 13.1 BASES MOVABLE CONTROL ASSEMBLIES TR 13.1.8 Position Indication System- Shutdown TR 13.1.9 Test Exception for Position Indication System- Shutdown TR 13.1.10 Rod Drop Time TR 13.1.8 Position Indication System-Shutdown Control rod positions and FUNCTIONALITY of the rod position indicators are required to be verified when the reactor trip breakers are closed and the rod control system is capable of rod withdrawal. In MODES in which the reactor is required to be shut down, FUNCTIONALITY of rod position indicators provides positive assurance that the control rods are being maintained in a safe condition.

TR 13.1.9 Test Exception for Position Indication System- Shutdown This special test exception permits the position indication channels to be nonfunctional during rod drop time measurements. The exception is required since the data necessary to determine the rod drop time is derived from the induced voltage in the position indicator coils as the rod is dropped. This induced voltage is small compared to the normal voltage and, therefore, can not be observed if the position indication channels remain FUNCTIONAL.

TR 13.1.10 Rod Drop Time The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with Tavg greater than or equal to 541°F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Farley Units 1 and 2 B 13.1-3 Version 9.0 Technical Requirements Bases

Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES TR 13.3.1 Movable Incore Detectors The FUNCTIONALITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The FUNCTIONALITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring FQ(Z) and Fxy a full incore flux map is used. Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system. Full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is nonfunctional.

TR 13.3.2 High Energy Line Break Isolation Sensors The high energy line break isolation sensors are designed to mitigate the consequences of the discharge of steam and/or water to the affected room and other lines and systems contained therein. In addition, the sensors will initiate signals that will alert the operator to bring the plant to a shutdown condition.

TR 13.3.3 Turbine Overspeed Protection This Technical Requirement is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are FUNCTIONAL and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

TR 13.3.4 Radiation Monitoring Instrumentation The FUNCTIONALITY of the radiation monitoring channels ensures that:

1) the radiation levels are continually measured in the areas served by the individual channels and

2) the alarm is initiated when the radiation level trip setpoint is exceeded.

Farley Units 1 and 2 B 13.3-1 Version 13.0 Technical Requirements Bases

Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES TR 13.3.5 Electric Hydrogen Recombiner Instrumentation and Control Circuits The FUNCTIONALITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. The containment atmosphere post-accident sampling system can be used as an alternative to a hydrogen analyzer should a hydrogen analyzer become nonfunctional. Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.

TR 13.3.6 Seismic Monitoring Instrumentation The FUNCTIONALITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude 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 facility to determine if plant shutdown is required pursuant to EPRI NP-5930, July 1988 and NP-6695, December 1988.

The instrumentation is consistent with the recommendations of EPRI TR-104239, Seismic Instrumentation in Nuclear Power Plants for Response to OBE Exceedance: Guidelines for Implementation, July 1994.

TR 13.3.7 Meteorological Monitoring Instrumentation The FUNCTIONALITY of the meteorological 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 and is generally consistent with the recommendations of Regulatory Guide 1.23, Onsite Meteorological Program, February 1972.

TR 13.3.8 Containment Hydrogen Monitors This TR was added to support NRC commitment # 10755 as defined in NRC Safety Evaluation Report (SER) for Technical Specifications (TS) Amendments 167/159 (Unit 1/Unit 2), dated March 8, 2005. These amendments removed the hydrogen recombiners from the TS. SNC committed to include the hydrogen monitors within the post accident monitoring instruments program described in the FSAR.

Farley Units 1 and 2 B 13.3-2 Version 13.0 Technical Requirements Bases

Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES The FUNCTIONALITY of the containment hydrogen monitors ensures the detection of high hydrogen concentration conditions that represent a potential for containment breach from a hydrogen explosion. This variable is also important in verifying the adequacy of mitigating actions. The hydrogen monitors are not Type A or Category I instrumentation (reference A-181866 and A-204866 Unit 1 & Unit 2, RG 1.97 Compliance Review and NRC SER for FNP RG 1.97 Compliance Report, Letter, Reeves to McDonald, 2/12/87).

