NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Requirements Manual
Text
Technical Requirements Manual (TRM)
Joseph M. Farley Nuclear Plant
Units 1 and 2
Table of Contents Farley Units 1 and 2 i Version 29.0 Technical Requirements 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)
Table of Contents Farley Units 1 and 2 iii Version 29.0 Technical Requirements 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
Use and Application 11.0 (continued)
Farley Units 1 and 2 11.0 - 1 Version 22.0 Technical Requirements 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.
Use and Application 11.0 Farley Units 1 and 2 11.0 - 2 Version 29.0 Technical Requirements 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),
Use and Application 11.0 Farley Units 1 and 2 11.0 - 3 Version 29.0 Technical Requirements 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.
TR Applicability 13.0 Farley Units 1 and 2 13.0 - 1 Version 29.0 Technical Requirements 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)
TR Applicability 13.0 Farley Units 1 and 2 13.0 - 2 Version 29.0 Technical Requirements 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.
TRS Applicability TRS 13.0 (continued)
Farley Units 1 and 2 13.0-3 Version 24.0 Technical Requirements 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 TRS Applicability TRS 13.0 Farley Units 1 and 2 13.0-4 Version 24.0 Technical Requirements 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.
SDM MODES 1 and 2 TR 13.1.1 Farley Units 1 and 2 13.1.1 - 1 Version 8.0 Technical Requirements 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 k eff 1.0 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. SDM not within limit.
A.1 Initiate boration to restore SDM to within limit.
Immediately TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.1.1 Verify SDM within limit with the control banks at the maximum insertion limit specified in the COLR and considering the following factors:
- 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 Prior to initial operation above 5%
RTP after each fuel loading.
Boration Flow Path - Shutdown TR 13.1.2 Farley Units 1 and 2 13.1.2 - 1 Version 24.0 Technical Requirements 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
- 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 nonfunctional.
A.1 Suspend CORE ALTERATIONS.
AND A.2 Suspend positive reactivity changes.
Immediately
Immediately
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 Boration Flow Path - Shutdown TR 13.1.2 Farley Units 1 and 2 13.1.2 - 2 Version 24.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.1.2.2 Verify that each manual, power operated, or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
31 days 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 pump develops a discharge pressure of 100 psig.
31 days Boration Flow Paths - Operating TR 13.1.3 Farley Units 1 and 2 13.1.3 - 1 Version 29.0 Technical Requirements 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 nonfunctional in MODE 1 or 2.
A.1 Restore at least two required flow paths to FUNCTIONAL status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One required flow path nonfunctional in MODE 3 or 4.
B.1 Restore at least two required flow paths to FUNCTIONAL status.
7 days
C. Required Actions and associated Completion
Times not met.
C.1 Initiate a Condition Report.
AND C.2 Continue action to restore the required flow path to FUNCTIONAL status.
Immediately Immediately
Boration Flow Paths - Operating TR 13.1.3 Farley Units 1 and 2 13.1.3 - 2 Version 24.0 Technical Requirements
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 boric acid tanks is 65 °F.
7 days TRS 13.1.3.2 Verify that each manual, power operated, or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
31 days 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 pump develops a discharge pressure of 100 psig.
31 days TRS 13.1.3.4 Verify required flow path from boric acid storage tanks delivers 30 gpm to the Reactor Coolant System.
While proceeding to
or in MODE 5 if not
performed in the
previous 12 months
Boration Pump - Shutdown TR 13.1.4 Farley Units 1 and 2 13.1.4 - 1 Version 24.0 Technical Requirements 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 nonfunctional.
A.1 Suspend CORE ALTERATIONS.
AND A.2 Suspend operations involving positive reactivity changes. Immediately
Immediately
Boration Pump - Shutdown TR 13.1.4 Farley Units 1 and 2 13.1.4 - 2 Version 29.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. More than one charging pump capable of injecting
into the RCS, except as allowed during pump swap operations.
B.1 Initiate action to render all but the above required FUNCTIONAL pump inoperable as specified in Technical Specifications SR
Immediately
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 required by TR 13.1.2 develops a differential pressure of 2323 psid.
In Accordance with
the Inservice Testing
Program TRS 13.1.4.2 TRS 13.1.2.3. is applicable when the boric acid transfer pump is required FUNCTIONAL.
In accordance with TRS 13.1.2.3 Charging Pumps - Operating TR 13.1.5
Farley Units 1 and 2 13.1.5 - 1 Version 29.0 Technical Requirements 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 pump nonfunctional in MODE 1 or 2.
A.1 Restore at least two charging pumps to FUNCTIONAL status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One required charging pump nonfunctional in MODE 3 or 4.
B.1 Restore at least two charging pumps to FUNCTIONAL status.
7 days
C. Required Action and associated Completion Time not met.
C.1 Initiate a Condition Report.
AND C.2 Continue action to restore the required charging pump to FUNCTIONAL status.
Immediately Immediately
Charging Pumps - Operating TR 13.1.5
Farley Units 1 and 2 13.1.5 - 2 Version 9.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.1.5.1 Verify that, on recirculation flow, each required charging pump develops a differential pressure of 2323 psid.
In Accordance with
the Inservice Testing
Program
Borated Water Source - Shutdown TR 13.1.6 Farley Units 1 and 2 13.1.6 - 1 Version 24.0 Technical Requirements 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 source nonfunctional.
A.1 Suspend CORE ALTERATIONS
AND
A.2 Suspend positive reactivity changes.
Immediately
Immediately
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. -----------------------------------------------------------------------------------------------------------------------------
Borated Water Sources - Operating TR 13.1.7 Farley Units 1 and 2 13.1.7 - 1 Version 29.0 Technical Requirements 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 storage system nonfunctional in MODE 1 or 2. A.1 Restore boric acid storage system to FUNCTIONAL status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Required boric acid storage system nonfunctional in MODE 3 or 4. B.1 Restore the boric acid storage system to FUNCTIONAL status.
7 days C. Required Actions and associated Completion Times of Condition A or B not met. C.1 Initiate a Condition Report.
AND C.2 Continue action to restore the boric acid storage system to FUNCTIONAL status. Immediately Immediately
Position Indication System - Shutdown TR 13.1.8 Farley Units 1 and 2 13.1.8 - 1 Version 24.0 Technical Requirements 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 for one or more shutdown or control rods nonfunctional.
A.1 Open the reactor trip system breakers.
Immediately TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.1.8.1 For each DRPI channel required FUNCTIONAL, verify the demand position indication system and the DRPI channels agree to within
+/- 12 steps.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Test Exception for Position Indication System - Shutdown TR 13.1.9 Farley Units 1 and 2 13.1.9 - 1 Version 24.0 Technical Requirements 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 DRPI nonfunctional during rod withdrawal.
OR More than one bank of rods withdrawn.
A.1 Open the reactor trip breakers.
Immediately
Test Exception for Position Indication System - Shutdown TR 13.1.9 Farley Units 1 and 2 13.1.9 - 2 Version 8.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.1.9.1 Verify the demand position indication system and the rod position indication system agree:
- a. Within 12 steps when the rods are stationary, and
- b. Within 24 steps during rod motion.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to initiation of rod drop time measurements
AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter
Rod Drop Time TR 13.1.10 Farley Units 1 and 2 13.1.10 - 1 Version 8.0 Technical Requirements 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, affected by maintenance on or modification to the control rod drive system which could affect the drop time, with rod drop time not within limits
A.1 Restore rod drop time to within limits.
