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NUREG-1430, Vol. 1, Rev. 5, Standard Technical Specifications Babcock and Wilcox Plants: Specifications
	ML21272A363
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Issue date:	09/30/2021
From:	Michelle Honcharik; Office of Nuclear Reactor Regulation
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NUREG-1430 Volume 1 Revision 5.0 Standard Technical Specifications Babcock and Wilcox Plants Revision 5.0 Volume 1, Specifications Office of Nuclear Reactor Regulation

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NUREG-1430 Volume 1 Revision 5.0 Standard Technical Specifications Babcock and Wilcox Plants Revision 5.0 Volume 1, Specifications Manuscript Completed: March 2021 Date Published: September 2021 Office of Nuclear Reactor Regulation

ABSTRACT This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B&W) plants. The changes reflected in Revision 5 result from the experience gained from plant operation using the improved STS and extensive public technical meetings and discussions among the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees and the Nuclear Steam Supply System (NSSS) Owners Groups.

The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.36) (60 FR 36953). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the practical extent, to Revision 5 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

Users may access the STS NUREGs in the PDF format at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/. Users may print or download copies from the NRC Web site.

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PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.

Babcock & Wilcox STS iii Rev. 5.0

TABLE OF CONTENTS Page ABSTRACT .......................................................................................................... iii 1.0 USE AND APPLICATION .................................................................................... 1.1-1 1.1 Definitions....................................................................................................... 1.1-1 1.2 Logical Connectors......................................................................................... 1.2-1 1.3 Completion Times .......................................................................................... 1.3-1 1.4 Frequency ...................................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs) ......................................................................................... 2.0-1 2.1 SLs ............................................................................................................ 2.0-1 2.2 Safety Limit Violations .................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS ................................................................... 3.1.1-1 3.1.1 SHUTDOWN MARGIN (SDM) ....................................................................... 3.1.1-1 3.1.2 Reactivity Balance .......................................................................................... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) .................................................... 3.1.3-1 3.1.4 CONTROL ROD Group Alignment Limits ...................................................... 3.1.4-1 3.1.5 Safety Rod Insertion Limits ............................................................................ 3.1.5-1 3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits ............................ 3.1.6-1 3.1.7 Position Indicator Channels............................................................................ 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 1 ....................................................... 3.1.8-1 3.1.9 PHYSICS TESTS Exceptions - MODE 2 ....................................................... 3.1.9-1 3.2 POWER DISTRIBUTION LIMITS ......................................................................... 3.2.1-1 3.2.1 Regulating Rod Insertion Limits ..................................................................... 3.2.1-1 3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits .............................. 3.2.2-1 3.2.3 AXIAL POWER IMBALANCE Operating Limits .............................................. 3.2.3-1 3.2.4 QUADRANT POWER TILT (QPT) ................................................................. 3.2.4-1 3.2.5 Power Peaking Factors .................................................................................. 3.2.5-1 3.3 INSTRUMENTATION Reactor Protection System (RPS) Instrumentation .......... 3.3.1-1 3.3.1 Reactor Protection System (RPS) Instrumentation ........................................ 3.3.1-1 3.3.2 Reactor Protection System (RPS) Manual Reactor Trip ................................ 3.3.2-1 3.3.3 Reactor Protection System (RPS) - Reactor Trip Module (RTM) ................... 3.3.3-1 3.3.4 CONTROL ROD Drive (CRD) Trip Devices ................................................... 3.3.4-1 3.3.5 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ......................................................................................... 3.3.5-1 3.3.6 Engineered Safety Feature Actuation System (ESFAS) Manual Initiation .................................................................................................... 3.3.6-1 3.3.7 Engineered Safety Feature Actuation System (ESFAS) Automatic Actuation Logic ......................................................................................... 3.3.7-1 3.3.8 Emergency Diesel Generator (EDG) Loss of Power Start (LOPS) ................ 3.3.8-1 3.3.9 Source Range Neutron Flux ........................................................................... 3.3.9-1 3.3.10 Intermediate Range Neutron Flux .................................................................. 3.3.10-1 3.3.11 Emergency Feedwater Initiation and Control (EFIC) System Instrumentation ......................................................................................... 3.3.11-1 3.3.12 Emergency Feedwater Initiation and Control (EFIC) Manual Initiation .................................................................................................... 3.3.12-1 Babcock & Wilcox STS v Rev. 5.0

TABLE OF CONTENTS Page 3.3 INSTRUMENTATION (continued) 3.3.13 Emergency Feedwater Initiation and Control (EFIC) Logic ............................ 3.3.13-1 3.3.14 Emergency Feedwater Initiation and Control (EFIC) - Emergency Feedwater (EFW) - Vector Valve Logic .................................................... 3.3.14-1 3.3.15 Reactor Building (RB) Purge Isolation - High Radiation ................................. 3.3.15-1 3.3.16 Control Room Isolation - High Radiation ........................................................ 3.3.16-1 3.3.17 Post Accident Monitoring (PAM) Instrumentation ........................................... 3.3.17-1 3.3.18 Remote Shutdown System ............................................................................. 3.3.18-1 3.4 REACTOR COOLANT SYSTEM (RCS) .............................................................. 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................................................. 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality ...................................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ................................................ 3.4.3-1 3.4.4 RCS Loops - MODES 1 and 2........................................................................ 3.4.4-1 3.4.5 RCS Loops - MODE 3 .................................................................................... 3.4.5-1 3.4.6 RCS Loops - MODE 4 .................................................................................... 3.4.6-1 3.4.7 RCS Loops - MODE 5, Loops Filled............................................................... 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled ........................................................ 3.4.8-1 3.4.9 Pressurizer ..................................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves .............................................................................. 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valve (PORV) ........................................ 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ......................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE .......................................................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................................ 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ....................................................... 3.4.15-1 3.4.16 RCS Specific Activity ...................................................................................... 3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity ............................................................ 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ......................................... 3.5.1-1 3.5.1 Core Flood Tanks (CFTs)............................................................................... 3.5.1-1 3.5.2 ECCS - Operating .......................................................................................... 3.5.2-1 3.5.3 ECCS - Shutdown .......................................................................................... 3.5.3-1 3.5.4 Borated Water Storage Tank (BWST) ............................................................ 3.5.4-1 3.6 CONTAINMENT SYSTEMS ................................................................................. 3.6.1-1 3.6.1 Containment ................................................................................................... 3.6.1-1 3.6.2 Containment Air Locks ................................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ......................................................................... 3.6.3-1 3.6.4 Containment Pressure.................................................................................... 3.6.4-1 3.6.5 Containment Air Temperature ........................................................................ 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ...................................................... 3.6.6-1 3.6.7 Spray Additive System ................................................................................... 3.6.7-1 3.6.8 Containment Sump......................................................................................... 3.6.8-1 3.7 PLANT SYSTEMS ............................................................................................... 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) .............................................................. 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ............................................................ 3.7.2-1 3.7.3 [Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs), and Associated Startup Feedwater Control Valves (SFCVs) ] ...................................................................................... 3.7.3-1 Babcock & Wilcox STS vi Rev. 5.0

TABLE OF CONTENTS Page 3.7 PLANT SYSTEMS (continued) 3.7.4 Atmospheric Vent Valves (AVVs) ................................................................... 3.7.4-1 3.7.5 Emergency Feedwater (EFW) System ........................................................... 3.7.5-1 3.7.6 Condensate Storage Tank (CST) ................................................................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System .................................................... 3.7.7-1 3.7.8 Service Water System (SWS) ........................................................................ 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)............................................................................... 3.7.9-1 3.7.10 Control Room Emergency Ventilation System (CREVS) ............................... 3.7.10-1 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) .............................................................................................. 3.7.11-1 3.7.12 Emergency Ventilation System (EVS) ............................................................ 3.7.12-1 3.7.13 Fuel Storage Pool Ventilation System (FSPVS) ............................................. 3.7.13-1 3.7.14 Fuel Storage Pool Water Level ...................................................................... 3.7.14-1 3.7.15 [Spent Fuel Pool Boron Concentration ........................................................... 3.7.15-1 ]

3.7.16 [Spent Fuel Pool Storage ............................................................................... 3.7.16-1 ]

3.7.17 Secondary Specific Activity ............................................................................ 3.7.17-1 3.7.18 Steam Generator Level .................................................................................. 3.7.18-1 3.8 ELECTRICAL POWER SYSTEMS ...................................................................... 3.8.1-1 3.8.1 AC Sources - Operating ................................................................................. 3.8.1-1 3.8.2 AC Sources - Shutdown ................................................................................. 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ...................................................... 3.8.3-1 3.8.4 DC Sources - Operating ................................................................................. 3.8.4-1 3.8.5 DC Sources - Shutdown ................................................................................. 3.8.5-1 3.8.6 Battery Parameters ........................................................................................ 3.8.6-1 3.8.7 Inverters - Operating ...................................................................................... 3.8.7-1 3.8.8 Inverters - Shutdown ...................................................................................... 3.8.8-1 3.8.9 Distribution Systems - Operating.................................................................... 3.8.9-1 3.8.10 Distribution Systems - Shutdown ................................................................... 3.8.10-1 3.9 REFUELING OPERATIONS ................................................................................ 3.9.1-1 3.9.1 Boron Concentration ...................................................................................... 3.9.1-1 3.9.2 Nuclear Instrumentation ................................................................................. 3.9.2-1 3.9.3 Containment Penetrations .............................................................................. 3.9.3-1 3.9.4 Decay Heat Removal (DHR) and Coolant Circulation - High Water Level ......................................................................................................... 3.9.4-1 3.9.5 Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level ......................................................................................................... 3.9.5-1 3.9.6 Refueling Canal Water Level.......................................................................... 3.9.6-1 4.0 DESIGN FEATURES ........................................................................................... 4.0-1 4.1 Site Location................................................................................................... 4.0-1 4.2 Reactor Core .................................................................................................. 4.0-1 4.3 Fuel Storage ................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS .......................................................................... 5.1-1 5.1 Responsibility ................................................................................................. 5.1-1 5.2 Organization ................................................................................................... 5.2-1 5.3 Unit Staff Qualifications .................................................................................. 5.3-1 5.4 Procedures .................................................................................................... 5.4-1 Babcock & Wilcox STS vii Rev. 5.0

TABLE OF CONTENTS Page 5.0 ADMINISTRATIVE CONTROLS (continued) 5.5 Programs and Manuals ................................................................................. 5.5-1 5.6 Reporting Requirements ............................................................................... 5.6-1 5.7 High Radiation Area ....................................................................................... 5.7-1 Babcock & Wilcox STS viii Rev. 5.0

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ALLOWABLE THERMAL ALLOWABLE THERMAL POWER shall be the maximum POWER reactor core heat transfer rate to the reactor coolant permitted by consideration of the number and configuration of reactor coolant pumps (RCPs) in operation.

AXIAL POWER IMBALANCE AXIAL POWER IMBALANCE shall be the power in the top half of the core, expressed as a percentage of RATED THERMAL POWER (RTP), minus the power in the bottom half of the core, expressed as a percentage of RTP.

AXIAL POWER SHAPING APSRs shall be control components used to control the axial RODS (APSRs) power distribution of the reactor core. The APSRs are positioned manually by the operator and are not trippable.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps[, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step].

Babcock & Wilcox STS 1.1-1 Rev. 5.0

Definitions 1.1 1.1 Definitions CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The ESFAS CHANNEL FUNCTIONAL TEST shall also include testing of ESFAS safety related bypass functions for each channel affected by bypass operation. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total steps[, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step].

CONTROL RODS CONTROL RODS shall be all full length safety and regulating rods that are used to shut down the reactor and control power level during maneuvering operations.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present.

The determination of DOSE EQUIVALENT I-131 shall be performed using

Reviewers Note -------------------------------

The first set of thyroid dose conversion factors shall be used for plants licensed to 10 CFR 100.11. The following Committed Dose Equivalent (CDE) or Committed Effective Dose Equivalent (CEDE) conversion factors shall be used for plants licensed to 10 CFR 50.67.

Babcock & Wilcox STS 1.1-2 Rev. 5.0

Definitions 1.1 1.1 Definitions DOSE EQUIVALENT I-131 (continued)

[thyroid dose conversion factors from:

a. Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or

b. Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977, or

c. ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity," or

d. Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

OR Committed Dose Equivalent (CDE) or Committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11.]

DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides [Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138] actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using [effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average gamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations" or similar source].

Babcock & Wilcox STS 1.1-3 Rev. 5.0

Definitions 1.1 1.1 Definitions EMERGENCY FEEDWATER The EFIC RESPONSE TIME shall be that time interval from INITIATION AND CONTROL when the monitored parameter exceeds its EFIC actuation (EFIC) RESPONSE TIME setpoint at the channel sensor until the emergency feedwater equipment is capable of performing its function (i.e., valves travel to their required positions, pumps discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except RCP seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);

Babcock & Wilcox STS 1.1-4 Rev. 5.0

Definitions 1.1 1.1 Definitions LEAKAGE (continued)

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE; and

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a fault in an RCS component body, pipe wall, or vessel wall. LEAKAGE past seals, packing, and gaskets is not pressure boundary LEAKAGE.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

NUCLEAR HEAT FLUX HOT FQ(Z) shall be the maximum local linear power density in the CHANNEL FACTOR FQ(Z) core divided by the core average fuel rod linear power density, assuming nominal fuel pellet and fuel rod dimensions.

NUCLEAR ENTHALPY RISE FNH shall be the ratio of the integral of linear power along the HOT CHANNEL FACTOR FNH fuel rod on which minimum departure from nucleate boiling ratio occurs, to the average fuel rod power.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

Babcock & Wilcox STS 1.1-5 Rev. 5.0

Definitions 1.1 1.1 Definitions PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.4.

QUADRANT POWER TILT QPT shall be defined by the following equation and is expressed as a percentage of the Power in any Core Quadrant (Pquad) to the Average Power of all Quadrants (Pavg).