The containment hydrogen monitors are part of the Post Accident Monitoring Display Instrumentation discussed in FSAR section 7.5.

Farley Units 1 and 2 B 13.3-3 Version 13.0 Technical Requirements Bases

Reactor Coolant System B 13.4 B 13.4 REACTOR COOLANT SYSTEM BASES TR 13.4.1 Chemistry The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.

The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The Technical Requirement Surveillances provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

TR 13.4.2 Pressurizer The pressurizer heatup and cooldown rates shall not exceed 100°F/hr and 200°F/hr respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 320°F.

System preservice hydrotests and in-service leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI.

Allowable pressure-temperature relationships for various heatup and cooldown rates are calculated using methods derived from Appendix G in Section XI of the ASME Boiler and Pressure Vessel Code as required by Appendix G to 10 CFR Part 50 and these methods are discussed in detail in WCAP-14040-NP-A, Revision 2, and the NRC letters dated March 31, 1998 and April 3, 1998.

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit for performance of engineering evaluation was established based on engineering judgment, to allow an adequate time for performance while ensuring promptness.

Farley Units 1 and 2 B 13.4-1 Version 3.0 Technical Requirements Bases

Reactor Coolant System B 13.4 B 13.4 REACTOR COOLANT SYSTEM BASES TR 13.4.3 Reactor Vessel Head Vents The FUNCTIONALITY of the Reactor Head Vent System ensures that adequate core cooling can be maintained in the event of the accumulation of non-condensable gases in the reactor vessel. This system is in accordance with 10 CFR 50.44(c)(3)(iii).

TR 13.4.4 Safety Valves- Shutdown The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 345,000 lbs per hour of saturated steam at the valve set point. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are FUNCTIONAL, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).

TR 13.4.5 RCS Pressure Isolation Valve (PIV) Leakage The Technical Requirement Surveillances for RCS Pressure Isolation Valves provide added assurance of valve integrity, thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS Pressure Isolation valves is IDENTIFIED LEAKAGE and will be considered a portion of the allowed limit.

Farley Units 1 and 2 B 13.4-2 Version 15.0 Technical Requirements Bases

Emergency Core Cooling Systems B 13.5 B 13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

BASES TR 13.5.1 Emergency Core Cooling System (ECCS)

As per TR 13.0.5, the term "operable" should be used for Structures, Systems, and Components (SSCs) that are explicitly required to be operable by the Technical Specifications (TSs) as well as those that are not explicitly required to be operable by the TSs, but that perform required support functions (as specified by the TS definition of operability) for SSCs that are required to be operable by the TSs. The definition of operability assumes that an SSC described in TSs can perform its specified function when all necessary support systems are capable of performing their related support functions. Since the ECCS is a SSC that is explicitly required to be operable in MODES 1, 2, and 3 while operating and MODE 4 during shutdown in TS 3.5.2 and 3.5.3, the term "operable," and all of its forms , should be used.

The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration. Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.

With the RCS temperature below 350°F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The Technical Specification Surveillance Requirements and Technical Requirement Surveillances provided to ensure OPERABILITY of each component ensure that at a minimum the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Technical Specification Surveillance Requirements and Technical Requirement Surveillances for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

Farley Units 1 and 2 B 13.5-1 Version 9.0 Technical Requirements Bases

Containment Systems B 13.6 B 13.6 CONTAINMENT SYSTEMS BASES TR 13.6.1 Containment Ventilation System Leakage Rate The purpose of the comparison of the results of degradation tests of the isolation valves in the containment purge supply and exhaust lines per TRS 13.6.1 is to identify excessive degradation of the resilient seals for these valves. In addition, these degradation tests are not subject to the requirements applicable to 10CFR50 Appendix J testing but are to be utilized to provide reasonable assurance that at least one set (inside containment or outside containment) of isolation valves provides a sufficient barrier to containment leakage. These degradation tests do not replace Appendix J testing, but are performed in addition to the type C tests required by Appendix J. Failure to satisfy the containment purge supply and exhaust isolation valve leakage rate specifications while in MODES 1-4 will be governed by the ACTION requirements of TS 3.6.3.D.