Prior to reactor criticality
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.1.10.1 Verify, for specifically affected individual rods, rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:
- a. Tavg 541 °F; and
- b. All reactor coolant pumps operating.
Prior to reactor criticality, following maintenance on or modification to the control rod drive
system which could affect the drop time of those specific rods
High Energy Line Break Isolation Sensors TR 13.3.2 Farley Units 1 and 2 13.3.2 - 1 Version 29.0 Technical Requirements 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 energy line break isolation
instrumentation channels nonfunctional.
A.1 Restore the nonfunctional channel to FUNCTIONAL
status.
7 days B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate a Condition Report.
AND B.2 Continue action to restore the required channel(s) to FUNCTIONAL status.
Immediately
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.3.2.1 Perform a COT on each required instrument channel listed in Table 13.3.2-1.
In accordance with Table 13.3.2-1.
High Energy Line Break Isolation Sensors TR 13.3.2 Farley Units 1 and 2 13.3.2 - 2 Version 25.0 Technical Requirements Table 13.3.2-1 High-Energy Line Break Isolation Instrumentation Instrument Channel Sensor Location Required Channels Surveillance Frequency
- 1. Pressure Switches
- a. PDSH 3367 A,B
- b. PSH 2850 A,D B,F C,E
- c. PSH 2851 A,F B,C D,E d. PSH 2852 A,H B,C, D,E F,G e. PSH 2853 A,B C,D E,F f. PSH 2853 G,H I,J RHR Heat Exchanger Room El. 83 ft.
Auxiliary Feedwater Pump Room El. 100 ft. Equipment Room El. 100 ft.
Auxiliary Feedwater Pump Room Corridor El.
100 ft.
Recycle Holdup Tank Room El. 121 ft. Moderating Heat Exchanger Room El. 121 ft. Moderating Heat Exchanger Valve Room El.
121 ft. Piping Penetration Room El. 100 ft.
Letdown Heat Exchanger Room El. 100 ft. Recycle Holdup Tank Room El. 121 ft.
Piping Penetration Room El. 121 ft. Blowdown Heat Exchanger Room El. 130 ft. Corridor El. 121 ft. (Unit 1) / Recycle Evaporator Room El. 121 ft. (Unit 2)
Recycle Evaporator Room El. 121 ft.
Corridor El. 121 ft. (I) and Sluice Filter Room El. 121 ft. (J - Unit 1) / Blowdown Surge Tank Room El. 130 ft. (J - Unit 2)
1 1 1 1
1 1 1 1 1 1 1 1 1 1 1
18 months
- 2. Flooding Detectors
- a. LSH 2828 A,B,C b. LSH 2829 A,B,C Main Steam Room El. 127 ft.
Main Steam Room El. 127 ft.
2 2
36 months Turbine Overspeed Protection TR 13.3.3 Farley Units 1 and 2 13.3.3 - 1 Version 29.0 Technical Requirements 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 governor valve on one or
more high pressure turbine steam lines nonfunctional.
A.1 Restore nonfunctional valve(s) to FUNCTIONAL status.
OR A.2 Isolate the affected steampath(s).
OR A.3 Plant management to determine an alternate course of action that continues to assure the safe operation of the plant.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Turbine Overspeed Protection TR 13.3.3 Farley Units 1 and 2 13.3.3 - 2 Version 29.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One reheat stop valve or one reheat intercept valve
on one or more low pressure turbine steam lines nonfunctional.
B.1 Restore nonfunctional valve(s) to FUNCTIONAL status.
OR B.2 Isolate the affected steampath(s).
OR B.3 Plant management to determine an alternate course of action that continues to assure the safe operation of the plant.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. Required Action and associated Completion
Time of Condition A or B
protection system nonfunctional for reasons other than Condition A or B.
C.1 Isolate the turbine from the steam supply.
OR C.2 Plant management to determine an alternate course of action that continues to assure the safe operation of the plant.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.3.3.1 The provisions of TRS 13.0.4 are not applicable.
N/A
Radiation Monitoring Instrumentation TR 13.3.4
Farley Units 1 and 2 13.3.4 - 1 Version 24.0 Technical Requirements 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 monitoring channel(s) with alarm/trip setpoint exceeding limit.
A.1 Adjust the setpoint(s) to within the limit.
OR A.2 DecIare the channel(s) nonfunctional.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. The fuel storage pool area (R-5) radiation monitoring channel nonfunctional.
B.1 ------------NOTE-----------------The first performance of TRS 13.3.4.1 is not required to be
completed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after R-5 is declared nonfunctional. --------------------------------------
Initiate action to perform 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.
Immediately
Radiation Monitoring Instrumentation TR 13.3.4
Farley Units 1 and 2 13.3.4 - 2 Version 24.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. The plant vent stack effluent (R-29B) radiation monitoring channel nonfunctional.
OR One or more main steam relief and atmospheric steam dump discharge (R-60 A, B or C) radiation monitoring channel(s) nonfunctional.
OR The auxiliary feed pump
turbine exhaust (R-60D)
radiation monitoring channel nonfunctional.
OR One or more turbine building ventilation
exhaust (R-15 B or C)
radiation monitoring channel(s) nonfunctional.
C.1 Initiate the preplanned alternate method of monitoring the appropriate
parameter(s).
AND C.2 Restore the nonfunctional channel(s) to FUNCTIONAL status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
7 days D. Required Action and associated Completion
Time of Condition C not met.
D.1 Prepare and submit a report to the Commission outlining the action taken, the cause of the nonfunctionality and the plans and schedule for restoring the system to FUNCTIONAL status.
14 days
Radiation Monitoring Instrumentation TR 13.3.4
Farley Units 1 and 2 13.3.4 - 3 Version 24.0 Technical Requirements 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
monitoring instrumentation.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
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
Radiation Monitoring Instrumentation TR 13.3.4
Farley Units 1 and 2 13.3.4 - 4 Version 24.0 Technical Requirements Table 13.3.4-1 Radiation Monitoring Instrumentation Radiation Monitoring Instrument Channel Applicable Modes or Other specified Conditions Alarm/Trip Setpoint Required Channels Technical Requirement Surveillance
- 1. Area Monitors
- a. Fuel Storage Pool Area (R-5)
With fuel in the storage pool
15 mr/hr
1
TRS 13.3.4.1(Note 1) TRS 13.3.4.2 TRS 13.3.4.3 TRS 13.3.4.4
- 2. Process Monitors (Noble Gas Effluent Monitors)
- a. Plant Vent Stack Effluent Monitor (R-29B) b. Main Steam Relief and Atmospheric
Steam Dump Discharge (R-60A, B, C)
- c. Auxiliary Feed Pump Turbine Exhaust (R-60D) d. Turbine Building Ventilation
Exhaust (includes condenser air ejector exhaust) (R-15 B and C)
1, 2, 3, 4
1, 2, 3
1, 2, 3
1, and With vacuum in the condenser
N/A N/A
N/A N/A
1 3
1 2
Note 1: Only required to be performed when the fuel storage pool area radiation monitoring channel (R-5) is nonfunctional.
Electric Hydrogen Recombiners Instrumentation and Control Circuits TR 13.3.5 Farley Units 1 and 2 13.3.5 - 1 Version 8.0 Technical Requirements 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 hydrogen recombiner instrumentation or control circuit(s) not in calibration.
A.1 Initiate action to restore the circuit(s) to within calibration limits.
Immediately TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.3.5.1 Perform a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.