QPT = 100 [ (Pquad / Pavg) - 1 ]

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of [2544] MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE when the monitored parameter exceeds its RPS trip setpoint at TIME the channel sensor until electrical power is interrupted at the control rod drive trip breakers. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full length CONTROL RODS (safety and regulating) are fully inserted except for the single CONTROL ROD of highest reactivity worth, which is assumed to be fully withdrawn. However, with all CONTROL RODS verified fully inserted by two independent means, it is not necessary to account for a stuck CONTROL ROD in the SDM calculation. With any CONTROL ROD not capable of being fully inserted, the reactivity worth of these CONTROL RODS must be accounted for in the determination of SDM,

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the [nominal zero power design level],

and

c. There is no change in APSR position.

Babcock & Wilcox STS 1.1-6 Rev. 5.0

Definitions 1.1 1.1 Definitions

[ STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function. ]

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

Babcock & Wilcox STS 1.1-7 Rev. 5.0

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES REACTIVITY % RATED AVERAGE MODE TITLE CONDITION THERMAL REACTOR COOLANT (keff) POWER(a) TEMPERATURE (F) 1 Power Operation 0.99 >5 NA 2 Startup 0.99 5 NA 3 Hot Standby < 0.99 NA [330]

4 Hot Shutdown(b) < 0.99 NA [330] > Tavg > [200]

5 Cold Shutdown(b) < 0.99 NA [200]

6 Refueling(c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

Babcock & Wilcox STS 1.1-8 Rev. 5.0

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

Babcock & Wilcox STS 1.2-1 Rev. 5.0

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify . . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Babcock & Wilcox STS 1.2-2 Rev. 5.0

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Babcock & Wilcox STS 1.2-3 Rev. 5.0

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO.

Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered. The "otherwise specified" exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. The exceptions may also be incorporated into the Completion Time. For example, LCO 3.8.1, "AC Sources - Operating," Required Action B.2, requires declaring required feature(s) supported by an inoperable diesel generator, inoperable when the redundant required feature(s) are inoperable. The Completion Time states, "4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)." In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied.

Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the Babcock & Wilcox STS 1.3-1 Rev. 5.0

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued) associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition, unless otherwise specified.

However, when a subsequent train, subsystem, component, or variable, expressed in the Condition, is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

Babcock & Wilcox STS 1.3-2 Rev. 5.0

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ."

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Babcock & Wilcox STS 1.3-3 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

Babcock & Wilcox STS 1.3-4 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X train to OPERABLE train status.

inoperable.

B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y train to OPERABLE train status.

inoperable.

C. One C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months One train to OPERABLE Function Y status.

train inoperable.

Babcock & Wilcox STS 1.3-5 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

Babcock & Wilcox STS 1.3-6 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3.. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

Babcock & Wilcox STS 1.3-7 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Babcock & Wilcox STS 1.3-8 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to 50% RTP.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

Babcock & Wilcox STS 1.3-9 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

inoperable. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

Babcock & Wilcox STS 1.3-10 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Reviewer's Note --------------------------------------

Example 1.3-8 is only applicable to plants that have adopted the Risk Informed Completion Time Program.

[ EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time may be applied as discussed in Example 1.3-2.

However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

Babcock & Wilcox STS 1.3-11 Rev. 5.0

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Condition A is exited, and therefore, the Required Actions of Condition B may be terminated. ]

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Babcock & Wilcox STS 1.3-12 Rev. 5.0

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0.2, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be preformed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

Babcock & Wilcox STS 1.4-1 Rev. 5.0

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

a. The Surveillance is not required to be met in the MODE or other specified condition to be entered; or

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or

c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

Babcock & Wilcox STS 1.4-2 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

Babcock & Wilcox STS 1.4-3 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by SR 3.0.2. "Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

Babcock & Wilcox STS 1.4-4 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP.

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches 25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (plus the extension allowed by SR 3.0.2) with power 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Babcock & Wilcox STS 1.4-5 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

Babcock & Wilcox STS 1.4-6 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1, 2 or 3 (the assumed Applicability of the associated LCO) between performances.

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Babcock & Wilcox STS 1.4-7 Rev. 5.0

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-[6] specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

Babcock & Wilcox STS 1.4-8 Rev. 5.0

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2, the maximum local fuel pin centerline temperature shall be [5080 - (6.5 x 10-3 MWD/MTU)F].

2.1.1.2 In MODES 1 and 2, the departure from nucleate boiling ratio shall be maintained greater than the limits of [1.3 for the BAW-2 correlation and 1.18 for the BWC correlation].

2.1.1.3 In MODES 1 and 2, Reactor Coolant System (RCS) core outlet temperature and pressure shall be maintained above and to the left of the SL shown in Figure 2.1.1-1.

2.1.2 Reactor Coolant System Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained [2750] psig.

2.2 SAFETY LIMIT VIOLATIONS With any SL violation, the following actions shall be completed:

2.2.1 In MODE 1 or 2, if SL 2.1.1.1 or SL 2.1.1.2 is violated, be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 In MODE 1 or 2, if SL 2.1.1.3 is violated, restore RCS pressure and temperature within limits and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.3 In MODE 1 or 2, if SL 2.1.2 is not met, restore compliance within limits and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.4 In MODES 3, 4, and 5, if SL 2.1.2 is not met, restore RCS pressure to

[2750] psig within 5 minutes.

Babcock & Wilcox STS 2.0-1 Rev. 5.0

SLs 2.0 Babcock & Wilcox STS 2.0-2 Rev. 5.0

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, LCO 3.0.8, and LCO 3.0.9.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO 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.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ,

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

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

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

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate (exceptions to this Specification are stated in the individual Specifications); or Babcock & Wilcox STS 3.0-1 Rev. 5.0

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

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

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

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

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.14, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCOs [3.1.9, 3.1.10, 3.1.11, and 3.4.19] allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met.

When a Test Exception LCO 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 Specifications.

Babcock & Wilcox STS 3.0-2 Rev. 5.0

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:

a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or

b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

LCO 3.0.9 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.

If the required OPERABLE train or subsystem becomes inoperable while this specification is in use, it must be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the provisions of this specification cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s).

At the end of the specified period, the required barriers must be able to perform their related support function(s) or the supported system LCO(s) shall be declared not met.

Babcock & Wilcox STS 3.0-3 Rev. 5.0

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.

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 LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

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

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

If a Completion Time requires periodic performance on a "once per . . ."

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. The delay period is only applicable when there is a reasonable expectation the Surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

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

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO 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 LCO 3.0.4.

Babcock & Wilcox STS 3.0-4 Rev. 5.0

SR Applicability 3.0 3.0 SR Applicability SR 3.0.4 (continued)

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.

Babcock & Wilcox STS 3.0-5 Rev. 5.0

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 The SDM shall be within the limits specified in the COLR.

APPLICABILITY: MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits. A.1 Initiate boration to restore 15 minutes SDM to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is within the limits specified in the [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.1-1 Rev. 5.0

Reactivity Balance 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Balance LCO 3.1.2 The measured core reactivity balance shall be within +/- 1% k/k of predicted values.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity A.1 Re-evaluate core design 7 days balance not within limit. and safety analysis and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Babcock & Wilcox STS 3.1.2-1 Rev. 5.0

Reactivity Balance 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ------------------------------NOTES-----------------------------

1. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading.

2. This Surveillance is not required to be performed prior to entry into MODE 2.

Verify measured core reactivity balance is within Prior to entering

+/- 1% k/k of predicted values. MODE 1 after each fuel loading AND

NOTE--------

Only required after 60 EFPD

[ 31 EFPD thereafter OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.2-2 Rev. 5.0

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The maximum positive limit shall be [ [ ] k/k/F at RTP].

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within limits. A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within the upper limit specified in the Prior to entering COLR. MODE 1 after each fuel loading SR 3.1.3.2 -------------------------------NOTE------------------------------

If the MTC is more negative than the COLR limit when extrapolated to the end of cycle, SR 3.1.3.2 may be repeated. Shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit.

Verify extrapolated MTC is within the lower limit Each fuel cycle specified in the COLR. within 7 EFPDs after reaching an equilibrium boron concentration equivalent to 300 ppm Babcock & Wilcox STS 3.1.3-1 Rev. 5.0

CONTROL ROD Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 CONTROL ROD Group Alignment Limits LCO 3.1.4 Each CONTROL ROD shall be OPERABLE.

AND Each CONTROL ROD shall be aligned to within [6.5]% of its group average height.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CONTROL ROD A.1 Restore CONTROL ROD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not aligned to within alignment.

[6.5]% of its group average height. OR A.2.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits specified in the COLR. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter OR A.2.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to 60% of the ALLOWABLE THERMAL POWER.

AND Babcock & Wilcox STS 3.1.4-1 Rev. 5.0

CONTROL ROD Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.3 Reduce the nuclear 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months overpower trip setpoint to 70% of the ALLOWABLE THERMAL POWER.

AND A.2.4 Verify the potential ejected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rod worth is within the assumptions of the rod ejection analysis.

AND A.2.5 --------------NOTE---------------

Only required when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not met.

C. More than one C.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CONTROL ROD not limits specified in the aligned within [6.5]% of COLR.

its group average height.

OR C.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND C.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Babcock & Wilcox STS 3.1.4-2 Rev. 5.0

CONTROL ROD Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more rods D.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. limits specified in the COLR.

OR D.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND D.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual CONTROL ROD positions are [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within [6.5]% of their group average height.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.1.4.2 Verify CONTROL ROD freedom of movement [ 92 days (trippability) by moving each individual CONTROL ROD that is not fully inserted 3% in any direction. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.4-3 Rev. 5.0

CONTROL ROD Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.3 -------------------------------NOTE------------------------------

With rod drop times determined with less than four reactor coolant pumps operating, operation may proceed provided operation is restricted to the pump combination operating during the rod drop time determination.

Verify the rod drop time for each CONTROL ROD, Prior to reactor from the fully withdrawn position, is [1.66] seconds criticality after from power interruption at the CONTROL ROD drive each removal of breakers to 3/4 insertion (25% withdrawn position) the reactor vessel with Tavg 525F. head Babcock & Wilcox STS 3.1.4-4 Rev. 5.0

Safety Rod Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Safety Rod Insertion Limits LCO 3.1.5 Each safety rod shall be fully withdrawn.

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

Not required for any safety rod inserted to perform SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One safety rod not fully A.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months withdrawn. limits specified in the COLR.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Declare the rod inoperable. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. More than one safety B.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod not fully withdrawn. limits specified in the COLR.

OR B.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND Babcock & Wilcox STS 3.1.5-1 Rev. 5.0

Safety Rod Insertion Limits 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each safety rod is fully withdrawn. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.5-2 Rev. 5.0

APSR Alignment Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 AXIAL POWER SHAPING ROD (APSR) Alignment Limits LCO 3.1.6 Each APSR shall be OPERABLE and aligned within [6.5]% of its group average height.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One APSR inoperable, A.1 Perform SR 3.2.3.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not aligned within its limits, or both. AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each APSR movement B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify position of each APSR is within [6.5]% of the [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months group average height.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.6-1 Rev. 5.0

Position Indicator Channels 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Position Indicator Channels LCO 3.1.7 The absolute position indicator channel and the relative position indicator channel for each CONTROL ROD and APSR shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each inoperable position indicator channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. The relative position A.1 Determine the absolute 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator channel position indicator channel inoperable for one or for the rod(s) is AND more rods. OPERABLE.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter B. The absolute position B.1.1 Determine position of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months indicator channel rods with inoperable inoperable for one or absolute position indicator more rods. by actuating the affected rod's zone position reference indicators.

AND Babcock & Wilcox STS 3.1.7-1 Rev. 5.0

Position Indicator Channels 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 Determine rods with 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable position indicators are maintained at AND the zone reference indicator position and within the Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months limits specified in thereafter LCO 3.1.5, "Safety Rod Insertion Limit," LCO 3.2.1, "Regulating Rod Insertion Limits," or LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits," as applicable.

OR B.2.1 Place the control groups 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with nonindicating rods under manual control.

AND Babcock & Wilcox STS 3.1.7-2 Rev. 5.0

Position Indicator Channels 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.2 Determine the position of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the nonindicating rods indirectly with fixed incore AND instrumentation.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND

NOTE----------

Not applicable during first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after motion of nonindicating rods, which exceeds

[15 inches] in one direction since the last determination of the rod's position C. The absolute position C.1 Declare the rod(s) Immediately indicator channel and inoperable.

the relative position indicator channel inoperable for one or more rods.

OR Required Action and associated Completion Time not met.

Babcock & Wilcox STS 3.1.7-3 Rev. 5.0

Position Indicator Channels 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify the absolute position indicator channels and [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the relative position indicator channels agree within the limit specified in the COLR. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.7-4 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 1 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 1 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of:

LCO 3.1.4, "CONTROL ROD Alignment Limits,"

LCO 3.1.5, "Safety Rod Insertion Limits,"

LCO 3.1.6, "AXIAL POWER SHAPING ROD Alignment Limits,"

LCO 3.2.1, "Regulating Rod Insertion Limits," for the restricted operation region only, LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits," and LCO 3.2.4, "QUADRANT POWER TILT,"

may be suspended, provided:

a. THERMAL POWER is maintained 85% RTP,

b. Nuclear overpower trip setpoint is 10% RTP higher than the THERMAL POWER at which the test is performed, with a maximum setting of 90% RTP,

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

c. Only required when THERMAL POWER is > 20% RTP.

FQ(Z) and FNH are maintained within the limits specified in the COLR and

d. SDM is within the limits specified in the COLR.

APPLICABILITY: MODE 1 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceptions.

Babcock & Wilcox STS 3.1.8-1 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 1 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. THERMAL POWER B.1 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

> 85% RTP. exceptions.

OR Nuclear overpower trip setpoint > 10% higher than PHYSICS TESTS power level.

OR Nuclear overpower trip setpoint > 90% RTP.