TR 13.6.2 Containment Isolation Valves The purpose of TR 13.6.2 is to ensure that containment isolation valves are restored to an operable status following maintenance activities which could affect their stoke times. Activities such as cleaning or inspection of the power circuits which do not affect the stroke time are not considered to be maintenance and therefore verification of isolation times is not required.

The FUNCTIONALITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

Farley Units 1 and 2 B 13.6-1 Version 9.0 Technical Requirements Bases

Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES TR 13.7.1 Steam Generator Pressure/Temperature Limitation The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70°F and 200 psig are based on steam generator average impact values taken at 10°F and are sufficient to prevent brittle fracture.

TR 13.7.2 Snubbers Snubbers that are supporting safety equipment that is in the Technical Specifications are required to be OPERABLE. All other snubbers are required to be FUNCTIONAL. This ensures 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 inspection program 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.

A manual, which contains a tabulation of the hydraulic and mechanical snubbers which are within the scope of TR 13.7.2, is maintained as a comprehensive list of snubbers which are to be included in the snubber inspection and test program. The snubbers originally in the program were identified in Technical Specification Tables 3.7-4a and 3.7-4b as of License Amendment No. 43. (Unit 1) and 34 (Unit 2) and also reflected changes identified in Alabama Power Company letter dated December 8, 1983, entitled, Safety-Related Snubber Technical Specification Table Changes. The manual will be controlled in accordance with 10 CFR 50.59.

Beginning with the Unit 2 R19 Refueling Outage (Fall 2008), the snubber inservice examination and testing meets the requirements of the ASME OM Code, 2001 Edition with Addenda through 2003 as supplemented by ASME OM Code Case OMN-13, Revision 0 and 10 CFR 50.55a(b)(3)(v), dated October 1, 2004.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of nonfunctional snubbers found during an inspection. ASME OM Code Case OMN-13 provides an alternative for extending the visual examination interval provided the extension is justified by visual examination results.

When a snubber is found nonfunctional, an engineering evaluation is performed. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the attached component.

(continued)

Farley Units 1 and 2 B 13.7-1 Version 9.0 Technical Requirements Bases

Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.) in accordance with the ASME OM Code, Article ISTD-6000. The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

TR 13.7.3 Sealed Source Contamination The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 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 with Technical Requirement Surveillances commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

Farley Units 1 and 2 B 13.7-2 Version 6.0 Technical Requirements Bases

Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES TR 13.7.4 Ultimate Heat Sink (UHS) Support Structures Maintenance of the UHS Support Structures in accordance with applicable maintenance requirements ensures that the UHS has the capability to perform its design basis functions as defined in FSAR section 9.2.5.1.A, during and after the most severe natural phenomena expected at the site, or site related events that may occur during the plant lifetime, in conformance with the criteria of Regulatory Guide 1.27. It also ensures that loss of the pond dam will not become a credible failure, in accordance with the accident analysis in FSAR section 9.2.5.

The measurement of the ground water seepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

TR 13.7.5 Area Temperature Monitoring (Unit 2 Only)

The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its FUNCTIONALITY.

The temperature limits include an allowance for instrument error of 2°F.

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit for performance of engineering evaluation was established based on engineering judgment, to allow an adequate time for performance while ensuring promptness.

Farley Units 1 and 2 B 13.7-3 Version 9.0 Technical Requirements Bases

Electrical Power Systems B 13.8 B 13.8 ELECTRICAL POWER SYSTEMS BASES TR 13.8.1 Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)

Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the FUNCTIONALITY of overcurrent protection circuit breakers during periodic surveillance.

The tabulation of required containment penetration conductor overcurrent protective devices and circuits which are within the scope of TR 13.8.1 are contained in Farley Nuclear Plant procedures. The overcurrent protection devices and circuits originally in the program were identified in Unit 2 License Amendment 34. The procedures will be controlled in accordance with 10CFR50.59.

TR 13.8.2 Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)

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

The FUNCTIONALITY of the motor operated valves thermal overload protection devices ensures that these devices will not prevent safety related valves from performing their function.