18 months
Seismic Monitoring Instrumentation TR 13.3.6 Farley Units 1 and 2 13.3.6 - 1 Version 29.0 Technical Requirements 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 seismic monitoring instrument channels nonfunctional.
A.1 Initiate action to restore the seismic monitoring instrument channel(s) to FUNCTIONAL status.
Immediately B. One or more seismic monitoring instruments actuated during a seismic event. B.1 Initiate action to retrieve and analyze data from the actuated seismic monitoring instruments to determine the magnitude of the vibratory ground motion.
AND B.2 Restore affected seismic monitoring instruments to FUNCTIONAL status.
AND B.3 Perform a CHANNEL CALIBRATION on the actuated seismic monitoring instruments.
AND Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5 days Seismic Monitoring Instrumentation TR 13.3.6 Farley Units 1 and 2 13.3.6 - 2 Version 29.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
B.4 Prepare and submit a special report to the Commission in accordance with 10 CFR 50.4 describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.
10 days TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.6.1 Perform a CHANNEL CHECK.
30 days TRS 13.3.6.2 Perform a CHANNEL OPERATIONAL TEST.
184 days TRS 13.3.6.3 Perform a CHANNEL CALIBRATION.
18 months
Seismic Monitoring Instrumentation TR 13.3.6 Farley Units 1 and 2 13.3.6 - 3 Version 29.0 Technical Requirements Table 13.3.6-1 Seismic Monitoring Instrumentation Instrumentation Number Sensor Location Measurement Range Required Channels Strong Motion Triaxial Accelographs 1A 1B 1C 2 3 Containment Base (1) Containment(1) Free Field Pond Intake Structure Diesel Generator Building
.5g full scale 1.0g full scale
.5g full scale
.5g full scale
.5g full scale 1 1 1 1 1
Notes: (1) Sensor located in Unit 1.
Meteorological Monitoring Instrumentation TR 13.3.7 Farley Units 1 and 2 13.3.7 - 1 Version 29.0 Technical Requirements 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 meteorological monitoring instrument channels nonfunctional.
A.1 Initiate action to restore the meteorological monitoring instrument channel(s) to FUNCTIONAL status.
Immediately TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.3.7.1 Perform a CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 13.3.7.2 ----------------------------NOTE-------------------------------------CHANNEL CALIBRATIONS for the wind speed instruments shall be performed according to the manufacturer's recommendations. -------------------------------------------------------------------------
Perform a CHANNEL CALIBRATION.
184 days Meteorological Monitoring Instrumentation TR 13.3.7 Farley Units 1 and 2 13.3.7 - 2 Version 29.0 Technical Requirements Table 13.3.7-1 Meteorological Monitoring Instrumentation Instrument Required Channels
- 1. WINDSPEED
- a. Meteorological tower, 10 m/32.8 ft
- b. Meteorological tower, 45.7 m/150 ft
- 2. WIND DIRECTION
- a. Meteorological tower, 10 m/32.8 ft
- b. Meteorological tower, 45.7 m/150 ft
- 3. AIR TEMPERATURE DIFFERENCE
- a. Meteorological tower, 60 m 10 m (196.9 ft to 32.8 ft) 1 of 2 1 of 2 1 of 2 1 of 2 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).
Containment Hydrogen Monitors TR 13.3.8 Farley Units 1 and 2 13.3.8 - 1 Version 29.0 Technical Requirements 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 hydrogen monitor instrument channels nonfunctional.
A.1 Initiate action to restore the containment hydrogen
monitor instrument channel(s) to FUNCTIONAL status. Immediately 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
RCS Chemistry TR 13.4.1 Farley Units 1 and 2 13.4.1 - 1 Version 29.0 Technical Requirements 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 parameters
> steady- state limit and transient limit in MODES 1, 2, 3, or
- 4. A.1 Restore parameter to within steady-state limit.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. One or more chemistry parameters
> transient limit in MODES 1, 2, 3, or
- 4. OR Required Action and associated Completion Time of Condition A not met. B.1 Plant management to determine an alternate course of action that continues to assure the safe operation of the plant.
OR B.2.1 Be in Mode 3.
AND B.2.2 Be in Mode 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> RCS Chemistry TR 13.4.1 Farley Units 1 and 2 13.4.1 - 2 Version 8.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE------------
All Required Actions must
be completed whenever this Condition is entered. ----------------------------------
Chloride or fluoride concentration
> steady-state limit for
> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any condition other than MODES 1, 2, 3, or 4.
OR Chloride or fluoride concentration
> transient limit in any condition other than MODES 1, 2, 3, or 4.
C.1 Initiate action to reduce the pressurizer pressure to 500 psig.
AND C.2 Perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural
integrity of the Reactor Coolant System.
AND C.3 Determine that the Reactor Coolant System remains acceptable for continued operation.
Immediately
Prior to increasing
pressurizer pressure
> 500 psig.
OR Prior to entering MODE 4.
Prior to increasing pressurizer pressure
> 500 psig.
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 specified on Table 3.4.1-1.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> RCS Chemistry TR 13.4.1 Farley Units 1 and 2 13.4.1 - 3 Version 8.0 Technical Requirements 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.
Pressurizer TR 13.4.2 Farley Units 1 and 2 13.4.2 - 1 Version 8.0 Technical Requirements 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-------------
All Required Actions must be completed whenever this Condition is entered. ----------------------------------
Pressurizer temperature not within limits.
A.1 Restore pressurizer temperature to within limits.
AND A.2 Perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural
integrity of the pressurizer.
AND A.3 Determine that the pressurizer remains acceptable for continued operation.
30 minutes
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Pressurizer TR 13.4.2 Farley Units 1 and 2 13.4.2 - 2 Version 29.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met.
B.1 Plant management to determine an alternate course of action that continues to assure the safe operation of the plant.
OR B.2.1 Be in MODE 3.
AND B.2.2 Reduce pressurizer pressure to < 500 psig.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 limits.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TRS 13.4.2.2 ---------------------------------NOTE-------------------------------- Only required to be performed during auxiliary spray operation.
Verify the spray water temperature differential is within
limit.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Reactor Vessel Head Vents TR 13.4.3 Farley Units 1 and 2 13.4.3 - 1 Version 29.0 Technical Requirements 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 Auxilia ry 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 vent system paths nonfunctional.
A.1 Initiate action to maintain the nonfunctional vent paths 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 path to FUNCTIONAL status.
Immediately
30 days B. Required Action and associated Completion Time not met.
B.1 Initiate a Condition Report.
AND B.2 Continue action to restore the required vent path(s) to FUNCTIONAL status.
Immediately
Immediately
Reactor Vessel Head Vents TR 13.4.3 Farley Units 1 and 2 13.4.3 - 2 Version 12.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.4.3.1 Verify each valve in the vent system operates through one complete cycle of full travel from the control room
during MODE 5 or 6.
18 months TRS 13.4.3.2 Verify flow through the reactor vessel head vent systems by venting during MODE 5 or 6.
18 months
Safety Valves - Shutdown TR 13.4.4
Farley Units 1 and 2 13.4.4 - 1 Version 24.0 Technical Requirements 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 safety valve nonfunctional.
A.1 Suspend all operations involving positive reactivity changes AND A.2 Initiate action to place an FUNCTIONAL RHR loop into operation in the shutdown
cooling mode.
Immediately
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.4.4.1 Verify requirements of the Inservice Testing Plan are met for the required pressurizer code safety valve.