OR

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

Only required when THERMAL POWER is

> 20% RTP.

FQ(Z) or FNH not within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify THERMAL POWER is 85% RTP. [ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.8-2 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 1 3.1.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.8.2 -------------------------------NOTE------------------------------

Only required to be met when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. [ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.1.8.3 Verify nuclear overpower trip setpoint is 10% RTP [ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months higher than the THERMAL POWER at which the test is performed, with a maximum setting of OR 90% RTP.

In accordance with the Surveillance Frequency Control Program ]

SR 3.1.8.4 Verify SDM is within the limits specified in the [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.8-3 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.9 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.3, "Moderator Temperature Coefficient,"

LCO 3.1.4, "CONTROL ROD Group Alignment Limits,"

LCO 3.1.5, "Safety Rod Insertion Limits,"

LCO 3.1.6, "AXIAL POWER SHAPING ROD Alignment Limits,"

LCO 3.2.1, "Regulating Rod Insertion Limits," for the restricted operation region only, and

[ LCO 3.4.2, "RCS Minimum Temperature for Criticality" ]

may be suspended provided that:

a. THERMAL POWER is 5% RTP,

b. Reactor trip setpoints on the OPERABLE nuclear overpower channels are set to 25% RTP,

c. Nuclear instrumentation high startup rate CONTROL ROD withdrawal inhibit is OPERABLE, and

d. SDM is within the limits specified in the COLR.

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER not A.1 Open control rod drive trip Immediately within limit. breakers.

B. SDM not within limit. B.1 Initiate boration to restore 15 minutes SDM to within limit.

AND B.2 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceptions.

Babcock & Wilcox STS 3.1.9-1 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Nuclear overpower trip C.1 Suspend PHYSICS TESTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months setpoint is not within exceptions.

limit.

OR Nuclear instrumentation high startup rate CONTROL ROD withdrawal inhibit inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify THERMAL POWER is 5% RTP. [ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.1.9.2 Verify nuclear overpower trip setpoint is 25% RTP. [ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.9-2 Rev. 5.0

PHYSICS TESTS Exceptions - MODE 2 3.1.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.9.3 Verify SDM is within the limits specified in the [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.1.9-3 Rev. 5.0

Regulating Rod Insertion Limits 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Regulating Rod Insertion Limits LCO 3.2.1 Regulating rod groups shall be within the physical insertion, sequence, and overlap limits specified in the COLR.

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

Not required for any regulating rod repositioned to perform SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Regulating rod groups A.1 --------------NOTE--------------

inserted in restricted Only required when operational region, or THERMAL POWER is sequence or overlap, or > 20% RTP.

any combination, not -------------------------------------

met.

Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.2 Restore regulating rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from groups to within limits. discovery of failure to meet the LCO B. Required Action and B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to less than or Time of Condition A not equal to THERMAL met. POWER allowed by regulating rod group insertion limits.

Babcock & Wilcox STS 3.2.1-1 Rev. 5.0

Regulating Rod Insertion Limits 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Regulating rod groups C.1 Initiate boration to restore 15 minutes inserted in unacceptable SDM to within the limit operational region. specified in the COLR.

AND C.2.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months groups to within restricted operating region.

OR C.2.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to less than or equal to the THERMAL POWER allowed by the regulating rod group insertion limits.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify regulating rod groups are within the sequence [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and overlap limits as specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.2.1-2 Rev. 5.0

Regulating Rod Insertion Limits 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 Verify regulating rod groups meet the insertion limits [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.2.1.3 Verify SDM is within the limit specified in the COLR. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality Babcock & Wilcox STS 3.2.1-3 Rev. 5.0

APSR Insertion Limits 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits LCO 3.2.2 APSRs shall be positioned within the limits specified in the COLR.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. APSRs not within limits. A.1 --------------NOTE--------------

Only required when THERMAL POWER is

> 20% RTP.

Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.2 Restore APSRs to within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Babcock & Wilcox STS 3.2.2-1 Rev. 5.0

APSR Insertion Limits 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify APSRs are within acceptable limits specified [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.2.2-2 Rev. 5.0

AXIAL POWER IMBALANCE Operating Limits 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL POWER IMBALANCE Operating Limits LCO 3.2.3 AXIAL POWER IMBALANCE shall be maintained within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 40% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AXIAL POWER A.1 Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months IMBALANCE not within limits. AND A.2 Reduce AXIAL POWER 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months IMBALANCE within limits.

B. Required Action and B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to 40% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AXIAL POWER IMBALANCE is within limits [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months as specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.2.3-1 Rev. 5.0

QPT 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT (QPT)

LCO 3.2.4 QPT shall be maintained less than or equal to the steady state limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > [20]% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPT greater than the A.1.1 Perform SR 3.2.5.1. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months steady state limit and less than or equal to the OR transient limit.

A.1.2.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER 2% RTP from the ALLOWABLE OR THERMAL POWER for each 1% of QPT greater 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after last than the steady state limit. performance of SR 3.5.2.1 AND A.1.2.2 Reduce nuclear overpower 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months trip setpoint and nuclear overpower based on Reactor Coolant System flow and AXIAL POWER IMBALANCE trip setpoint 2% RTP from the ALLOWABLE THERMAL POWER for each 1% of QPT greater than the steady state limit.

AND Babcock & Wilcox STS 3.2.4-1 Rev. 5.0

QPT 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 Restore QPT to less than or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from equal to the steady state discovery of failure to limit. meet the LCO B. QPT greater than the B.1 Reduce THERMAL 30 minutes transient limit and less POWER 2% RTP from than or equal to the ALLOWABLE THERMAL maximum limit due to POWER for each 1% of misalignment of a QPT greater than the CONTROL ROD or an steady state limit.

APSR.

AND B.2 Restore QPT to less than or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months equal to the transient limit.

C. Required Action and C.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to < 60% of the Time of Condition A or B ALLOWABLE THERMAL not met. POWER.

AND C.2 Reduce nuclear overpower 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months trip setpoint to 65.5% of the ALLOWABLE THERMAL POWER.

D. QPT greater than the D.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months transient limit and less POWER to < 60% of the than or equal to the ALLOWABLE THERMAL maximum limit due to POWER.

causes other than the misalignment of either AND CONTROL ROD or APSR. D.2 Reduce nuclear overpower 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months trip setpoint to 65.5% of the ALLOWABLE THERMAL POWER.

Babcock & Wilcox STS 3.2.4-2 Rev. 5.0

QPT 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion POWER to [20]% RTP.

Time for Condition C or D not met.

F. QPT greater than the F.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months maximum limit. POWER to [20]% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 Verify QPT is within limits as specified in the COLR. [ 7 days OR In accordance with the Surveillance Frequency Control Program ]

AND When QPT has been restored to less than or equal to the steady state limit, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for 12 consecutive hours, or until verified acceptable at 95% RTP Babcock & Wilcox STS 3.2.4-3 Rev. 5.0

Power Peaking Factors 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Power Peaking Factors LCO 3.2.5 FQ(Z) and FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. FQ(Z) not within limit. A.1 Reduce THERMAL 15 minutes POWER 1% RTP for each 1% that FQ(Z) exceeds limit.

AND A.2 Reduce nuclear overpower 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months trip setpoint and nuclear overpower based on Reactor Coolant System (RCS) flow and AXIAL POWER IMBALANCE trip setpoint 1% RTP for each 1% that FQ(Z) exceeds limit.

AND A.3 Restore FQ(Z) to within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit.

B. FNH not within limit. B.1 Reduce THERMAL 15 minutes POWER RH(%) RTP (specified in the COLR) for each 1% that FNH exceeds limit.

AND Babcock & Wilcox STS 3.2.5-1 Rev. 5.0

Power Peaking Factors 3.2.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Reduce nuclear overpower 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months trip setpoint and nuclear overpower based on RCS flow and AXIAL POWER IMBALANCE trip setpoint RH(%) RTP (specified in the COLR) for each 1% that FNH exceeds limit.

AND B.3 Restore FNH to within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Required Action and C.1 Be in MODE 1 with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion THERMAL POWER 20%

Time not met. RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 -------------------------------NOTE------------------------------

Only required to be performed when specified in LCO 3.1.8, "PHYSICS TESTS Exceptions -

MODE 1," or when complying with Required Actions of LCO 3.1.4, "CONTROL ROD Group Alignment Limits," LCO 3.2.1, "Regulating Rod Insertion Limits," LCO 3.2.2, "AXIAL POWER SHAPING ROD (APSR) Insertion Limits," LCO 3.2.3, "AXIAL POWER IMBALANCE Operating Limits," LCO 3.2.4, "QUADRANT POWER TILT (QPT)."

Verify FQ(Z) and FNH are within limits by using the As specified by Incore Detector System to obtain a power the applicable distribution map. LCO(s)

Babcock & Wilcox STS 3.2.5-2 Rev. 5.0

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1 Four channels of RPS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Place channel in bypass or 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. trip.

B. Two channels B.1 Place one channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

[OR In accordance with the Risk Informed Completion Time Program]

AND B.2 Place second channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months bypass.

C. Three or more channels C.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.1-1 for the Function.

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

Babcock & Wilcox STS 3.3.1-1 Rev. 5.0

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in AND Table 3.3.1-1.

D.2 Open all CONTROL ROD 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months drive (CRD) trip breakers.

E. As required by Required E.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.1-1.

F. As required by Required F.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and POWER < [45]% RTP.

referenced in Table 3.3.1-1.

G. As required by Required G.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and POWER < [15]% RTP.

referenced in Table 3.3.1-1.

Babcock & Wilcox STS 3.3.1-2 Rev. 5.0

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply to each RPS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.1.2 ------------------------------NOTES-----------------------------

1. Adjust power range channel output if the absolute difference is > [2]% RTP.

2. Not required to be performed until [24] hours after THERMAL POWER is 15% RTP.

Compare result of calorimetric heat balance [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculation to power range channel output.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.1-3 Rev. 5.0

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3 -----------------------------NOTES----------------------------

1. Adjust the power range channel imbalance output if the absolute value of the imbalance error is [2]% RTP.

2. Not required to be performed until [24] hours after THERMAL POWER is 15% RTP.

Compare results of out of core measured AXIAL [ 31 days POWER IMBALANCE (API0) to incore measured AXIAL POWER IMBALANCE (API1) as follows: OR (RTP/TP)(API0 - API1) = imbalance error. In accordance with the Surveillance Frequency Control Program ]

SR 3.3.1.4 Perform CHANNEL FUNCTIONAL TEST. [ [45] days on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.1-4 Rev. 5.0

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.5 ------------------------------NOTE-----------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.1.6 ------------------------------NOTE-----------------------------

Neutron detectors are excluded from RPS RESPONSE TIME testing.

Verify that RPS RESPONSE TIME is within limits. [ [18] months on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.1-5 Rev. 5.0

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION C.1 REQUIREMENTS VALUE

1. Nuclear Overpower -

a. High Setpoint 1,2(a),3(b) D SR 3.3.1.1 [104.9]% RTP SR 3.3.1.2 SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6

b. Low Setpoint 2(e),3(e) E SR 3.3.1.1 5% RTP SR 3.3.1.4(c)(d) 4(e),5(e) SR 3.3.1.5(c)(d)

SR 3.3.1.6

2. RCS High Outlet 1,2 D SR 3.3.1.1 [618]F Temperature SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

3. RCS High Pressure 1,2(a),3(b) D SR 3.3.1.1 [2355] psig SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6

4. RCS Low Pressure 1,2(a) D SR 3.3.1.1 [1800] psig SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

SR 3.3.1.6 (a) When not in shutdown bypass operation.

(b) With any CRD trip breaker in the closed position, the CRD System capable of rod withdrawal, and not in shutdown bypass operation.

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(e) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

Babcock & Wilcox STS 3.3.1-6 Rev. 5.0

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION C.1 REQUIREMENTS VALUE

5. RCS Variable Low Pressure 1,2(a) D SR 3.3.1.1 ([11.59]

Tout -

SR 3.3.1.4(c)(d) [5037.8]) psig SR 3.3.1.5(c)(d)

6. Reactor Building High 1,2,3(f) D SR 3.3.1.1 [4] psig Pressure SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

7. Reactor Coolant Pump to 1,2(a) D SR 3.3.1.1 [5]% RTP with 2 pumps Power SR 3.3.1.4(c)(d) operating SR 3.3.1.5(c)(d)

SR 3.3.1.6

8. Nuclear Overpower RCS 1,2(a) D SR 3.3.1.1 Nuclear Overpower RCS Flow and Measured AXIAL SR 3.3.1.3 Flow and AXIAL POWER POWER IMBALANCE SR 3.3.1.4(c)(d) IMBALANCE setpoint SR 3.3.1.5(c)(d) envelope in COLR SR 3.3.1.6

9. Main Turbine Trip (Control [45]% RTP F SR 3.3.1.1 [45] psig Oil Pressure) SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

(a) When not in shutdown bypass operation.

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(f) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

Babcock & Wilcox STS 3.3.1-7 Rev. 5.0

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION C.1 REQUIREMENTS VALUE

10. Loss of Main Feedwater [15]% RTP G SR 3.3.1.1 [55] psig Pumps (Control Oil SR 3.3.1.4(c)(d)

Pressure) SR 3.3.1.5(c)(d)

11. Shutdown Bypass RCS High 2(e),3(e),4(e) E SR 3.3.1.1 [1720] psig Pressure 5(e) SR 3.3.1.4(c)(d)

SR 3.3.1.5(c)(d)

(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures [Nominal Trip Setpoint] to confirm channel performance. The LTSP and the methodologies used to determine the as-found and as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

(e) During shutdown bypass operation with any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

Babcock & Wilcox STS 3.3.1-8 Rev. 5.0

RPS Manual Reactor Trip 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Protection System (RPS) Manual Reactor Trip LCO 3.3.2 The RPS Manual Reactor Trip Function shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Manual Reactor Trip A.1 Restore Function to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met in AND MODE 1, 2, or 3.