The Technical Requirement Surveillances for demonstrating the FUNCTIONALITY of these devices are in accordance with Regulatory Guide 1.106 "Thermal Overload Protection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.

If one or more thermal overload protection device(s) are nonfunctional the operability of the valve is affected. The Required Action in TR 13.8.2 A.1 requires a TS Condition to be entered and the related TS Required Actions to be completed. The definition of "functional", as per TR 13.0.5, does not apply to the valve(s) only to the thermal overload protection devices.

TR 13.8.3 Emergency Diesel Generators (EDG) Maintenance and Inspection Requirements The Technical Requirement Surveillances for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9, Selection of Diesel Generator Set Capacity for Standby Power Supplies, March 10, 1971, and 1.108, Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants, Revision 1, August 1977. Emergency Diesel Generators provide power to the Emergency Safety Feature loads due to a loss of offsite power along with a Loss of Coolant (continued)

Farley Units 1 and 2 B 13.8-1 Version 9.0 Technical Requirements Bases

Electrical Power Systems B 13.8 B 13.8 ELECTRICAL POWER SYSTEMS BASES Accident. The EDGs perform required support functions for other SSCs that are required to be operable by TSs, the term functional will not replace operable in TR subsection 13.8.3. TR 13.8.3 was revised by STI Evaluation Number 558904.

Farley Units 1 and 2 B 13.8-2 Version 11.0 Technical Requirements Bases

Refueling Operations B 13.9 B 13.9 REFUELING OPERATIONS BASES TR 13.9.1 Decay Time The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time of 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months is consistent with the assumptions used in the SFP cooling analyses. [Note: A decay time of 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months is assumed in the fuel handling accident analysis.]

TR 13.9.2 Communications The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

TR 13.9.3 Manipulator Crane The FUNCTIONALITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of control rods and fuel assemblies,

2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and

3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

TR 13.9.4 Crane Travel- Spent Fuel Storage Building TR 13.9.5 Spent Fuel Cask Crane The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool 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 accident analyses.

(continued)

Farley Units 1 and 2 B 13.9-1 Version 19.0 Technical Requirements Bases

Refueling Operations B 13.9 BASES The outdoor overhead gantry crane does not meet the design requirements for wire rope strength and fleet angle safety margins of reeving systems, therefore the ropes must be inspected to assure that they meet the requirements of the standard specified in the surveillance. Cold proof tests of the crane or material testing will be performed to demonstrate FUNCTIONALITY.

TR 13.9.6 Storage Pool Ventilation (Fuel Storage)

The limitations on the storage pool ventilation system ensure that all radioactive material released from a recently irradiated fuel assembly (i.e., fuel that has occupied part of a critical reactor core within the previous 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months ) will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Due to radioactive decay, a fuel handling accident involving handling non-recently irradiated fuel (i.e., fuel that has not occupied part of a critical reactor core within the previous 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months ) will result in doses that are within the guideline values specified in 10 CFR 50.67. The FUNCTIONALITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

TR 13.9.7 Average Reactor Coolant Temperature This Technical Requirement is provided to ensure that the average reactor coolant temperature remains consistent with initial conditions assumed in analysis of a dilution event during refueling. Supporting this requirement is also a Technical Specification requirement that at least one residual heat removal pump be in operation in MODE 6 to provide sufficient coolant circulation to minimize the effects of a boron dilution accident and prevent boron stratification.

Farley Units 1 and 2 B 13.9- 2 Version 19.0 Technical Requirements Bases

EGSTRAM Program B 13.12 B 13.12 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING (EGSTRAM) PROGRAM BASES TR 13.12.1 Waste Gas Monitoring Instrumentation This instrumentation monitors (and controls) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The FUNCTIONALITY and use of this instrumentation are consistent with the requirements of General Design Criteria 60 and 63 of Appendix A to 10 CFR Part 50.