In Accordance with the Inservice Testing Program
RCS Pressure Isolation Valve (PIV) Leakage TR 13.4.5 Farley Units 1 and 2 13.4.5 - 1 Version 8.0 Technical Requirements 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 pressure isolation valves (PIVs) with leakage in
excess of limit following maintenance, repair or replacement work on the
valve affecting the seating capability of the valve.
A.1 Restore leakage to within limit.
Prior to returning
valve to service
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.4.5.1 Verify PIV leakage within limits of Table 13.4.5-1 following maintenance, repair or replacement work on the valve affecting the seating capability of the valve.
Prior to returning valve to service
RCS Pressure Isolation Valve (PIV) Leakage TR 13.4.5 Farley Units 1 and 2 13.4.5 - 2 Version 8.0 Technical Requirements Table 13.4.5-1 Reactor Coolant System Pressure Isolation Valves Valve Number Description Maximum Allowable Leakage Q1/2E11V001A Q1/2E11V001B Q1/2E11V016A Q1/2E11V016B Q1/2E11V021A Q1/2E11V021B Q1/2E11V021C Q1/2E21V032A Q1/2E21V032B Q1/2E21V032C Q1/2E21V037A Q1/2E21V037B Q1/2E21V037C Q1/2E11V042A Q1/2E11V042B Q1/2E21V076A Q1/2E21V076B Q1/2E21V077A Q1/2E21V077B Q1/2E21V077C 12" Gate 12" Gate 12" Gate 12" Gate 6" Check 6" Check 6" Check 12" Check
12" Check
12" Check 12" Check 12" Check
12" Check
10" Check
10" Check 6" Check 6" Check 6" Check 6" Check 6" Check 5.000 gpm
5.000 gpm
5.000 gpm
5.000 gpm
3.000 gpm 3.000 gpm 3.000 gpm
5.000 gpm
5.000 gpm
5.000 gpm 5.000 gpm 5.000 gpm
5.000 gpm
5.000 gpm
5.000 gpm
3.000 gpm 3.000 gpm 3.000 gpm
3.000 gpm
3.000 gpm Note: See TS 3.4.14 for applicable Actions and Surveillance Requirements
ECCS TR 13.5.1 Farley Units 1 and 2 13.5.1 - 1 Version 8.0 Technical Requirements 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 subsystems inoperable.
A.1 Refer to Technical Specification 3.5.2 or 3.5.3, as applicable, and associated Required Actions.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.5.1.1 Perform a visual inspection of accessible areas of containment (or those areas affected by a containment entry during MODES 1-4) to verify that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
Once prior to entry into MODE 4 from MODE 5 AND Thereafter at the completion of each containment entry.
ECCS TR 13.5.1 Farley Units 1 and 2 13.5.1 - 2Version 32.0 Technical RequirementsTECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.5.1.2 Verify correct position of each mechanical position stop for the following ECCS throttle valves: CVC-V-8991 A/B/C CVC-V-8989 A/B/C CVC-V-8996 A/B/C CVC-V-8994 A/B/C Once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE. TRS 13.5.1.3 Verify that the mechanical stops are intact for the following low head safety injection valves: RHR-HV-603 A/B Prior to entry into MODE 3 from MODE 4. TRS 13.5.1.4 Perform a flow balance test, during shutdown, and verify the following flow rates:
a) For HHSI System - single pump that provides the greatest flow: 193 gpm for each cold leg injection line, and 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: 3911 gpm (total injection) Once following completion of modifications to the ECCS subsystem(s) that alter the subsystem(s) flow characteristics.
ECCS TR 13.5.1 Farley Units 1 and 2 13.5.1 - 3 Version 17.0 Technical Requirements Table 13.5.1-1 Minimum Allowable HHSI Pump Performance PUMP FLOW (gpm) PUMP HEAD (ft) 0 5420 125 5320 225 5220 260 5120 305 4920 390 4420 460 3920 520 3420 580 2920 635 2420 700 1770 Containment Ventilation System Leakage Rate TR 13.6.1 Farley Units 1 and 2 13.6.1 - 1 Version 8.0 Technical Requirements 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 valve degradation (for the
containment purge supply and exhaust penetrations) based on comparison of the leakage rate for each
containment purge supply
and exhaust penetration
to the previously measured leakage rate.
A.1 Perform an engineering evaluation to determine what corrective action, if any, is necessary.
Prior to entering
MODE 4 following
the next entry into MODE 5 if the existing leakage is
determined during testing per Technical Specification SR
3.6.3.5 OR Prior to entering MODE 4 if excess leakage is determined during
MODE 5 per SR
Containment Ventilation System Leakage Rate TR 13.6.1 Farley Units 1 and 2 13.6.1 - 2 Version 28.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.6.1.1 Compare the leakage rate for each containment purge supply and exhaust penetration to the previously measured leakage rate (for the containment purge supply and exhaust penetrations) to detect excess valve degradation.
Prior to entering MODE 4 from
MODE 5 if not
performed in the
previous 92 days
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 and the 8-inch containment purge supply and exhaust
isolation valves.
9 Years
Containment Isolation Valves TR 13.6.2 Farley Units 1 and 2 13.6.2 - 1 Version 8.0 Technical Requirements 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 isolation valve(s) with isolation times exceeding the limit.
A.1 Restore the isolation time of the valve(s) to within the
limit.
Prior to returning the valve(s) to service
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 affected valve(s) is within the limit(s) listed in Table 13.6.2-1.
Prior to returning the valve(s) to service
Containment Isolation Valves TR 13.6.2 (continued)
Farley Units 1 and 2 13.6.2 - 2 Version 23.0 Technical Requirements Table 13.6.2-1 (Page 1 of 3)
Containment Isolation Valves Valve Number
Function Isolation Time (sec)
A. Phase "A" Isolation
- 1. CVC-HV-8871 2. CVC-HV-8961
- 3. CVC-HV-8880
- 4. RC-HV-8047
- 5. RC-HV-8033
- 6. RC-HV-8028 7. LWP-LCV-1003 8. LWP-HV-7136
- 9. CBV-MOV-3318A 10. CBV-MOV-3318B 11. CVC-HV-8152
- 12. CVC-HV-8149A 13. CVC-HV-8149B 14. CVC-HV-8149C
- 15. CVC-MOV-8100
- 16. CVC-MOV-8112 17. SS-HV-3104
- 18. SS-HV-3331 19. SS-HV-3103 20. SS-HV-3332
- 21. SS-HV-3765 22. SS-HV-3333 23. CBV-HV-3657
- 24. CBV-MOV-3660 25. CBV-HV-3658 26. CBV-HV-3198A
- 27. CBV-HV-3198D 28. LWP-HV-3376 29. LWP-HV-3377
- 30. CCW-HV-3095
- 31. CCW-HV-3443 Accum. Test Line to RWST Iso. Valve
Accum. Test Line to RWST Iso. Valve N2 Supply to Isolation Accum. Pressurizer Relief Tank N2 Supply Pressurizer Relief Tank N2 Supply Reactor Makeup Water to PRT Iso. Valve Reactor Coolant Drain Tank LCV RCDT Pumps Discharge Line Iso.