B.2 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. Required Action and C.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met in MODE 4 or 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL FUNCTIONAL TEST. Once prior to each reactor startup if not performed within the previous 7 days Babcock & Wilcox STS 3.3.2-1 Rev. 5.0

RPS - RTM 3.3.3 3.3 INSTRUMENTATION 3.3.3 Reactor Protection System (RPS) - Reactor Trip Module (RTM)

LCO 3.3.3 Four RTMs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RTM inoperable. A.1.1 Trip the associated CRD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months trip breaker.

OR A.1.2 Remove power from the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated CRD trip breaker.

AND A.2 Physically remove the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable RTM.

B. Two or more RTMs B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable in MODE 1, 2, or 3. AND OR B.2.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action and OR associated Completion Time not met in B.2.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months MODE 1, 2, or 3. CRD trip breakers.

Babcock & Wilcox STS 3.3.3-1 Rev. 5.0

RPS - RTM 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two or more RTMs C.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable in MODE 4 or 5. OR OR C.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CRD trip breakers.

Required Action and associated Completion Time not met in MODE 4 or 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL FUNCTIONAL TEST. [ [23] days on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.3-2 Rev. 5.0

CRD Trip Devices 3.3.4 3.3 INSTRUMENTATION 3.3.4 CONTROL ROD Drive (CRD) Trip Devices LCO 3.3.4 The following CRD trip devices shall be OPERABLE:

a. Two AC CRD trip breakers,

b. Two DC CRD trip breaker pairs, and

c. Eight electronic trip assembly (ETA) relays.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 when any CRD trip breaker is in the closed position and the CRD System is capable of rod withdrawal.

ACTIONS

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

Separate Condition entry is allowed for each CRD trip device.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CRD trip A.1 Trip the CRD trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months breaker(s) [or breaker breaker(s) pair] undervoltage or shunt trip Functions OR inoperable.

A.2 Remove power from the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months CRD trip breaker(s).

B. One or more CRD trip B.1 Trip the CRD trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months breaker(s) [or breaker breaker(s).

pair] inoperable for reasons other than those OR in Condition A.

B.2 Remove power from the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CRD trip breaker(s).

Babcock & Wilcox STS 3.3.4-1 Rev. 5.0

CRD Trip Devices 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more ETA relays C.1 Transfer affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. CONTROL ROD group to power supply with OPERABLE ETA relays.

OR C.2 Trip corresponding AC 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CRD trip breaker.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met in AND MODE 1, 2, or 3.

D.2.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR D.2.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CRD trip breakers.

E. Required Action and E.1 Open all CRD trip breakers. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met in MODE 4 OR or 5.

E.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CRD trip breakers.

Babcock & Wilcox STS 3.3.4-2 Rev. 5.0

CRD Trip Devices 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL FUNCTIONAL TEST. [ [23] days on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.4-3 Rev. 5.0

ESFAS Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Engineered Safety Feature Actuation System (ESFAS) Instrumentation)

LCO 3.3.5 Three channels of ESFAS instrumentation for each Parameter in Table 3.3.5-1 shall be OPERABLE in each ESFAS train.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

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

Separate Condition entry is allowed for each Parameter.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Parameters A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one channel inoperable. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more Parameters B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with two or more channels inoperable. AND OR Required Action and associated Completion Time not met.

Babcock & Wilcox STS 3.3.5-1 Rev. 5.0

ESFAS Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.1 --------------NOTE--------------

Only required for RCS Pressure - Low setpoint.

Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< [1800] psig.

AND B.2.2 --------------NOTE--------------

Only required for RCS Pressure - Low Low setpoint.

Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< [900] psig.

AND B.2.3 --------------NOTES-------------

1. Only required for Reactor Building Pressure High setpoint and High High setpoint.

2. LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.3.5-2 Rev. 5.0

ESFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.5-3 Rev. 5.0

ESFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.2 -------------------------------NOTES----------------------------

1. When an ESFAS channel is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , provided the remaining two channels of ESFAS instrumentation are OPERABLE or tripped.

2. If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

3. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

Perform CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.5-4 Rev. 5.0

ESFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.3 -------------------------------NOTES----------------------------

1. If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

2. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the LTSP at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The LTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference].

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.5-5 Rev. 5.0

ESFAS Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.4 Verify ESFAS RESPONSE TIME within limits. [ [18] months on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.5-6 Rev. 5.0

ESFAS Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED ALLOWABLE PARAMETER CONDITIONS VALUE

1. Reactor Coolant System Pressure - Low [1800] psig [1600] psig Setpoint (HPI Actuation, RB Isolation, RB Cooling, EDG Start)

2. Reactor Coolant System Pressure - Low Low [900] psig [400] psig Setpoint (HPI Actuation, LPI Actuation, RB Isolation, RB Cooling)

3. Reactor Building (RB) Pressure - High 1,2,3,4 [5] psig Setpoint (HPI Actuation, LPI Actuation, RB Isolation, RB Cooling)

4. Reactor Building Pressure - High High 1,2,3,4 [30] psig Setpoint (RB Spray Actuation)

Babcock & Wilcox STS 3.3.5-7 Rev. 5.0

ESFAS Manual Initiation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Engineered Safety Feature Actuation System (ESFAS) Manual Initiation LCO 3.3.6 Two manual initiation channels of each one of the ESFAS Functions below shall be OPERABLE:

a. High Pressure Injection,

b. Low Pressure Injection,

[ c. Reactor Building (RB) Cooling, ]

[ d. RB Spray, ]

e. RB Isolation, and

[ f. Control Room Isolation. ]

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when associated engineered safeguard equipment is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ESFAS A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Functions with one OPERABLE status.

channel inoperable. [OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.3.6-1 Rev. 5.0

ESFAS Manual Initiation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL FUNCTIONAL TEST. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.6-2 Rev. 5.0

ESFAS Automatic Actuation Logic 3.3.7 3.3 INSTRUMENTATION 3.3.7 Engineered Safety Feature Actuation System (ESFAS) Automatic Actuation Logic LCO 3.3.7 All the ESFAS automatic actuation logic matrices shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when associated engineered safeguard equipment is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each automatic actuation logic matrix.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more automatic A.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months actuation logic matrices component(s) in inoperable. engineered safeguard configuration.

OR A.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months component(s) inoperable.

Babcock & Wilcox STS 3.3.7-1 Rev. 5.0

ESFAS Automatic Actuation Logic 3.3.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform automatic actuation logic CHANNEL [ 31 days on a FUNCTIONAL TEST. STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.7-2 Rev. 5.0

EDG LOPS 3.3.8 3.3 INSTRUMENTATION 3.3.8 Emergency Diesel Generator (EDG) Loss of Power Start (LOPS)

LCO 3.3.8 Three channels of loss of voltage Function and three channels of degraded voltage Function EDG LOPS instrumentation per EDG shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, When associated EDG is required to be OPERABLE by LCO 3.8.2 "AC Sources - Shutdown."

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one channel per EDG inoperable. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more Functions B.1 Restore all but one channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with two or more to OPERABLE status.

channels per EDG [OR inoperable.

In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Required Time not met. Action for EDG made inoperable by EDG LOPS.

Babcock & Wilcox STS 3.3.8-1 Rev. 5.0

EDG LOPS 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.8.2 -------------------------------NOTE------------------------------

When EDG LOPS instrumentation is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed as follows: (a) up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for the degraded voltage Function, and (b) up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for the loss of voltage Function, provided the two channels monitoring the Function for the bus are OPERABLE or tripped.

Perform CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.8.3 Perform CHANNEL CALIBRATION with setpoint [ 18 months Allowable Value as follows:

OR

a. Degraded voltage [ ] and [ ] V with a time delay of [ ] seconds +/- [ ] seconds at [ ] V and In accordance with the

b. Loss of voltage [ ] and [ ] V with a time Surveillance delay of [ ] seconds +/- [ ] seconds at [ ] V. Frequency Control Program ]

Babcock & Wilcox STS 3.3.8-2 Rev. 5.0

Source Range Neutron Flux 3.3.9 3.3 INSTRUMENTATION 3.3.9 Source Range Neutron Flux LCO 3.3.9 Two source range neutron flux channels shall be OPERABLE.

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

High voltage to detector may be de-energized with neutron flux

> 1E-10 amp on intermediate range channels.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One source range A.1 Restore channel to Prior to increasing neutron flux channel OPERABLE status. neutron flux inoperable with neutron flux 1E-10 amp on the intermediate range neutron flux channels.

B. Two source range B.1 --------------NOTE--------------

neutron flux channels Plant temperature changes inoperable with neutron are allowed provided the flux 1E-10 amp on the temperature change is intermediate range accounted for in the neutron flux channels. calculated SDM.

Suspend operations Immediately involving positive reactivity changes.

AND B.2 Initiate action to insert all Immediately CONTROL RODS.

AND Babcock & Wilcox STS 3.3.9-1 Rev. 5.0

Source Range Neutron Flux 3.3.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.3 Open CONTROL ROD 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months drive trip breakers.

AND B.4 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits specified in the COLR. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter C. One or more source C.1 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months range neutron flux affected channel(s) to channel(s) inoperable OPERABLE status.

with neutron flux

> 1E-10 amp on the intermediate range neutron flux channels.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.9-2 Rev. 5.0

Source Range Neutron Flux 3.3.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.9.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.9-3 Rev. 5.0

Intermediate Range Neutron Flux 3.3.10 3.3 INSTRUMENTATION 3.3.10 Intermediate Range Neutron Flux LCO 3.3.10 Two intermediate range neutron flux channels shall be OPERABLE.

APPLICABILITY: MODE 2, MODES 3, 4, and 5 with any CONTROL ROD drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. A.1 Reduce neutron flux to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1E-10 amp.

B. Two channels B.1 --------------NOTE--------------

inoperable. Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity changes.

AND B.2 Open CRD trip breakers. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Babcock & Wilcox STS 3.3.10-1 Rev. 5.0

Intermediate Range Neutron Flux 3.3.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.10.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.10-2 Rev. 5.0

EFIC System Instrumentation 3.3.11 3.3 INSTRUMENTATION 3.3.11 Emergency Feedwater Initiation and Control (EFIC) System Instrumentation LCO 3.3.11 The EFIC System instrumentation channels for each Function in Table 3.3.11-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.11-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Emergency A.1 Place channel(s) in bypass 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Feedwater (EFW) or trip.

Initiation, Main Steam Line Isolation, or Main AND Feedwater (MFW)

Isolation Functions listed A.2 Place channel(s) in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in Table 3.3.11-1 with one channel inoperable. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more EFW B.1 Place one channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Initiation, Main Steam bypass.

Line Isolation, or MFW Isolation Functions listed AND in Table 3.3.11-1 with two channels inoperable.

Babcock & Wilcox STS 3.3.11-1 Rev. 5.0

EFIC System Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Place second channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months trip.

[OR In accordance with the Risk Informed Completion Time Program]

AND B.3 Restore one channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. One EFW Vector Valve C.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Control channel OPERABLE status.

inoperable. [OR In accordance with the Risk Informed Completion Time Program]

D. Three or more channels D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable for Functions 1.a or 1.b. AND OR D.2.1 --------------NOTE--------------

Only required for Required Action and Function 1a.

associated Completion -------------------------------------

Time not met for Functions 1.a or 1.b. Open CONTROL ROD 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months drive trip breakers.

AND Babcock & Wilcox STS 3.3.11-2 Rev. 5.0

EFIC System Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2.2 --------------NOTE--------------

Only required for Function 1b.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Three or more channels E.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable for POWER to 10% RTP.

Functions 1.d.

OR Required Action and associated Completion Time not met for Function 1.d.

F. Three or more channels F.1 Reduce once through 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable for steam generator pressure Functions 1.c, 2, 3, or 4. to < 750 psig.

OR Required Action and associated Completion Time not met for Functions 1.c, 2, 3, or 4.

Babcock & Wilcox STS 3.3.11-3 Rev. 5.0

EFIC System Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.11-1 to determine which SRs shall be performed for each EFIC Function.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.11.2 Perform CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.11.3 Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.11-4 Rev. 5.0

EFIC System Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.11.4 Verify EFIC RESPONSE TIME is within limits. [ [18] months on a STAGGERED TEST BASIS OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.11-5 Rev. 5.0

EFIC System Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 2)

Emergency Feedwater Initiation and Control System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. EFW Initiation

a. Loss of MFW Pumps 1,2(a),3(a) 4 SR 3.3.11.1 > [55] psig (Control Oil Pressure) SR 3.3.11.2 SR 3.3.11.3

b. SG Level - Low 1,2,3 4 per SG SR 3.3.11.1 [9] inches SR 3.3.11.2 SR 3.3.11.3 SR 3.3.11.4

c. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1 [600] psig SR 3.3.11.2 SR 3.3.11.3

d. RCP Status 10% RTP 4 SR 3.3.11.1 NA SR 3.3.11.2 SR 3.3.11.3

2. EFW Vector Valve Control

a. SG Pressure - Low 1,2,3(b) 4 per SG SR 3.3.11.1 [600] psig SR 3.3.11.2 SR 3.3.11.3

b. SG Differential 1,2,3(b) 4 SR 3.3.11.1 [125] psid Pressure - High SR 3.3.11.2 SR 3.3.11.3

c. [ SG Level - High 1,2,3(b) 4 SR 3.3.11.1 [ ] inches ]

SR 3.3.11.2 SR 3.3.11.3

3. Main Steam Line Isolation

a. SG Pressure - Low 1,2,3(b)(c) 4 per SG SR 3.3.11.1 [600] psig SR 3.3.11.2 SR 3.3.11.3 SR 3.3.11.4 (a) When not in shutdown bypass.

(b) When SG pressure 750 psig.

(c) Except when all associated valves are closed and [deactivated].