TR 13.12.2 Liquid Holdup 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 10 CFR Part 20, Appendix B, (to paragraphs 20.1001 -20.2401), Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

TR 13.12.3 Waste Gas Monitoring This Technical Requirement is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. During recombiner operation, an automatic control feature is included in the system to prevent the oxygen concentration from reaching these flammability limits. The automatic control feature includes isolation of the source of oxygen (the recombiner oxygen supply), to reduce the concentration below the flammability limit. When the recombiner is not operating and thus the recombiner oxygen supply is isolated, a grab sample can be taken to measure oxygen levels in the waste gas system. Maintaining the concentration of oxygen below the flammability limit when hydrogen is above 4% by volume provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

TR 13.12.4 Gas Storage Tanks Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, "Waste Gas System Failure".

Farley Units 1 and 2 B 13.12-1 Version 9.0 Technical Requirements Bases

Emergency Response Facilities B 13.13.1 B 13.13 EMERGENCY RESPONSE FACILITIES B 13.13.1 Emergency Response Facilities BASES Applicability This TR is applicable to the Technical Support Center (TSC), the Operations Support Center (OSC), and the Emergency Operations Facility (EOF).

Emergency events could occur during all modes of operation; consequently, the emergency response facilities (ERFs) shall be FUNCTIONAL at all times.

Conditions Condition A The 1-hour completion time is acceptable since it is within the ERF activation time specified in the Emergency Plan. If alternate locations for performing the ERF functions for the affected facility are not available, then Condition B is immediately entered.

Condition B If the alternate locations are available, then no additional compensatory actions may be needed, provided the necessary compensatory actions are encompassed in the procedures for the alternate locations. If the alternate locations are not available, then compensatory actions must immediately be put in place.

Reference NMP-AD-031 for potential reporting criteria.

Admittedly, the term high priority is subjective. Consequently, the following clarification is provided: In the context of this TR, high priority is taken to mean that all necessary resources (for example, work planning, parts expediting, vendor support, craft support, etc.) for prompt restoration of a component, facility or function are applied to include 24/7 support as necessary to restore the facility to FUNCTIONAL status upon completion of the work activity. Planned maintenance in excess of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is allowed under the provision of CONDITION A and CONDITION B. The planned maintenance activity shall occur with the high priority objective to minimize the time the ERF is not FUNCTIONAL.

Farley Units 1 and 2 B 13.13.1-1 Version 16.0 Technical Requirements Bases

Emergency Response Facilities B 13.13.1 BASES FUNCTIONALITY Requirements TSC The following is required for FUNCTIONALITY of the TSC:

The ventilation system for radiological control.

Offsite dose projection capability.

Communication capability between control room, TSC, OSC, EOF, Field Monitoring Teams and offsite agencies.

Event assessment capability.

If any of the following are out of service, the impact of their loss shall be evaluated in determining the ability of the TSC to perform its required function:

Climate control capable of maintaining an adequate environment.

Communication devices capable of performing the indicated function as provided below:

Communication Function FNP TSC Management with EOF Commercial Telephone Lines TSC/EOF/OSC Conference Bridge Radio Resource Management Commercial Telephone Lines (Offsite Premises Extension) OPX Radiological Monitoring Southern LINC Kenwood Radio System The Emergency Notification Network ENN (ENN) and Offsite Protective Action Commercial Telephone Lines Recommendations (PAR)

The Emergency Notification System (ENS) for NRC notifications.

Availability of plant procedures and plant drawings. For example:

Technical Specifications, EOPs, plant operating procedures, emergency implementing procedures, system piping and instrumentation drawings, and elementary diagrams.

Farley Units 1 and 2 B 13.13.1-2 Version 16.0 Technical Requirements Bases

Emergency Response Facilities B 13.13.1 BASES

Emergency supplies and equipment as delineated in the Emergency Plan, section III.

Technical data displays for event assessment.

OSC The following is required for FUNCTIONALITY of the OSC:

Communication capability with the TSC and control room.

If any of the following are out of service, the impact of their loss shall be evaluated in determining the ability of the OSC to perform its required function:

Emergency equipment supplies as delineated in the Emergency Plan, section III.

Communication devices capable of performing the indicated function as provided below:

Communication Function FNP OSC Management with TSC Commercial Telephone Lines TSC/EOF/OSC Conference Bridge Resource Management Commercial Telephone Lines OPX Radiological Monitoring Portable Radio Equipment EOF The following is required for FUNCTIONALITY of the EOF:

Offsite dose projection capability.