CTMT Differential Press. Iso. Valve CTMT Differential Press. Iso. Valve Letdown Line CTMT Iso. Valve Letdown Orifice Isolation Valve 45 gpm Letdown Orifice Isolation Valve 60 gpm Letdown Orifice Isolation Valve 60 gpm RCP Seal Water Return Iso. Valve RCP Seal Water Return Iso. Valve Pressurizer Steam Sample Iso. Valve Pressurizer Steam Sample Iso. Valve Pressurizer Liquid Sample Iso. Valve Pressurizer Liquid Sample Iso. Valve Reactor Loops 2 and 3 Sample Iso. Valve Reactor Loops 2 and 3 Sample Iso. Valve Containment Air Sample Iso. Valve Containment Air Sample Iso. Valve Containment Air Sample Iso. Valve Containment Purge Exhaust Iso. Valve Containment Purge Supply Iso. Valve Containment Sump Discharge Valve Containment Sump Discharge Valve CCW to Excess Letdown/RCDT HXs. CCW from Excess Letdown/RCDT HXs 10 10 10 10 10 10 10 10 15 15 10 10 10 10 10 (a) 15 10 10 10 10 10 10 10 15 10 5 5 10 10 10 10 (a) In accordance with MDC 1090703801, Unit 1 CVC-MOV-8100 isolation time has been changed to 15 s.
Containment Isolation Valves TR 13.6.2 Farley Units 1 and 2 13.6.2 - 3 Version 16.0 Technical Requirements Table 13.6.2-1 (Page 2 of 3)
Containment Isolation Valves Valve Number
Function Isolation Time (sec)
A. Phase "A" Isolation (continued)
- 32. CCW-HV-3067 33. CVC-HV-8860
- 34. SS-HV-3766 35. SS-HV-3334 36. LWP-HV-7126
- 37. LWP-HV-7150 38. LWP-HV-3380 39. CTS-HV-3659
- 40. CBV-HV-3196 41. CBV-HV-3197 42. CBV-HV-2867C
- 43. CBV-HV-2867D 44. CBV-HV-2866C 45. CBV-HV-2866D CCW from Exc. Letdown / RCDT HXs Accum. Fill Line Isolation
Accum. Tanks Sample Iso. Valve Accum. Tanks Sample Iso. Valve RCDT Vent Line Iso. Valve RCDT Vent Line Iso. Valve CTMT Sump Recirculation Valve Demin. Water to Reactor HD Storage CTMT Purge Exhaust Iso. Valve CTMT Purge Supply Iso. Valve CTMT Mini-Purge Exhaust Iso. Valve CTMT Mini-Purge Exhaust Iso. Valve CTMT Mini-Purge Supply Iso. Valve CTMT Mini-Purge Supply Iso. Valve 10 10 10 10 10 10 10 10 5 5 5 5 5 5 B. Phase "B" Isolation
- 1. CCW-MOV-3052
- 2. CCW-MOV-3046
- 3. CCW-MOV-3182
- 4. CCW-HV-3184
CCW from RCP Oil Coolers CCW from RCP Thermal Barrier CCW from RCP Thermal Barrier CTMT Instrument Air Supply Valve
< 15 < 36 for Unit 1
< 15 for Unit 2
< 15 < 10
< 10 < 10 7. IA-HV-2228 Pressurizer PORV Backup Air/N2 Supply Valve < 10 C. Safety Injection Signal
- 1. CVC-MOV-8107
- 2. CVC-MOV-8108
- 3. SW-MOV-3135 4. SW-MOV-3131 5. SW-MOV-3134 Charging Pumps to Regenerative HX
Charging Pumps to Regenerative HX SW to RCP Motor Air Coolers SW From RCP Motor Air Coolers SW From RCP Motor Air Coolers
< 10
< 10
< 36 < 36 < 36 (continued)
Containment Isolation Valves TR 13.6.2 Farley Units 1 and 2 13.6.2 - 4 Version 12.0 Technical Requirements Table 13.6.2-1 (Page 3 of 3)
Containment Isolation Valves Valve Number
Function Isolation Time (sec)
D. Manual
- 1. Q1/2G31V012 2. Q1/2G21V005
- 3. RHR-MOV-8701A 4. RHR-MOV-8702A 5. Q1/2P18V001
- 6. Q1/2P18V002 7. CBV-MOV-3238 8. CBV-MOV-3239
- 9. RHR-MOV-8811A 10. RHR-MOV-8811B 11. RHR-MOV-8812A
- 12. RHR-MOV-8812B 13. CS-MOV-8826A 14. CS-MOV-8826B
- 15. CS-MOV-8827A 16. CS-MOV-8827B 17. Q1/2B13V026B
- 18. CBV-MOV-3528A 19. CBV-MOV-3528B 20. CBV-MOV-3528C
- 21. CBV-MOV-3528D 22. CBV-MOV-3739A 23. CBV-MOV-3739B
- 24. CBV-MOV-3745A 25. CBV-MOV-3745B 26. CBV-MOV-3835A
- 27. CBV-MOV-3835B 28. CBV-MOV-3740 29. CBV-MOV-3530
- 30. Q2P18V004 31. Q2P18V005 Refueling Cavity Supply Reactor Coolant Drain Tank Reactor Coolant LP C to RHR Pump A Reactor Coolant LP A to RHR Pump B Service Air
Service Air CTMT Leak Rate Test Valve CTMT Leak Rate Test Valve CTMT Sump to RHR Pump A CTMT Sump to RHR Pump B CTMT Sump to RHR Pump A CTMT Sump to RHR Pump B CS Pump A CTMT Sump Suction Iso. CS Pump B CTMT Sump Suction Iso.
CS Pump A CTMT Sump Suction Iso. CS Pump B CTMT Sump Suction Iso. Pressurizer Pressure Generator CTMT Post-LOCA Sampling Valve 1 CTMT Post-LOCA Sampling Valve 2 CTMT Post-LOCA Sampling Valve 3 CTMT Post-LOCA Sampling Valve 4 CTMT Post-LOCA Sampling Iso. Valve CTMT Post-LOCA Sampling Iso. Valve CTMT Post-LOCA Sampling Rtn. Valve CTMT Post-LOCA Sampling Rtn. Valve CTMT Post-LOCA Sampling Rtn. Valve CTMT Post-LOCA Sampling Rtn. Valve CTMT Post-LOCA Vent Iso. Valve CTMT Post-LOCA Vent Iso. Valve
Breathing Air (Service Air) (Unit 2 Only)
Breathing Air (Service Air) (Unit 2 Only) N/A N/A < 120 < 120 N/A N/A N/A N/A < 17 < 17 < 17
< 17 < 17 < 17
< 17 < 17 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 32. Q1/2P19V1099 HV2228 Bypass Manual Isolation Valve N/A Steam Generator Pressure/Temperature Limitation TR 13.7.1 Farley Units 1 and 2 13.7.1 - 1 Version 8.0 Technical Requirements 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------------- All Required Actions must be completed whenever this Condition is entered. ----------------------------------
SG temperatures not within limits.
A.1 Reduce the SG pressure of the applicable side to 200 psig.
AND A.2 Perform an engineering evaluation to determine the effect of the over-pressurization on the structural integrity of the SG.
AND A.3 Determine that the SG remains acceptable for continued operation.
30 minutes
Prior to increasing the SG coolant temperatures
> 200 °F
Prior to increasing the SG coolant temperatures
> 200 °F Steam Generator Pressure/Temperature Limitation TR 13.7.1 Farley Units 1 and 2 13.7.1 - 2 Version 8.0 Technical Requirements 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Snubbers TR 13.7.2 Farley Units 1 and 2 13.7.2 - 1 Version 29.0 Technical Requirements 13.7 Plant Systems
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 snubbers removed from supported system.
OR One or more required snubbers inoperable while in place.