Babcock & Wilcox STS 3.3.11-6 Rev. 5.0

EFIC System Instrumentation 3.3.11 Table 3.3.11-1 (page 2 of 2)

Emergency Feedwater Initiation and Control System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

4. MFW Isolation

a. SG Pressure - Low 1,2,3(b)(d) 4 per SG SR 3.3.11.1 [600] psig SR 3.3.11.2 SR 3.3.11.3 SR 3.3.11.4 (b) When SG pressure 750 psig.

(d) Except when all [MFSVs], [MFCVs], [or associated SFCVs] are closed and [deactivated] [or isolated by a closed manual valve].

Babcock & Wilcox STS 3.3.11-7 Rev. 5.0

EFIC Manual Initiation 3.3.12 3.3 INSTRUMENTATION 3.3.12 Emergency Feedwater Initiation and Control (EFIC) Manual Initiation LCO 3.3.12 Two manual initiation switches per actuation channel for each of the following EFIC Functions shall be OPERABLE:

a. Steam generator (SG) A Main Feedwater (MFW) Isolation,

b. SG B MFW Isolation,

c. SG A Main Steam Line Isolation,

d. SG B Main Steam Line Isolation, and

e. Emergency Feedwater Actuation.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EFIC A.1 Place actuation channel for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function(s) with one or the associated EFIC both manual initiation Function(s) in trip. [OR switches inoperable in one actuation channel. In accordance with the Risk Informed Completion Time Program]

B. One or more EFIC B.1 Restore one actuation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function(s) with one or channel for the associated both manual initiation EFIC Function(s) to [OR switches inoperable in OPERABLE status.

both actuation channels. In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.3.12-1 Rev. 5.0

EFIC Manual Initiation 3.3.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.12.1 Perform CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.12-2 Rev. 5.0

EFIC Logic 3.3.13 3.3 INSTRUMENTATION 3.3.13 Emergency Feedwater Initiation and Control (EFIC) Logic LCO 3.3.13 Channels A and B of each Logic Function shown below shall be OPERABLE:

a. Main Feedwater Isolation,

b. Main Steam Line Isolation,

c. Emergency Feedwater Actuation, and

d. Vector Valve Enable Logic.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channel A A.1 Restore affected channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Functions inoperable OPERABLE status.

with all channel B [OR Functions OPERABLE.

In accordance with OR the Risk Informed Completion Time One or more channel B Program]

Functions inoperable with all channel A Functions OPERABLE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.3.13-1 Rev. 5.0

EFIC Logic 3.3.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.13.1 Perform CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.13-2 Rev. 5.0

EFIC-EFW - Vector Valve Logic 3.3.14 3.3 INSTRUMENTATION 3.3.14 Emergency Feedwater Initiation and Control (EFIC) - Emergency Feedwater (EFW)

- Vector Valve Logic LCO 3.3.14 Four channels of the vector valve logic shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One vector valve logic A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channel inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.3.14-1 Rev. 5.0

EFIC-EFW - Vector Valve Logic 3.3.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.14.1 Perform a CHANNEL FUNCTIONAL TEST. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.14-2 Rev. 5.0

RB Purge Isolation - High Radiation 3.3.15 3.3 INSTRUMENTATION 3.3.15 Reactor Building (RB) Purge Isolation - High Radiation LCO 3.3.15 [One] channel of Reactor Building Purge Isolation - High Radiation shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of [recently] irradiated fuel assemblies within the RB.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable A.1 Place and maintain RB 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in MODE 1, 2, 3, or 4. purge valves in closed positions.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. One channel inoperable C.1 Place and maintain RB Immediately during movement of purge valves in closed

[recently] irradiated fuel positions.

assemblies within the RB. OR C.2 Suspend movement of Immediately

[recently] irradiated fuel assemblies within the RB.

Babcock & Wilcox STS 3.3.15-1 Rev. 5.0

RB Purge Isolation - High Radiation 3.3.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.15.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.15.2 Perform CHANNEL FUNCTIONAL TEST. [ 92 days OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.15.3 Perform CHANNEL CALIBRATION with setpoint [ [18] months Allowable Value [25] mR/hr.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.15-2 Rev. 5.0

Control Room Isolation - High Radiation 3.3.16 3.3 INSTRUMENTATION 3.3.16 Control Room Isolation - High Radiation LCO 3.3.16 [One] channel of Control Room Isolation - High Radiation shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6,]

During movement of [recently] irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable A.1 --------------NOTE--------------

in MODE 1, 2, 3, or 4. Place in toxic gas protection mode if automatic transfer to toxic gas protection mode is inoperable.

Place one OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Control Room Emergency Ventilation System (CREVS) train in the emergency recirculation mode.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. One channel inoperable C.1 Place one OPERABLE Immediately during movement of CREVS train in emergency

[recently] irradiated fuel. recirculation mode.

OR Babcock & Wilcox STS 3.3.16-1 Rev. 5.0

Control Room Isolation - High Radiation 3.3.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.16.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.16.2 -------------------------------NOTE------------------------------

When the Control Room Isolation - High Radiation instrumentation is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Perform CHANNEL FUNCTIONAL TEST. [ 92 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.16-2 Rev. 5.0

Control Room Isolation - High Radiation 3.3.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.16.3 Perform CHANNEL CALIBRATION with setpoint [ [18] months Allowable Value [25] mR/hr.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.16-3 Rev. 5.0

PAM Instrumentation 3.3.17 3.3 INSTRUMENTATION 3.3.17 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.17 The PAM instrumentation for each Function in Table 3.3.17-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

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

channel inoperable.

B. Required Action and B.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.5.

Time of Condition A not met.

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

channels inoperable.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.17-1 for the met. channel.

Babcock & Wilcox STS 3.3.17-1 Rev. 5.0

PAM Instrumentation 3.3.17 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action D.1 and referenced in AND Table 3.3.17-1.

E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.5.

referenced in Table 3.3.17-1.

SURVEILLANCE REQUIREMENTS

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

These SRs apply to each PAM instrumentation Function in Table 3.3.17-1.

SURVEILLANCE FREQUENCY SR 3.3.17.1 Perform CHANNEL CHECK for each required [ 31 days instrumentation channel that is normally energized.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.17-2 Rev. 5.0

PAM Instrumentation 3.3.17 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.17.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.17-3 Rev. 5.0

PAM Instrumentation 3.3.17 Table 3.3.17-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1

1. Wide Range Neutron Flux 2 E

2. RCS Hot Leg Temperature 2 per loop E

3. RCS Cold Leg Temperature 2 per loop E

4. RCS Pressure (Wide Range) 2 E

5. Reactor Vessel Water Level 2 F

6. Containment Sump Water Level (Wide Range) 2 E

7. Containment Pressure (Wide Range) 2 E

8. Penetration Flow Path Containment Isolation 2 per penetration flow path(a)(b) E Valve Position

9. Containment Area Radiation (High Range) 2 F

10. Pressurizer Level 2 E

11. Steam Generator Water Level 2 per SG E

12. Condensate Storage Tank Level 2 E

13. Core Exit Temperature 2 independent sets of 5(c) E

14. Emergency Feedwater Flow 2 E

REVIEWER'S NOTE---------------------------------------------------------------

Table 3.3.17-1 shall be amended for each unit as necessary to list all U.S. NRC Regulatory Guide 1.97, Type A instruments and all U.S. NRC Regulatory Guide 1.97, Category I, non-Type A instruments in accordance with the unit's U.S. NRC Regulatory Guide 1.97, Safety Evaluation Report.

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) The subcooling margin monitor takes the average of the five highest CETs for each of the inadequate core cooling monitor (ICCM) trains.

Babcock & Wilcox STS 3.3.17-4 Rev. 5.0

Remote Shutdown System 3.3.18 3.3 INSTRUMENTATION 3.3.18 Remote Shutdown System LCO 3.3.18 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.18.1 [ Perform CHANNEL CHECK for each required [ 31 days instrumentation channel that is normally energized.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.3.18-1 Rev. 5.0

Remote Shutdown System 3.3.18 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.18.2 Verify each required control circuit and transfer [ [18] months switch is capable of performing the intended function. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.3.18.3 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each [ [18] months required instrumentation channel.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.3.18-2 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits LCO 3.4.1 RCS DNB parameters for loop pressure, hot leg temperature, and RCS total flow rate shall be within the limits specified below:

a. With four reactor coolant pumps (RCPs) operating:

RCS loop pressure shall be [2061.6] psig, RCS hot leg temperature shall be [604.6]F, and RCS total flow rate shall be

[139.7 E6] lb/hr, and

b. With three RCPs operating:

RCS loop pressure shall be [2057.2] psig, RCS hot leg temperature shall be [604.6] F, and RCS total flow rate shall be

[104.4 E6] lb/hr.

APPLICABILITY: MODE 1.

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

RCS loop pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months parameters not within parameter(s) to within limit.

limits.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Babcock & Wilcox STS 3.4.1-1 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 -------------------------------NOTE------------------------------

With three RCPs operating, the limits are applied to the loop with two RCPs in operation.

Verify RCS loop pressure [2061.6] psig with [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months four RCPs operating or [2057.2] psig with three RCPs operating. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.1.2 -------------------------------NOTE------------------------------

With three RCPs operating, the limits are applied to the loop with two RCPs in operation.

Verify RCS hot leg temperature [604.6]F. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.1.3 Verify RCS total flow [139.7 E6] lb/hr with four [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RCPs operating or [104.4 E6] lb/hr with three RCPS operating. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.1-2 Rev. 5.0

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.1.4 -------------------------------NOTE------------------------------

Only required to be performed when stable thermal conditions are established in the higher power range of MODE 1.

Verify RCS total flow rate is within limit by [ [18] months measurement.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.1-3 Rev. 5.0

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be 525F.

APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A.1 Be in MODE 2 with Keff 30 minutes loops not within limit. < 1.0.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 525F. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.2-1 Rev. 5.0

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Restore parameter(s) to 30 minutes Required Action A.2 within limits.

shall be completed whenever this Condition AND is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for continued Requirements of operation.

LCO not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. ------------NOTE------------ C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within limit.

shall be completed whenever this Condition AND is entered.

C.2 Determine RCS is Prior to entering acceptable for continued MODE 4 Requirements of operation.

LCO not met in other than MODE 1, 2, 3, or 4.

Babcock & Wilcox STS 3.4.3-1 Rev. 5.0

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 -------------------------------NOTE------------------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS [ 30 minutes heatup and cooldown rates are within the limits specified in the PTLR. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.3-2 Rev. 5.0

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES 1 and 2 LCO 3.4.4 Two RCS Loops shall be in operation, with:

a. Four reactor coolant pumps (RCPs) operating or

b. Three RCPs operating and THERMAL POWER restricted to

[79.9]% RTP.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify required RCS loops are in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.4-1 Rev. 5.0

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE and one RCS loop shall be in operation.

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

All reactor coolant pumps (RCPs) may be removed from operation for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period for the transition to or from the Decay Heat Removal System, and all RCPs may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for any other reason, provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1 and

b. Core outlet temperature is maintained at least [10]F below saturation temperature.

APPLICABILITY: MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Restore RCS loop to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

Babcock & Wilcox STS 3.4.5-1 Rev. 5.0

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two RCS loops C.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required RCS loop not of LCO 3.1.1.

in operation.

AND C.2 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify one RCS loop is in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.5-2 Rev. 5.0

RCS Loops - MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.5.2 ------------------------------NOTE-----------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power available to each required pump.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.5-3 Rev. 5.0

RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and decay heat removal (DHR) loops shall be OPERABLE and one loop shall be in operation.

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

All reactor coolant pumps (RCPs) may be removed from operation for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period for the transition to or from the DHR System, and all RCPs and DHR pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for any other reason, provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1 and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required loop A.1 --------------NOTE--------------

inoperable. LCO 3.0.4.a is not applicable when entering MODE 4.

Initiate action to restore a Immediately second loop to OPERABLE status.

Babcock & Wilcox STS 3.4.6-1 Rev. 5.0

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two required loops B.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required loop not in of LCO 3.1.1.

operation.

AND B.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required DHR or RCS loop is in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.6-2 Rev. 5.0

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.6.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power available to each required pump.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.6.3 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 4.

Verify required DHR loop locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.6-3 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One decay heat removal (DHR) loop shall be OPERABLE and in operation, and either:

a. One additional DHR loop shall be OPERABLE or

b. The secondary side water level of each steam generator (SG) shall be [50]%.

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

1. The DHR pump of the loop in operation may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1 and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

2. One required DHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other DHR loop is OPERABLE and in operation.

3. All DHR loops may be not in operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY: MODE 5 with RCS loops filled.

Babcock & Wilcox STS 3.4.7-1 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required DHR loop A.1 Initiate action to restore a Immediately inoperable. second DHR loop to OPERABLE status.

AND OR One DHR loop OPERABLE. A.2 Initiate action to restore Immediately required SGs secondary side water levels to within limits.

B. One or more required B.1 Initiate action to restore a Immediately SGs with secondary side second DHR loop to water level not within OPERABLE status.

limit.

OR AND B.2 Initiate action to restore Immediately One DHR loop required SGs secondary OPERABLE. side water level to within limit.

C. No required DHR loop C.1 Suspend operations that Immediately OPERABLE. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required DHR loop not of LCO 3.1.1.

in operation.

AND C.2 Initiate action to restore one Immediately DHR loop to OPERABLE status and operation.

Babcock & Wilcox STS 3.4.7-2 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required DHR loop is in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.7.2 Verify required SG secondary side water levels are [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

[50]%.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.7.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power available to each required DHR pump.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.7-3 Rev. 5.0

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.7.4 Verify required DHR loop locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.7-4 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two decay heat removal (DHR) loops shall be OPERABLE and one DHR loop shall be in operation.

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

1. All DHR pumps may be removed from operation for 15 minutes when switching from one loop to another provided:

[ a. The maximum RCS temperature is [160]F, ]

b. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1 and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One DHR loop may be inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other DHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required DHR loop A.1 Initiate action to restore Immediately inoperable. DHR loop to OPERABLE status.