Communication capability between control room, TSC, OSC, EOF and offsite agencies.

If any of the following are out of service, the impact of their loss shall be evaluated in determining the ability of the EOF to perform its required function:

Technical data displays.

Availability of procedural information for EOF positions.

Communication devices capable of performing the indicated function as provided below:

Farley Units 1 and 2 B 13.13.1-3 Version 8.0 Technical Requirements Bases

Emergency Response Facilities B 13.13.1 BASES Communication Function FNP TSC Management with EOF Commercial Telephone Lines TSC/EOF/OSC Conference Bridge Radio Resource Management Commercial Telephone Lines OPX Radiological Monitoring Southern LINC Kenwood Radio System Offsite (PARs) ENN Commercial Telephone Lines Technical Requirement Surveillances TRS 13.13.1.1 Procedure FNP-2-ETP-4181, TSC Systems Filtration Performance Testing, requires FUNCTIONAL testing of the TSC ventilation and filtration system. A suitable environment must be maintained in the TSC for personnel occupancy and equipment operation during radiological events. To accomplish this, the TSC ventilation and filtration system provides an adequate supply of filtered, fresh air during accident conditions, as well as minimizing airborne radioactivity in the TSC during and after an accident. FUNCTIONAL testing of the ventilation system is therefore performed to ensure the TSC remains habitable.

TRS 13.13.1.2 Procedure FNP-0-EIP-16.0, Emergency Equipment and Supplies, requires that inventories be performed of equipment in the TSC once per calendar quarter. This TRS also ensures the availability of emergency equipment supplies that are normally kept in the OSC. This surveillance ensures that the ERFs are maintained in a state of readiness with respect to the equipment and items necessary for emergency response. If some items are not in place, they shall be immediately replaced. However, if certain items cannot be replaced, Emergency Preparedness personnel shall evaluate their loss with respect to the FUNCTIONALITY of the respective ERF.

Farley Units 1 and 2 B 13.13.1-4 Version 12.0 Technical Requirements Bases

Emergency Response Facilities B 13.13.1 BASES Communication equipment capable of performing the indicated functions provided below shall be available. Availability of any combination of equipment to perform the desired function is acceptable to maintain ERF FUNCTIONALITY for communications.

Communication Function FNP TSC Management with EOF and EOF Commercial Telephone Lines Management with TSC TSC/EOF/OSC Conference Bridge Radio Resource Management Commercial Telephone Lines OPX Radiological Monitoring Southern LINC Kenwood Radio System Offsite (PARs) ENN Commercial Telephone Lines For onsite ERFs, Procedure FNP-0-EPP-3.0, Emergency Communications Operability Tests, requires FUNCTIONAL testing of the ENN and ENS offsite notification systems every calendar month. The multiline ERF phones require FUNCTIONAL testing each calendar quarter and provide communications within the plant during an emergency to facilitate event diagnosis, the assignment and dispatch of emergency personnel, and information updates of plant conditions.

The ENN and ENS systems are the primary methods of notifying State and local authorities and the NRC and, as such, these systems should remain FUNCTIONAL. ENN and ENS equipment are available in both the TSC and EOF. Testing of EOF communication equipment is performed quarterly in accordance with NMP-EP-300.

A single nonfunctional communications system will not necessarily indicate a nonfunctional ERF. Emergency Preparedness shall evaluate each case in determining the FUNCTIONALITY of the particular ERF.

Procedure FNP-0-EIP-16.0, Emergency Equipment and Supplies, requires FUNCTIONAL testing of offsite dose projection equipment once per calendar month. Initial offsite dose projections are often made from the TSC. Followup projections are usually made from the EOF.

Consequently, it is appropriate that both facilities retain FUNCTIONAL offsite dose projection equipment. The calendar month frequency is appropriate since, realistically, the offsite dose projection equipment will be also tested during the three or four drills that are held each year at Plant Farley.

Farley Units 1 and 2 B 13.13.1-5 Version 16.0 Technical Requirements Bases

NL-20-0442, Revisions to Technical Requirements Manual (TRM)

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