A.1 Refer to the requirements of Technical Specification LCO 3.0.8. Immediately
B. One or more required snubbers nonfunctional.
B.1 Perform an engineering evaluation on the supported
component in accordance with ASME OM Code, 2001 Edition through 2003 Addenda, Subarticle ISTD-1800.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. Required Action and associated Completion
Time of Condition B not met.
C.1 Declare supported system nonfunctional or inoperable as appropriate.
Immediately Snubbers TR 13.7.2 Farley Units 1 and 2 13.7.2 - 2 Version 24.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES
NOTE--------------------------------------------------------
Each snubber shall be demonstrated FUNCTIONAL by performance of an inservice examination and testing inspection program in accordance with the ASME OM Code, 2001 Edition with Addenda through 2003, Subsection ISTD and ASME Code Case OMN-13, Revision 0 and 10 CFR 50.55a(b)(3)(v), dated October 1, 2004. -----------------------------------------------------------------------------------------------------------------------------
SURVEILLANCE FREQUENCY
TRS 13.7.2.1 Perform visual examinations of each snubber in accordance with ASME OM Code, Article ISTD-4000 and 10 CFR 50.55a(b)(3)(v). Preservice Examinations shall be in accordance with ASME OM Code, Subarticle ISTD-4100.
Inservice Examinations shall be in accordance with ASME OM Code, Subarticle ISTD-4200.
In accordance with ASME OM Code
Table ISTD-4542-1 and ASME OM Code Case OMN-13 as applicable.
TRS 13.7.2.2 Perform a functional test on a representative sample of snubbers in accordance with ASME OM Code, Article ISTD-5000.
Preservice Examinations s hall be in accordance with ASME OM Code, Subarticle ISTD-5100.
Inservice Examinations shall be in accordance with ASME OM Code, Subarticle ISTD-5200.
Each fuel Cycle
TRS 13.7.2.3 Snubber service life will be monitored in accordance with ASME OM Code, Article ISTD-6000.
Each fuel Cycle
Snubbers TR 13.7.2 Farley Units 1 and 2 13.7.2 - 3 Version 19.0 Technical Requirements Table 13.7.2-1 Visual Examinations
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 VT-3 visual examination method described in the ASME Section XI Code, 2001 Edition through 2003 Addenda, paragraph IWA-2213 (see 10 CFR 50.55a(b)(3)(v).
Snubbers TR 13.7.2 Farley Units 1 and 2 13.7.2 - 4 Version 19.0 Technical Requirements 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, Article ISTD-5000. The tests may be done either in place or in a test bench. One of the sampling plans described in Subarticle ISTD-5300 shall be used to select the snubbers to be tested.
Sealed Source Contamination TR 13.7.3 Farley Units 1 and 2 13.7.3 - 1 Version 8.0 Technical Requirements 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 contamination not within limit. A.1 Remove sealed source from use. AND A.2.1 Decontaminate and repair the sealed source OR A.2.2 Dispose of sealed source in accordance with Commission regulations.
Immediately
Prior to returning the sealed source to use
In accordance with Commission
regulations
Sealed Source Contamination TR 13.7.3 Farley Units 1 and 2 13.7.3 - 2 Version 8.0 Technical Requirements 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 sealed source.
6 months 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 each sealed source and fission detector.
Within 6 months prior to use or transfer to another licensee.
Sealed Source Contamination TR 13.7.3 Farley Units 1 and 2 13.7.3 - 3 Version 8.0 Technical Requirements 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 each sealed startup source and fission detector.
Within 31 days prior to being subjected to
core flux or being installed in the core.
AND Following repair or
maintenance to the source.
The Ultimate Heat Sink (UHS) Support Structures TR 13.7.4 Farley Units 1 and 2 13.7.4 - 1 Version 8.0 Technical Requirements 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 Heat Sink (UHS) support structures in degraded condition.
A.1 Initiate action to return support structure to compliance with related maintenance requirements.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.7.4.1 Verify the spillway channel and adjacent areas are free of erosion damage.
After each storm that 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
< 15 cfs. 5 years
Area Temperature Monitoring (Unit 2 Only)
TR 13.7.5 Farley Unit 2 13.7.5 - 1 Version 29.0 Technical Requirements 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 within limits for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
A.1 Declare the equipment in the area nonfunctional or inoperable and apply the appropriate Required Action(s) for the nonfunctional/inoperable equipment.
AND 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.
Immediately
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.7.5.1 Verify the temperature in each of the areas in Table 13.7.5-1 is within limits.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Area Temperature Monitoring (Unit 2 Only)
TR 13.7.5 Farley Unit 2 13.7.5 - 2 Version 8.0 Technical Requirements 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 Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)
TR 13.8.1
Farley Unit 2 13.8.1 - 1 Version 24.0 Technical Requirements 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 containment penetration conductor overcurrent
protective device(s) nonfunctional.
A.1.1 Restore the protective device(s) to FUNCTIONAL status.
OR A.1.2 Deenergize the circuit(s).
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. One or more containment penetration circuit(s),
which are required to be deenergized, energized.
B.1 Deenergize the circuit(s).
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)
TR 13.8.1
Farley Unit 2 13.8.1 - 2 Version 29.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time not met.
C.1 Initiate a Condition Report.
AND C.2 Continue action to restore the required protective device(s) to FUNCTIONAL status or deenergize the circuits which are required to be deenergized.
Immediately
Immediately 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 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.
18 months Containment Penetration Conductor Overcurrent Protective Devices (Unit 2 Only)
TR 13.8.1
Farley Unit 2 13.8.1 - 3 Version 24.0 Technical Requirements 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 10% of each type of lower voltage circuit breakers.
18 months TRS 13.8.1.3 Inspect and perform preventive maintenance on each circuit breaker in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
60 months TRS 13.8.1.4 Verify power sources feeding circuits required to be deenergized are interrupted by an open breaker or removed fuse.
31 days Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)
TR 13.8.2 Farley Unit 2 13.8.2 - 1 Version 24.0 Technical Requirements 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 nonfunctional thermal overload protection device(s).
A.1 Declare the affected valve(s) inoperable and enter the
appropriate Technical Specification Condition and follow the applicable
Required Actions for the
affected valve(s).
Immediately
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 6 years. -------------------------------------------------------------------------
Verify the required thermal overload protection devices FUNCTIONAL by performance of a CHANNEL CALIBRATION of a representative sample of at least 25% of all thermal overload devices.
18 months
Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)
TR 13.8.2 Farley Unit 2 13.8.2 - 2 Version 8.0 Technical Requirements 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)
Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)
TR 13.8.2 Farley Unit 2 13.8.2 - 3 Version 8.0 Technical Requirements 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)
Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)
TR 13.8.2 Farley Unit 2 13.8.2 - 4 Version 8.0 Technical Requirements 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)
Motor Operated Valves Thermal Overload Protection Devices (Unit 2 Only)
TR 13.8.2 Farley Unit 2 13.8.2 - 5 Version 8.0 Technical Requirements 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.
Emergency Diesel Generators (EDGs) Maintenance and Inspection Requirements TR 13.8.3 Farley Units 1 and 2 13.8.3 - 1 Version 30.0 Technical Requirements 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 maintenance or inspection requirements not met.
A.1 Initiate action to restore compliance with maintenance and inspection requirements.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.8.3.1 Verify that the following EDG lockout features prevent the EDG's 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) 18 months
TRS 13.8.3.2 Verify that the permanently connected and auto-connected loads to each EDG do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generators and
3100 kw for the 2850 kw generator.