Babcock & Wilcox STS 3.4.8-1 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No required DHR loop B.1 Suspend operations that Immediately OPERABLE. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SDM Required DHR loop not of LCO 3.1.1.

in operation.

AND B.2 Initiate action to restore one Immediately DHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required DHR loop is in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.8-2 Rev. 5.0

RCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.8.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required pump is not in operation.

Verify correct breaker alignment and indicated [ 7 days power available to each required DHR pump.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.8.3 Verify DHR loop locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.8-3 Rev. 5.0

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level [290] inches and

b. A minimum of [126] kW of pressurizer heaters OPERABLE [and capable of being powered from an emergency power supply].

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

OPERABILITY requirements on pressurizer heaters do not apply in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with RCS temperature [275]F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level A.1 Restore level to within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4 with RCS [24] hours temperature [275]F.

C. Capacity of pressurizer C.1 Restore pressurizer heater 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months heaters [capable of capability.

being powered by [OR emergency power supply] less than limit. In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.4.9-1 Rev. 5.0

Pressurizer 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level [290] inches. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.9.2 [ Verify [126] kW of pressurizer heaters are [ [18] months capable of being powered from an emergency power supply. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.4.9-2 Rev. 5.0

Pressurizer 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.3 [ Verify emergency power supply for pressurizer [ [18] months heaters is OPERABLE.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.4.9-3 Rev. 5.0

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings

[2475] psig and [2525] psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > [283]F.

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

The lift settings are not required to be within the LCO limits for entry into MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for [36] hours following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 4 with any [24] hours RCS cold leg temperature Two pressurizer safety [283]F.

valves inoperable.

Babcock & Wilcox STS 3.4.10-1 Rev. 5.0

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE In accordance in accordance with the INSERVICE TESTING with the PROGRAM. Following testing, lift settings shall be INSERVICE within +/- 1%. TESTING PROGRAM Babcock & Wilcox STS 3.4.10-2 Rev. 5.0

Pressurizer PORV 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valve (PORV)

LCO 3.4.11 The PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. PORV inoperable. A.1 Close block valve. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Remove power from block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

B. Block valve inoperable. B.1 Close block valve. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.2 Remove power from block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.4.11-1 Rev. 5.0

Pressurizer PORV 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 -------------------------------NOTE------------------------------

Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.

Perform one complete cycle of the block valve. [ 92 days OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.11.2 Perform one complete cycle of the PORV. [ 18 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.11.3 [ Verify PORV and block valve are capable of being [ 18 months powered from an emergency power source.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.4.11-2 Rev. 5.0

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of [one] makeup pump capable of injecting into the RCS, high pressure injection (HPI) deactivated, and the core flood tanks (CFTs) isolated and:

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

1. [Two makeup pumps] may be capable of injecting for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for pump swap operations.

2. CFT may be unisolated when CFT pressure is less than the maximum RCS pressure for the existing RCS temperature allowed by the pressure and temperature limit curves provided in the PTLR.

a. Pressurizer level [220] inches and an OPERABLE power operated relief valve (PORV) with a lift setpoint of [555] psig or

b. The RCS depressurized and an RCS vent of [0.75] square inch.

APPLICABILITY: MODE 4 when any RCS cold leg temperature is [283]F, MODE 5, MODE 6 when the reactor vessel head is on.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. More than [one] makeup A.1 Initiate action to verify only Immediately pump capable of [one] makeup pump is injecting into the RCS. capable of injecting into the RCS.

B. HPI activated. B.1 Initiate action to verify HPI Immediately deactivated.

Babcock & Wilcox STS 3.4.12-1 Rev. 5.0

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. A CFT not isolated when C.1 Isolate affected CFT. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CFT pressure is greater than or equal to the maximum RCS pressure for existing temperature allowed in the PTLR.

D. Required Action C.1 not D.1 Increase RCS temperature 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months met within the required to > 175F.

Completion Time.

OR D.2 Depressurize affected CFT 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to < [555] psig.

E. Pressurizer level E.1 Restore pressurizer level to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

> [220] inches. [220] inches.

F. Required Action E.1 not F.1 Close and maintain closed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months met within the required the makeup control valve Completion Time. and its associated isolation valve.

AND F.2 Stop RCS heatup. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months G. PORV inoperable. G.1 Restore PORV to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

H. Required Action G.1 not H.1 Reduce makeup tank level 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months met within the required to [70] inches.

Completion Time.

AND H.2 Deactivate low low makeup 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months tank level interlock to the borated water storage tank suction valves.

Babcock & Wilcox STS 3.4.12-2 Rev. 5.0

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. Pressurizer level I.1 Depressurize RCS and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> [220] inches. establish RCS vent of

[0.75] square inch.

AND PORV inoperable.

OR LTOP System inoperable for any reason other than Condition A through Condition H.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of [one] makeup pump is capable [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of injecting into the RCS.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.2 Verify HPI is deactivated. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.12-3 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.3 Verify each CFT is isolated. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.4 Verify pressurizer level is [220] inches. 30 minutes during RCS heatup and cooldown AND

[ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.5 Verify PORV block valve is open. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.12-4 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.6 Verify required RCS vent [0.75] square inch is [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open. unlocked open vent valve(s)

AND 31 days for other vent path(s)

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.12.7 Perform CHANNEL FUNCTIONAL TEST for PORV. Within [12] hours after decreasing RCS temperature to [283]F AND

[ 31 days thereafter OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.12-5 Rev. 5.0

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.8 Perform CHANNEL CALIBRATION for PORV. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.12-6 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE,

b. 1 gpm unidentified LEAKAGE,

c. 10 gpm identified LEAKAGE, and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressure boundary A.1 Isolate affected component, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE exists. pipe, or vessel from the RCS by use of a closed manual valve, closed and de-activated automatic valve, blind flange, or check valve.

B. RCS operational B.1 Reduce LEAKAGE to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

Babcock & Wilcox STS 3.4.13-1 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Primary to secondary LEAKAGE not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ------------------------------NOTES-----------------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by [ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months performance of RCS water inventory balance.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.13-2 Rev. 5.0

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.13.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is [ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 150 gallons per day through any one SG.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.13-3 Rev. 5.0

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limits.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except valves in the decay heat removal (DHR) flow path when in, or during the transition to or from, the DHR mode of operation.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths --------------------NOTE-------------------

with leakage from one or Each valve used to satisfy Required more RCS PIVs not Action A.1 and Required Action A.2 within limit. must have been verified to meet SR 3.4.14.1 and be on the RCS pressure boundary [or the high pressure portion of the system].

A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND Babcock & Wilcox STS 3.4.14-1 Rev. 5.0

RCS PIV Leakage 3.4.14 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 [ Isolate the high pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

[or]

Restore RCS PIV to within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ]

limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. [ Decay Heat Removal C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ]

(DHR) System penetration by use of one autoclosure interlock closed manual or function inoperable. deactivated automatic valve.

Babcock & Wilcox STS 3.4.14-2 Rev. 5.0

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 ------------------------------NOTES-----------------------------

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the DHR flow path when in the DHR mode of operation.

3. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent to [ In accordance 0.5 gpm per nominal inch of valve size up to a with the maximum of 5 gpm at an RCS pressure INSERVICE

[2215] psia and [2255] psia. TESTING PROGRAM OR

[ [18] months]

OR In accordance with the Surveillance Frequency Control Program ]

AND Babcock & Wilcox STS 3.4.14-3 Rev. 5.0

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND

[ Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve ]

SR 3.4.14.2 -------------------------------NOTE------------------------------

[ Not required to be met when the DHR System autoclosure interlock is disabled in accordance with LCO 3.4.12.

Verify DHR System autoclosure interlock prevents [ [18] months the valves from being opened with a simulated or actual RCS pressure signal [425] psig. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.4.14-4 Rev. 5.0

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.14.3 -------------------------------NOTE------------------------------

[ Not required to be met when the DHR System autoclosure interlock is disabled in accordance with LCO 3.4.12.

Verify DHR System autoclosure interlock causes the [ [18] months valves to close automatically with a simulated or actual RCS pressure signal [600] psig. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.4.14-5 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump monitor and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment sump A.1 --------------NOTE--------------

monitor inoperable. Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore containment sump 30 days monitor to OPERABLE status.

B. Required containment B.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere radioactivity the containment monitor inoperable. atmosphere.

OR Babcock & Wilcox STS 3.4.15-1 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 --------------NOTE--------------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

NOTE -------------- C.1 Analyze grab samples of Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Only applicable when the the containment containment atmosphere atmosphere.

gaseous radiation monitor is the only OPERABLE AND monitor.

C.2 Restore containment sump 7 days monitor to OPERABLE C. Containment sump status.

monitor inoperable.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 ------------- NOTE ------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Both required monitors E.1 Enter LCO 3.0.3. Immediately inoperable.

Babcock & Wilcox STS 3.4.15-2 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of required containment [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.15.2 Perform CHANNEL FUNCTIONAL TEST of required [ 92 days containment atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.15-3 Rev. 5.0

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.15.3 Perform CHANNEL CALIBRATION of required [ [18] months containment sump monitor.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.4.15.4 Perform CHANNEL CALIBRATION of required [ [18] months containment atmosphere radioactivity monitor.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.15-4 Rev. 5.0

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE --------------------NOTE-------------------

EQUIVALENT I-131 not LCO 3.0.4.c is applicable.

within limit. ------------------------------------------------

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131

[60] Ci/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT I-131 to within limit.

B. DOSE --------------------NOTE-------------------

EQUIVALENT XE-133 LCO 3.0.4.c is applicable.

not within limit. ------------------------------------------------

B.1 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT XE-133 to within limit.

Babcock & Wilcox STS 3.4.16-1 Rev. 5.0

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR DOSE EQUIVALENT I-131

> [60] Ci/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT XE-133 [ 7 days specific activity [280] µCi/gm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.4.16-2 Rev. 5.0

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.2 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 [ 14 days specific activity [1.0] Ci/gm.

OR In accordance with the Surveillance Frequency Control Program ]

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Babcock & Wilcox STS 3.4.16-3 Rev. 5.0

SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube plugging [or repair] criteria shall be plugged [or repaired] in accordance with the Steam Generator Program.

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

ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube affected tube(s) is plugging [or repair] maintained until the next criteria and not plugged refueling outage or SG tube

[or repaired] in inspection.

accordance with the Steam Generator AND Program.

A.2 Plug [or repair] the affected Prior to entering tube(s) in accordance with MODE 4 following the the Steam Generator next refueling outage Program. or SG tube inspection B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR SG tube integrity not maintained.

Babcock & Wilcox STS 3.4.17-1 Rev. 5.0

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance Steam Generator Program. with the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube plugging [or repair] criteria is plugged [or MODE 4 following repaired] in accordance with the Steam Generator a SG tube Program. inspection Babcock & Wilcox STS 3.4.17-2 Rev. 5.0

CFTs 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Core Flood Tanks (CFTs)

LCO 3.5.1 Two CFTs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System (RCS) pressure > [750] psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CFT inoperable due A.1 Restore boron 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to boron concentration concentration to within not within limits. limits.

B. One CFT inoperable for B.1 Restore CFT to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Reduce RCS pressure to [12] hours

[750] psig.

D. Two CFTs inoperable. D.1 Enter LCO 3.0.3. Immediately Babcock & Wilcox STS 3.5.1-1 Rev. 5.0

CFTs 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each CFT isolation valve is fully open. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.1.2 Verify borated water volume in each CFT is [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

[7555 gallons, [ ] ft and 8005 gallons, [ ] ft].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.1.3 Verify nitrogen cover pressure in each CFT is [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

[575] psig and [625] psig.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.5.1-2 Rev. 5.0

CFTs 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.4 Verify boron concentration in each CFT is [ 31 days

[2270] ppm and [3500] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

AND

NOTE--------

Only required to be performed for affected CFT Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of

[80 gallons] that is not the result of addition from the borated water storage tank SR 3.5.1.5 Verify power is removed from each CFT isolation [ 31 days valve operator when RCS pressure is [2000] psig.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.5.1-3 Rev. 5.0

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

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

[ Operation in MODE 3 with high pressure injection (HPI) de-activated in accordance with LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," is allowed for up to [4] hours. ]

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure A.1 Restore LPI subsystem to [7] days injection (LPI) OPERABLE status.

subsystem inoperable. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more trains B.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons OPERABLE status.

other than Condition A. [OR In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.5.2-1 Rev. 5.0

ECCS - Operating 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Less than 100% of the D.1 Enter LCO 3.0.3. D.1 Immediately ECCS flow equivalent to a single OPERABLE train available.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 [ Verify the following valves are in the listed position [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power to the valve operator removed.

OR Valve Number Position Function

[ ] [ ] [ ] In accordance

[ ] [ ] [ ] with the

[ ] [ ] [ ] Surveillance Frequency Control Program ] ]

SR 3.5.2.2 ---------------------------------NOTE----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, and [ 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the OR correct position.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.5.2-2 Rev. 5.0

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify ECCS locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the required developed head. INSERVICE TESTING PROGRAM SR 3.5.2.5 Verify each ECCS automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.5.2.6 Verify each ECCS pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.5.2-3 Rev. 5.0

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.7 [ Verify the correct settings of stops for the following [ [18] months HPI stop check valves:

OR

a. [MUV-2],

b. [MUV-6], and In accordance

c. [MUV-10]. with the Surveillance Frequency Control Program ] ]

SR 3.5.2.8 [ Verify the flow controllers for the following LPI [ [18] months throttle valves operate properly:

OR

a. [DHV-110] and

b. [DHV-111]. In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.5.2-4 Rev. 5.0

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

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

1. A DHR train may be considered OPERABLE during alignment and operation for DHR, if capable of being manually realigned to the ECCS mode of operation.

2. High pressure injection (HPI) may be de-activated in accordance with LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP) System."

APPLICABILITY: MODE 4.