18 months on a STAGGERED TEST BASIS
Decay Time TR 13.9.1 Farley Units 1 and 2 13.9.1 - 1 Version 8.0 Technical Requirements 13.9 Refueling Operations
TR 13.9.1 Decay Time
TR 13.9.1 The Reactor shall be subcritical for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
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
< 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
A.1 Suspend all operations involving movement of irradiated fuel in the reactor pressure vessel.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.1.1 Verify the reactor has been subcritical for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by confirming the date and time of subcriticality.
Prior to movement of irradiated fuel in the
Communications TR 13.9.2 Farley Units 1 and 2 13.9.2 - 1 Version 8.0 Technical Requirements 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 between control room and refueling station not
maintained.
A.1 Suspend all CORE ALTERATIONS.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.2.1 Verify direct communication exists between control room and refueling station.
Once within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to start of CORE ALTERATIONS
AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter
during CORE ALTERATIONS
Manipulator Crane TR 13.9.3
Farley Units 1 and 2 13.9.3 - 1 Version 24.0 Technical Requirements 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 nonfunctional.
A.1 Suspend use of manipulator crane from operations involving the movement of fuel assemblies within the reactor pressure vessel.
Immediately
Manipulator Crane TR 13.9.3
Farley Units 1 and 2 13.9.3 - 2 Version 24.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Auxiliary hoist nonfunctional.
B.1 Suspend use of auxiliary hoist from operations involving the movement of control rods within the reactor pressure vessel.
Immediately TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.9.3.1 Verify manipulator crane FUNCTIONALITY by:
- a. Performing a load test of 3250 pounds, and
- b. Demonstrating operation of the automatic load cutoff when the crane load exceeds 2850 pounds. Once within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the
start of movement of fuel assemblies within the reactor pressure vessel TRS 13.9.3.2 Verify auxiliary hoist and associated load indicator FUNCTIONAL by performance of a load test 700 pounds.
Once within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of movement of drive rods within the
Crane Travel - Spent Fuel Storage Building TR 13.9.4
Farley Units 1 and 2 13.9.4 - 1 Version 8.0 Technical Requirements 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 not met.
A.1 Place the crane load in a safe condition.
Immediately
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
Spent Fuel Cask Crane TR 13.9.5 Farley Units 1 and 2 13.9.5 - 1 Version 24.0 Technical Requirements 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 less than the cold proof
test temperature.
A.1 --------------------------------------TR 13.0.3 is not applicable --------------------------------------
Derate the crane 1-1/2% of rated load for each degree F the ambient temperature is below the proof test
temperature.
Immediately
B. Lifting components not meeting any of the criteria
of TRS 13.9.5.2.
B.1 Suspend lifting of loads with the main hoist until the degraded components are repaired or replaced.
Immediately
Spent Fuel Cask Crane TR 13.9.5 Farley Units 1 and 2 13.9.5 - 2 Version 8.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY
TRS 13.9.5.1 Perform a cold proof test at 125% of rated load pursuant to ANSI-B.30.2.0.
40 months
TRS 13.9.5.2 Perform testing and inspection of the lifting components pursuant to ANSI-B.30.2.0 and the manufacturers recommendations.
40 months
Storage Pool Ventilation (fuel storage)
TR 13.9.6 Farley Units 1 and 2 13.9.6 - 1 Version 24.0 Technical Requirements 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. 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 the spent fuel pool room.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to storage of fuel in the spent fuel pool AND 7 days thereafter while fuel is stored in the storage pool
Storage Pool Ventilation (fuel storage)
TR 13.9.6 Farley Units 1 and 2 13.9.6 - 2 Version 8.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.6.2 Initiate, from the control room, flow through the HEPA 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.
31 days on a STAGGERED TEST BASIS
TRS 13.9.6.3 Perform required penetration room filtration system filter testing in accordance with the Ventilation Filter Testing
Program (VFTP).
In accordance with
the VFTP TRS 13.9.6.4 Verify that the normal spent fuel pool ventilation system 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.
18 months Average Reactor Coolant Temperature TR 13.9.7 Farley Units 1 and 2 13.9.7 - 1 Version 8.0 Technical Requirements 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 temperature
> 140 °F.
A.1 Initiate action to restore average reactor coolant
temperature to within limit.
Immediately
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.9.7.1 Verify average reactor coolant temperature 140 °F. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
Waste Gas Monitoring Instrumentation TR 13.12.1 Farley Units 1 and 2 13.12.1 - 1 Version 24.0 Technical Requirements 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------------Not applicable during
testing of oxygen monitors. ----------------------------------
One oxygen monitor for
one or more recombiners nonfunctional.
A.1 Isolate the oxygen supply to the affected recombiner(s).
Immediately
B. Both oxygen monitors for one or more recombiners nonfunctional.
B.1 Analyze grab samples from the affected on-service waste decay tank during addition of waste gas.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
(continued)
Waste Gas Monitoring Instrumentation TR 13.12.1 Farley Units 1 and 2 13.12.1 - 2 Version 24.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
B.2 Verify oxygen concentration remains less than 1 percent.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Required hydrogen monitor for one or more recombiners nonfunctional.
C.1 Analyze grab samples from the affected on-service waste decay tank during addition of waste gas.
AND C.2 Verify oxygen concentration remains less than 1 percent.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. Required Actions and associated Completion Times of Conditions A, B or C not met.
D.1 Suspend addition of waste gas to the system.
Immediately
E. Any oxygen or hydrogen monitor(s) for one or more recombiners nonfunctional for more than 30 days.
E.1 Prepare and submit a report to the Commission to explain
why this nonfunctionality was not corrected in a timely manner.
30 days Waste Gas Monitoring Instrumentation TR 13.12.1 Farley Units 1 and 2 13.12.1 - 3 Version 8.0 Technical Requirements 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 manufacturer's recommendations.
- 3. For the oxygen monitors, the CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's 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 Liquid Holdup Tanks TR 13.12.2 Farley Units 1 and 2 13.12.2 - 1 Version 13.0 Technical Requirements 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 material in any outside temporary tank, excluding liners being used to solidify radioactive wastes, in excess of limit.
A.1 Suspend addition of radioactive material to the tank.
AND A.2 Reduce the tank contents to within limit.
Immediately
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.2.1 Verify quantity of radioactive material contained in each outdoor temporary tank, excluding liners being used to solidify radioactive wastes, to be less than the limit by analyzing a representative sample of the tank contents.
7 days when
radioactive materials are being added to a tank.
Waste Gas Monitoring TR 13.12.3 Farley Units 1 and 2 13.12.3 - 1 Version 24.0 Technical Requirements 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 FUNCTIONAL.
A.1 Reduce oxygen concentration to 2% by volume. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> AND Concentration of oxygen in the gaseous radwaste treatment system
> 2% by volume but 4% by volume.
Waste Gas Monitoring TR 13.12.3 Farley Units 1 and 2 13.12.3 - 2 Version 24.0 Technical Requirements ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Monitors in TR 13.12.1 not FUNCTIONAL.
AND Concentration of oxygen in
the gaseous radwaste treatment system
> 1% by volume but 4% by volume. B.1 Analyze grab samples from the affected on-service waste decay tank during addition of waste gas.
AND B.2 Reduce oxygen concentration to 1% by volume.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
C. Required Actions and associated Completion Times of Conditions A or B not met. C.1 Suspend addition of waste gas to the system.
Immediately D. Concentration of oxygen in the gaseous radwaste treatment system > 4% by volume. D.1 Suspend all additions of waste gases to the system.