ACTIONS

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

LCO 3.0.4.b is not applicable to ECCS DHR loops.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS decay A.1 Initiate action to restore Immediately heat removal (DHR) loop required ECCS DHR loop inoperable. to OPERABLE status.

B. Required ECCS HPI B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable. HPI subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

Babcock & Wilcox STS 3.5.3-1 Rev. 5.0

ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 For all equipment required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs

[SR 3.5.2.1] SR 3.5.2.6 SR 3.5.2.2 [SR 3.5.2.7]

[SR 3.5.2.3] [SR 3.5.2.8]

SR 3.5.2.4 SR 3.5.2.5 Babcock & Wilcox STS 3.5.3-2 Rev. 5.0

BWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Borated Water Storage Tank (BWST)

LCO 3.5.4 The BWST shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. BWST boron A.1 Restore BWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not within OPERABLE status.

limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. BWST water C.1 Restore BWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within OPERABLE status.

limits.

D. BWST inoperable for D.1 Restore BWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A or C.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C or D AND not met.

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Babcock & Wilcox STS 3.5.4-1 Rev. 5.0

BWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 -------------------------------NOTE------------------------------

Only required to be performed when ambient air temperature is < [40]F or > [100]F.

Verify BWST borated water temperature is [40]F [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and [100]F.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.4.2 Verify BWST borated water volume is [ 7 days

[415,200 gallons] [ ] ft. and [449,000 gallons]

[ ] ft. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.5.4.3 Verify BWST boron concentration is [2270] ppm [ 7 days and [2450] ppm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.5.4-2 Rev. 5.0

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance rate testing except for containment air lock testing, with the in accordance with the Containment Leakage Rate Containment Testing Program. Leakage Rate Testing Program SR 3.6.1.2 [ Verify containment structural integrity in In accordance accordance with the Containment Tendon with the Surveillance Program. Containment Tendon Surveillance Program ]

Babcock & Wilcox STS 3.6.1-1 Rev. 5.0

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 [Two] containment air lock[s] shall be OPERABLE.

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

ACTIONS

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

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more -------------------NOTES------------------

containment air locks 1. Required Actions A.1, A.2, with one containment air and A.3 are not applicable if both lock door inoperable. doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls [if both air locks are inoperable].

A.1 Verify the OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Babcock & Wilcox STS 3.6.2-1 Rev. 5.0

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 Lock the OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND A.3 --------------NOTE--------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE door Once per 31 days is locked closed in the affected air lock.

B. One or more -------------------NOTES------------------

containment air locks 1. Required Actions B.1, B.2, with containment air lock and B.3 are not applicable if both interlock mechanism doors in the same air lock are inoperable. inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Babcock & Wilcox STS 3.6.2-2 Rev. 5.0

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND B.3 --------------NOTE--------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is locked closed in the affected air lock.

C. One or more C.1 Initiate action to evaluate Immediately containment air locks overall containment inoperable for reasons leakage rate per LCO 3.6.1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.6.2-3 Rev. 5.0

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 --------------NOTE--------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 ------------------------------NOTES-----------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in In accordance accordance with the Containment Leakage Rate with the Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be opened at [ 24 months a time.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.2-4 Rev. 5.0

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

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

ACTIONS

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

1. Penetration flow paths [except for 48 inch purge valve penetration flow paths] may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for system(s) made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

Babcock & Wilcox STS 3.6.3-1 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

REVIEWER'S NOTE----- A.1 Determine the OPERABLE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months The Condition A Note containment isolation valve should list the specific in the affected penetration penetrations (if any) is not inoperable due to identified by the plant- common cause failure.

specific risk analysis as having high risk significance AND for an interfacing systems loss of coolant accident (ISLOCA). A.2 Isolate the affected 7 days

penetration flow path by use of at least one closed [OR A. ------------NOTE------------ and de-activated automatic Only applicable to valve, closed manual valve, In accordance with penetration flow paths blind flange, or check valve the Risk Informed with two [or more] with flow through the valve Completion Time containment isolation secured. Program]

valves except containment isolation AND valves in the main steam lines and [ ].

One or more penetration flow paths with one containment isolation valve inoperable [for reasons other than purge valve leakage not within limit].

Babcock & Wilcox STS 3.6.3-2 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 -------------NOTES--------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is [following isolation]

isolated. for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Babcock & Wilcox STS 3.6.3-3 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

REVIEWER'S NOTE----- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months The Condition B Note penetration flow path by should list the specific use of at least one closed [OR penetrations (if any) and de-activated automatic identified by the plant- valve, closed manual valve, In accordance with specific risk analysis as blind flange, or check valve the Risk Informed having high risk significance with flow through the valve Completion Time for an interfacing systems secured. Program]

loss of coolant accident (ISLOCA). AND B.2 -------------NOTES--------------

B. ------------NOTE------------ 1. Isolation devises in high Only applicable to radiation areas may be penetration flow paths verified by use of with two [or more] administrative means.

containment isolation valves in the main steam 2. Isolation devices that lines and [ ]. are locked, sealed, or

otherwise secured may be verified by use of One or more penetration administrative means.

flow paths with one -------------------------------------

containment isolation valve inoperable [for Verify the affected Once per 31 days reasons other than penetration flow path is [following isolation]

purge valve leakage not isolated. for isolation devices within limit]. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Babcock & Wilcox STS 3.6.3-4 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Isolate all but one of the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to affected penetration flow penetration flow paths paths by use of at least one with two [or more] closed and de-activated containment isolation automatic valve, closed valves. manual valve, or blind

flange.

Two or more penetration flow paths with one containment isolation valve inoperable [for reasons other than Condition[s] E [and F] ].

D. ------------NOTE------------ D.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two [or more] and de-activated automatic containment isolation valve, closed manual valve, valves. or blind flange.

One or more penetration flow paths with two [or more] containment isolation valves inoperable [for reasons other than purge valve leakage not within limit].

Babcock & Wilcox STS 3.6.3-5 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. ------------NOTE------------ E.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path by penetration flow paths use of at least one closed [OR with only one and de-activated automatic containment isolation valve, closed manual valve, In accordance with valve and a closed or blind flange. the Risk Informed system. Completion Time

Program]

One or more penetration AND flow paths with one containment isolation E.2 -------------NOTES--------------

valve inoperable. 1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is [following isolation]

isolated.

F. [ One or more F.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months penetration flow paths penetration flow path by with one or more use of at least one [closed containment purge and de-activated automatic valves not within purge valve, closed manual valve, valve leakage limits. or blind flange].

AND Babcock & Wilcox STS 3.6.3-6 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.2 -------------NOTES--------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment AND F.3 Perform SR 3.6.3.6 for the Once per [ ] days ]

resilient seal purge valves closed to comply with Required Action E.1.

Babcock & Wilcox STS 3.6.3-7 Rev. 5.0

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND G.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 [ Verify each [48] inch purge valve is sealed closed [ 31 days except for one purge valve in a penetration flow path while in Condition D of the LCO. OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.6.3.2 Verify each [8] inch purge valve is closed except [ 31 days when the [8] inch purge valves are open for pressure control, ALARA or air quality OR considerations for personnel entry, or for Surveillances that require the valves to be open. In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.3-8 Rev. 5.0

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.3 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and [ 31 days blind flange that is located outside containment and not locked, sealed, or otherwise secured and is OR required to be closed during accident conditions is closed, except for containment isolation valves that In accordance are open under administrative controls. with the Surveillance Frequency Control Program ]

SR 3.6.3.4 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days Babcock & Wilcox STS 3.6.3-9 Rev. 5.0

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.5 Verify the isolation time of each automatic power [In accordance operated containment isolation valve is within limits. with the INSERVICE TESTING PROGRAM OR

[92 days]

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.3.6 Perform leakage rate testing for containment purge [ 184 days valves with resilient seals.

OR In accordance with the Surveillance Frequency Control Program ]

AND Within 92 days after opening the valve Babcock & Wilcox STS 3.6.3-10 Rev. 5.0

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.7 Verify each automatic containment isolation valve [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.3.8 [ Verify each [ ] inch containment purge valve is [ [18] months blocked to restrict the valve from opening > [50]%.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.6.3-11 Rev. 5.0

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be [-2.0] psig and [+3.0] psig.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.4-1 Rev. 5.0

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be [130]F.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air temperature to limit. within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.6.5-1 Rev. 5.0

Containment Air Temperature 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is within [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months limit.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.5-2 Rev. 5.0

Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray [7] days train inoperable. train to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months C. One [required] C.1 Restore [required] 7 days containment cooling containment cooling train to train inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.6.6-1 Rev. 5.0

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One containment spray D.1 Restore containment spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months train and one [required] train to OPERABLE status.

containment cooling [OR train inoperable. OR In accordance with D.2 Restore [required] the Risk Informed containment cooling train to Completion Time OPERABLE status. Program]

E. Two [required] E.1 Restore one [required] 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment cooling containment cooling train to trains inoperable. OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C or D AND not met.

F.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months G. Two containment spray G.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Any combination of three or more trains inoperable.

Babcock & Wilcox STS 3.6.6-2 Rev. 5.0

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 -------------------------------NOTE---------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power [ 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in OR position is in the correct position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6.2 Operate each [required] containment cooling train [ 31 days fan unit for 15 minutes.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6.3 Verify each [required] containment cooling train [ 31 days cooling water flow rate is [1780] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.6-3 Rev. 5.0

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.4 Verify containment spray locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6.5 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. INSERVICE TESTING PROGRAM SR 3.6.6.6 Verify each automatic containment spray valve in [ [18] months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position OR on an actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6.7 Verify each containment spray pump starts [ [18] months automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.6-4 Rev. 5.0

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.8 Verify each [required] containment cooling train [ [18] months starts automatically on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.6.9 Verify each spray nozzle is unobstructed. [ At first refueling ]

AND

[ 10 years OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.6-5 Rev. 5.0

Spray Additive System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Spray Additive System LCO 3.6.7 The Spray Additive System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A.1 Restore Spray Additive 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. System to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify each spray additive manual, power operated, [ 31 days and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in OR the correct position.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.7-1 Rev. 5.0

Spray Additive System 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.2 Verify spray additive tank solution volume is [ 184 days

[12,970] gal and [13,920] gal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.3 Verify spray additive tank [NaOH] solution [ 184 days concentration is [60,000 ppm] and [65,000 ppm].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.4 Verify each spray additive automatic valve in the [ [18] months flow path actuates to the correct position on an actual or simulated actuation signal, except for OR valves that are locked, sealed, or otherwise secured in the actuated position. In accordance with the Surveillance Frequency Control Program ]

SR 3.6.7.5 Verify Spray Additive System flow [rate] from each [ 5 years solution's flow path.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.6.7-2 Rev. 5.0

Containment Sump 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Containment Sump LCO 3.6.8 [The][Two] containment sump[s] shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. [One or more] A.1 Initiate action to mitigate Immediately containment sump[s] containment accident inoperable due to generated and transported containment accident debris.

generated and transported debris AND exceeding the analyzed limits. A.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.3 Restore the containment 90 days sump[s] to OPERABLE status.

Babcock & Wilcox STS 3.6.8-1 Rev. 5.0

Containment Sump 3.6.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. [One or more] B.1 --------------NOTES-------------

containment sump[s] 1. Enter applicable inoperable for reasons Conditions and other than Condition A. Required Actions of LCO 3.5.2, "ECCS -

Operating," and LCO 3.5.3, "ECCS -

Shutdown," for emergency core cooling trains made inoperable by the containment sump[s].

2. Enter applicable Conditions and Required Actions of LCO 3.6.6, "Containment Spray and Cooling Systems,"

for containment spray trains made inoperable by the containment sump[s].

Restore the containment [72 hours]

sump[s] to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Babcock & Wilcox STS 3.6.8-2 Rev. 5.0

Containment Sump 3.6.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify, by visual inspection, the containment sump[s] [ [18] months does not show structural damage, abnormal corrosion, or debris blockage. OR In accordance with the Surveillance Frequency Control Program]

Babcock & Wilcox STS 3.6.8-3 Rev. 5.0

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Figure 3.7.1-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Reduce power to less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months MSSVs inoperable. the reduced power requirement of Figure 3.7.1-1.

AND A.2 Reduce the nuclear 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months overpower trip setpoint in accordance with Figure 3.7.1-1.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators with less than [two] MSSVs OPERABLE.

Babcock & Wilcox STS 3.7.1-1 Rev. 5.0

MSSVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance Table 3.7.1-1 in accordance with the INSERVICE with the TESTING PROGRAM. Following testing, lift INSERVICE settings shall be within +/- 1%. TESTING PROGRAM Babcock & Wilcox STS 3.7.1-2 Rev. 5.0

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

Main Steam Safety Valve Lift Settings LIFT SETTING VALVE NUMBER (psig +/- [3]%)

[2] MSSVs/steam generator [1050]

[7] MSSVs/steam generator [ 1100]

Babcock & Wilcox STS 3.7.1-3 Rev. 5.0

MSSVs 3.7.1 Babcock & Wilcox STS 3.7.1-4 Rev. 5.0

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed [and deactivated].

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to [8] hours MODE 1. OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. ------------NOTE------------ C.1 Close MSIV. [8] hours Separate Condition entry is allowed for each AND MSIV.

C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.7.2-1 Rev. 5.0

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify isolation time of each MSIV is within limits. In accordance with the INSERVICE TESTING PROGRAM SR 3.7.2.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each MSIV actuates to the isolation position [ [18] months on an actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.2-2 Rev. 5.0

[MFSVs, MFCVs, and Associated SFCVs]

3.7.3 3.7 PLANT SYSTEMS 3.7.3 [Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs),

and Associated Startup Feedwater Control Valves (SFCVs)]

LCO 3.7.3 [Two] [MFSVs], [MFCVs], [or associated SFCVs] shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 except when all [MFSVs], [MFCVs], [or associated SFCVs] are closed [and deactivated] [or isolated by a closed manual valve].