AND D.2 Reduce oxygen concentration to 4%. AND D.3 Reduce oxygen concentration to within limit.
Immediately
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> Waste Gas Monitoring TR 13.12.3 Farley Units 1 and 2 13.12.3 - 3 Version 24.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.3.1 Verify concentration of hydrogen or oxygen in the gaseous radwaste treatment system to be less than the limit by monitoring the waste gases in the gaseous During addition of
waste gases to the 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Gas Storage Tanks TR 13.12.4 Farley Units 1 and 2 13.12.4 - 1 Version 13.0 Technical Requirements 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 material in any gas storage tank exceeding
limit. A.1 Suspend all additions of radioactive material to the tank.
AND A.2 Reduce the tank contents to within the limit.
Immediately
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.4.1 Verify quantity of radioactive material contained in each gas storage tank to be less than the limit.
Once per 7 days
when radioactive materials have been added to the tank during the previous
7 days.
Gas Storage Tanks TR 13.12.4 Farley Units 1 and 2 13.12.4 - 2 Version 8.0 Technical Requirements TECHNICAL REQUIREMENT SURVEILLANCES SURVEILLANCE FREQUENCY TRS 13.12.4.2 In the event of confirmed major fuel failure (> 1%), verify quantity of radioactive material contained in each waste gas storage tank to be less than the limit.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
when radioactive
materials have been added to the tank during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Technical Requirements Manual (TRM) Bases
Joseph M. Farley Nuclear Plant Units 1 and 2
Table of Contents Farley Units 1 and 2 i Version 7.0 Technical Requirements Bases 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)
Table of Contents Farley Units 1 and 2 ii Version 8.0 Technical Requirements Bases 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
TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES Farley Units 1 and 2 B 13.0-1 Version 9.0 Technical Requirements 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)
TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES Farley Units 1 and 2 B 13.0-2 Version 13.0 Technical Requirements 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)
TR Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT (TR) Applicability BASES Farley Units 1 and 2 B 13.0-3 Version 13.0 Technical Requirements 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)
TR Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-4 Version 13.0 Technical Requirements 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)
TR Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-5 Version 9.0 Technical Requirements Bases documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing ri sk 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 Appl icability 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)
TR Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-6 Version 9.0 Technical Requirements 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)
TR Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-7 Version 13.0 Technical Requirements 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 FUNCTIONALI TY. 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.
TRS Applicability B 13.0 B 13.0 TECHNICAL REQUIREMENT S URVEILLANCES (TRS) Applicability BASES Farley Units 1 and 2 B 13.0-8 Version 9.0 Technical Requirements 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)
TRS Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-9 Version 9.0 Technical Requirements 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.
TRS Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-10 Version 9.0 Technical Requirements 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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)
TRS Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-11 Version 9.0 Technical Requirements 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)
TRS Applicability B 13.0 BASES Farley Units 1 and 2 B 13.0-12 Version 4.0 Technical Requirements 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 TR's 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.
Reactivity Control Systems B 13.1 B 13.1 REACTIVITY CONTROL SYSTEMS BASES Farley Units 1 and 2 B 13.1-1 Version 9.0 Technical Requirements 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)
Reactivity Control Systems B 13.1 BASES Farley Units 1 and 2 B 13.1-2 Version 9.0 Technical Requirements 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 7.5 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 Requirem ents Manual (TRM) refers to TS equipment, it remains appropriate to refer to these SSCs as e i ther operable or inoperable
.)
Reactivity Control Systems B 13.1 BASES Farley Units 1 and 2 B 13.1-3 Version 9.0 Technical Requirements 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.
Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES Farley Units 1 and 2 B 13.3-1 Version 13.0 Technical Requirements 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.
Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES Farley Units 1 and 2 B 13.3-2 Version 13.0 Technical Requirements Bases TR 13.3.5 Electric Hydrogen Recombiner Instrumentation and Control Circuits The FUNCTIONALITY of the equipment and system s 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.
Instrumentation B 13.3 B 13.3 INSTRUMENTATION BASES Farley Units 1 and 2 B 13.3-3 Version 13.0 Technical Requirements 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.
Reactor Coolant System B 13.4 B 13.4 REACTOR COOLANT SYSTEM BASES Farley Units 1 and 2 B 13.4-1 Version 3.0 Technical Requirements 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit for performance of engineering evaluation was established based on engineering judgment, to allow an adequate time for performance while ensuring promptness.
Emergency Core Cooling Systems B 13.5 B 13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
BASES Farley Units 1 and 2 B 13.5-1 Version 9.0 Technical Requirements Bases TR 13.5.1 Emergency Core Cooling System (ECCS)
As per TR 13.0.5, the te rm " operable" should b e used for Structur e s, Systems, and Components (SSCs) that are explicitly required to be operab l e by the Technical Sp ecifications (T S s) as w ell a s 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 o p e rability) for SSCs that are required to b e operable by the TSs. The definition of operability assumes that an SSC described in TSs can perform its specified function when all necessary supp ort systems are capable of pe rfor ming their related support functions. Since the ECCS is a SSC t hat is explicitly required to be o p erable 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 considerati on. 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.
Containment Systems B 13.6 B 13.6 CONTAINMENT SYSTEMS BASES Farley Units 1 and 2 B 13.6-1 Version 9.0 Technical Requirements 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 isolat ion 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.
Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES Farley Units 1 and 2 B 13.7-1 Version 9.0 Technical Requirements 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 ma intaining 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)
Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES Farley Units 1 and 2 B 13.7-2 Version 6.0 Technical Requirements 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.
Plant Systems B 13.7 B 13.7 PLANT SYSTEMS BASES Farley Units 1 and 2 B 13.7-3 Version 9.0 Technical Requirements 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit for performance of engineering evaluation was established based on engineering judgment, to allow an adequate time for performance while ensuring promptness.
Electrical Power Systems B 13.8 B 13.8 ELECTRICAL POWER SYSTEMS BASES (continued)
Farley Units 1 and 2 B 13.8-1 Version 9.0 Technical Requirements 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 per iodic 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 Electrical Power Systems B 13.8 B 13.8 ELECTRICAL POWER SYSTEMS BASES Farley Units 1 and 2 B 13.8-2 Version 11.0 Technical Requirements 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.
Refueling Operations B 13.9 B 13.9 REFUELING OPERATIONS BASES Farley Units 1 and 2 B 13.9-1 Version 9.0 Technical Requirements 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 is consistent with the assumptions used in the accident analyses.
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)
Refueling Operations B 13.9 BASES Farley Units 1 and 2 B 13.9- 2 Version 9.0 Technical Requirements 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 will be performed to demonstrate FUNCTIONALITY. It is permissible to operate the crane at temperatures less than the temperature at which it was proof tested, provided these operations take place at derated loads as stated in the action statement.
TR 13.9.6 Storage Pool Ventilation (Fuel Storage)
The limitations on the storage pool ventilation syst em ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. 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.
EGSTRAM Program B 13.12 B 13.12 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING (EGSTRAM) PROGRAM
BASES Farley Units 1 and 2 B 13.12-1 Version 9.0 Technical Requirements 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".
Emergency Response Facilities B 13.13.1 BASES Farley Units 1 and 2 B 13.13.1-3 Version 8.0 Technical Requirements 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.
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:
Emergency Response Facilities B 13.13.1 BASES Farley Units 1 and 2 B 13.13.1-4 Version 12.0 Technical Requirements 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 F iltration 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.