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One [MFSV] in one or A.1 Close or isolate [MFSV]. [8 or 72] hours more flow paths inoperable. AND A.2 Verify [MFSV] is closed or Once per 7 days isolated.

B. One [MFCV] in one or B.1 Close or isolate [MFCV]. [8 or 72] hours more flow paths inoperable. AND B.2 Verify [MFCV] is closed or Once per 7 days isolated.

C. One [SFCV] in one or C.1 Close or isolate [SFCV]. [8 or 72] hours more flow paths inoperable. AND C.2 Verify [SFCV] is closed or Once per 7 days isolated.

Babcock & Wilcox STS 3.7.3-1 Rev. 5.0

[MFSVs, MFCVs, and Associated SFCVs]

3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path inoperable for one or more flow paths.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. [ AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ]

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify the isolation time of each [MFSV], [MFCV], In accordance and [SFCV] is within limits. with the INSERVICE TESTING PROGRAM SR 3.7.3.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each [MFSV], [MFCV], and [SFCV] actuates [ [18] months to the isolation position on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.3-2 Rev. 5.0

AVVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Vent Valves (AVVs)

LCO 3.7.4 [Two] AVVs [lines per steam generator] shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required AVV [line] A.1 Restore required AVV [line] [7 days]

inoperable. to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

B. [ Two or more required B.1 Restore all but one AVV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ]

AVV [lines] inoperable. [line] to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4 without [24] hours reliance upon steam generator for heat removal.

Babcock & Wilcox STS 3.7.4-1 Rev. 5.0

AVVs 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each AVV. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.4.2 [ Verify one complete cycle of each AVV block [ [18] months valve.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.4-2 Rev. 5.0

EFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Emergency Feedwater (EFW) System LCO 3.7.5 [Three] EFW trains shall be OPERABLE.

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

Only one EFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME A. [ Turbine driven EFW A.1 Restore affected equipment 7 days train inoperable due to to OPERABLE status.

one inoperable steam [OR supply.

In accordance with OR the Risk Informed Completion Time

NOTE------------ Program] ]

Only applicable if MODE 2 has not been entered following refueling.

One turbine driven EFW pump inoperable in MODE 3 following refueling.

Babcock & Wilcox STS 3.7.5-1 Rev. 5.0

EFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One EFW train B.1 Restore EFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, OPERABLE status.

2, or 3 [for reasons other [OR than Condition A].

In accordance with the Risk Informed Completion Time Program]

C. One turbine driven EFW C.1 Restore the steam supply [24 or 48] hours train inoperable due to to the turbine driven train to one inoperable steam OPERABLE status.

supply.

OR AND C.2 Restore the motor driven [24 or 48] hours Motor driven EFW train EFW train to OPERABLE inoperable. status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A [B, AND or C] not met.

D.2 Be in MODE 4. [18] hours

[ OR Two EFW trains inoperable in MODE 1, 2, or 3 for reasons other than Condition C. ]

Babcock & Wilcox STS 3.7.5-2 Rev. 5.0

EFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. [Three] EFW trains E.1 --------------NOTE---------------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one EFW train is restored to OPERABLE status.

Initiate action to restore Immediately one EFW train to OPERABLE status.

F. Required EFW train F.1 Initiate action to restore Immediately inoperable in MODE 4. EFW train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each EFW manual, power operated, and [ 31 days automatic valve in each water flow path and in both steam supply flow paths to the steam turbine driven OR pumps, that is not locked, sealed, or otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.5-3 Rev. 5.0

EFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.2 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven EFW pumps, until [24] hours after reaching

[800] psig in the steam generators.

Verify the developed head of each EFW pump at the In accordance flow test point is greater than or equal to the with the required developed head. INSERVICE TESTING PROGRAM SR 3.7.5.3 ------------------------------NOTES-----------------------------

1. Not required to be performed until [24] hours after reaching [800] psig in the steam generators.

2. Not required to be met in MODE 4.

Verify each EFW automatic valve that is not locked, [ [18] months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated OR actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.5-4 Rev. 5.0

EFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.4 ------------------------------NOTES-----------------------------

1. Not required to be performed until [24] hours after reaching [800] psig in the steam generators.

2. Not required to be met in MODE 4.

Verify each EFW pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.5.5 Verify proper alignment of the required EFW flow Prior to entering paths by verifying [valve alignment/flow] from the MODE 2 condensate storage tank to each steam generator. whenever plant has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days SR 3.7.5.6 [ Perform a CHANNEL FUNCTIONAL TEST for the [ 31 days EFW pump suction pressure interlocks.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.5-5 Rev. 5.0

EFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.7 [ Perform a CHANNEL CALIBRATION for the EFW [ [18] months pump suction pressure interlocks.

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.5-6 Rev. 5.0

CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)

LCO 3.7.6 The [two] CST(s) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The [two] CST(s) A.1 Verify by administrative 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable. means OPERABILITY of backup water supply. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore CST(s) to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4 without [24] hours reliance on steam generator for heat removal.

Babcock & Wilcox STS 3.7.6-1 Rev. 5.0

CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify CST level is [250,000] gal. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.6-2 Rev. 5.0

CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 -------------NOTES--------------

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources -

Operating," for emergency diesel generator made inoperable by CCW.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops

- MODE 4," for decay heat removal made inoperable by CCW.

Restore CCW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.7.7-1 Rev. 5.0

CCW System 3.7.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 -------------------------------NOTE------------------------------

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

Verify each CCW manual, power operated, and [ 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or OR otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

SR 3.7.7.2 Verify each CCW automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.7-2 Rev. 5.0

CCW System 3.7.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.7.3 Verify each CCW pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.7-3 Rev. 5.0

SWS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water System (SWS)

LCO 3.7.8 Two SWS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SWS train A.1 -------------NOTES--------------

inoperable. 1. [ Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"

for emergency diesel generator made inoperable by SWS. ]

2. [ Enter Applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops

- MODE 4," for decay heat removal made inoperable by SWS. ]

Restore SWS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.7.8-1 Rev. 5.0

SWS 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------------------NOTE------------------------------

Isolation of SWS flow to individual components does not render the SWS inoperable.

Verify each SWS manual, power operated, and [ 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or OR otherwise secured in position, is in the correct position. In accordance with the Surveillance Frequency Control Program ]

SR 3.7.8.2 Verify each SWS automatic valve in the flow path [ [18] months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an OR actual or simulated actuation signal.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.8-2 Rev. 5.0

SWS 3.7.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.8.3 Verify each SWS pump starts automatically on an [ [18] months actual or simulated actuation signal.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.8-3 Rev. 5.0

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. [ One or more cooling A.1 Restore cooling tower 7 days towers with one cooling fan(s) to OPERABLE tower fan inoperable. status. [OR In accordance with the Risk Informed Completion Time Program] ]

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.7.9-1 Rev. 5.0

UHS 3.7.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

REVIEWER'S NOTE----- C.1 Verify water temperature of Once per hour]

The [ ]F is the maximum the UHS is [90]F allowed UHS temperature averaged over the previous value and is based on 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

temperature limitations of the equipment that is relied upon for accident mitigation and safe shutdown of the unit.

C. [ Water temperature of the UHS > [90]F and

[ ]F.

D. [ Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR ]

UHS inoperable [for reasons other than Condition A or C].

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 [ Verify water level of UHS is [562] ft [mean sea [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months level].

OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.9-2 Rev. 5.0

UHS 3.7.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.9.2 [ Verify average water temperature of UHS is [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

[90]F.

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.9.3 [ Operate each cooling tower fan for > [15] minutes. [ 31 days OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.9-3 Rev. 5.0

CREVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.10 Two CREVS trains shall be OPERABLE.

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

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6],

[During movement of [recently] irradiated fuel assemblies].

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVS train A.1 Restore CREVS train to 7 days inoperable for reasons OPERABLE status.

other than Condition B.

B. One or more CREVS B.1 Initiate action to implement Immediately trains inoperable due to mitigating actions.

inoperable CRE boundary in MODE 1, 2, AND 3, or 4.

B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

Babcock & Wilcox STS 3.7.10-1 Rev. 5.0

CREVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. [ Required Action and D.1 --------------NOTE---------------

associated Completion Place in emergency mode if Time of Condition A not automatic transfer to met [in MODE 5 or 6, or] emergency mode is during movement of inoperable.

[recently] irradiated fuel -------------------------------------

assemblies.

Place OPERABLE CREVS Immediately train in emergency mode.

OR D.2 Suspend movement of Immediately ]

[recently] irradiated fuel assemblies.

Babcock & Wilcox STS 3.7.10-2 Rev. 5.0

CREVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. [ Two CREVS trains E.1 Suspend movement of Immediately ]

inoperable [in MODE 5 [recently] irradiated fuel or 6, or] during assemblies.

movement of [recently]

irradiated fuel assemblies.

OR One or more CREVS trains inoperable due to an inoperable CRE boundary [in MODE 5 or 6, or] during movement of [recently] irradiated fuel assemblies.

F. Two CREVS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.10-3 Rev. 5.0

CREVS 3.7.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with the [Ventilation Filter Testing Program (VFTP)]. with the [VFTP]

SR 3.7.10.3 Verify [each CREVS train actuates] [or the control [ [18] months room isolates] on an actual or simulated actuation signal, except for dampers and valves that are OR locked, sealed, or otherwise secured in the actuated position. In accordance with the Surveillance Frequency Control Program ]

SR 3.7.10.4 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program SR 3.7.10.5 [ Verify the system makeup flow rate is [270] and [ [18] months

[330] cfm when supplying the the control room with outside air. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.10-4 Rev. 5.0

CREATCS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS)

LCO 3.7.11 Two CREATCS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, [5, and 6],

[During movement of [recently] irradiated fuel assemblies].

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREATCS train A.1 Restore CREATCS train to 30 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4. B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. [ Required Action and C.1 Place OPERABLE Immediately associated Completion CREATCS train in Time of Condition A not operation.

met during movement of

[recently] irradiated fuel OR assemblies.

C.2 Suspend movement of Immediately ]

[recently] irradiated fuel assemblies.

Babcock & Wilcox STS 3.7.11-1 Rev. 5.0

CREATCS 3.7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. [ Two CREATCS trains D.1 Suspend movement of Immediately ]

inoperable during [recently] irradiated fuel movement of [recently] assemblies.

irradiated fuel assemblies.

E. Two CREATCS trains E.1 Enter LCO 3.0.3. Immediately inoperable during MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CREATCS train has the capability to [ [18] months remove the assumed heat load.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.11-2 Rev. 5.0

EVS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Emergency Ventilation System (EVS)

LCO 3.7.12 Two EVS trains shall be OPERABLE.

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

The auxiliary building negative pressure area boundary may be opened intermittently under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One EVS train A.1 Restore EVS train to 7 days inoperable. OPERABLE status.

B. Two EVS trains B.1 Restore auxiliary building 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to negative pressure area inoperable auxiliary boundary to OPERABLE building negative status.

pressure area boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Babcock & Wilcox STS 3.7.12-1 Rev. 5.0

EVS 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each EVS train for 15 continuous minutes [ 31 days

[with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.7.12.2 Perform required EVS filter testing in accordance In accordance with the [Ventilation Filter Testing Program (VFTP)]. with the [VFTP]

SR 3.7.12.3 Verify each EVS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ]

SR 3.7.12.4 Verify one EVS train can maintain a pressure [ ] [ [18] months on a inches water gauge relative to atmospheric pressure STAGGERED during the [post accident] mode of operation at a TEST BASIS flow rate of [3000] cfm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.12-2 Rev. 5.0

EVS 3.7.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.12.5 [ Verify each EVS filter cooling bypass damper can [ [18] months be opened, except for dampers that are locked, sealed, or otherwise secured in the open position. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.12-3 Rev. 5.0

FSPVS 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Fuel Storage Pool Ventilation System (FSPVS)

LCO 3.7.13 [Two] FSPVS trains shall be OPERABLE.

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

The fuel building boundary may be opened intermittently under administrative control.

APPLICABILITY: [MODES 1, 2, 3, and 4,]

During movement of [recently] irradiated fuel assemblies in the fuel building.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One FSPVS train A.1 Restore FSPVS train to 7 days inoperable. OPERABLE status.

B. Two FSPVS trains B.1 Restore fuel building 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to boundary to OPERABLE inoperable fuel building status.

boundary in MODE 1, 2, 3, or 4.

Babcock & Wilcox STS 3.7.13-1 Rev. 5.0

FSPVS 3.7.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. [ Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ]

OR Two FSPVs trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

D. Required Action and D.1 Place OPERABLE FSPVS Immediately associated Completion train in operation.

Time of Condition A not met during movement of OR

[recently] irradiated fuel assemblies in the fuel D.2 Suspend movement of Immediately building. [recently] irradiated fuel assemblies in the fuel building.

E. Two FSPVS trains E.1 Suspend movement of Immediately inoperable during [recently] irradiated fuel movement of [recently] assemblies in the fuel irradiated fuel building.

assemblies in the fuel building.

Babcock & Wilcox STS 3.7.13-2 Rev. 5.0

FSPVS 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 [ Operate each FSPVS train for 15 continuous [ 31 days minutes [with heaters operating].

OR In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.13.2 [ Perform required FSPVS filter testing in In accordance accordance with the [Ventilation Filter Testing with the [VFTP] ]

Program (VFTP)].

SR 3.7.13.3 [ Verify each FSPVS train actuates on an actual or [ [18] months simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured OR in the actuated position.

In accordance with the Surveillance Frequency Control Program ] ]

SR 3.7.13.4 Verify one FSPVS train can maintain a pressure [ [18] months on a

[ ] inches water gauge with respect to STAGGERED atmospheric pressure during the [post accident] TEST BASIS mode of operation at a flow rate [3000] cfm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.13-3 Rev. 5.0

FSPVS 3.7.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.13.5 [ Verify each FSPVS filter bypass damper can be [ [18] months opened, except for dampers that are locked, sealed, or otherwise secured in the open position.. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.7.13-4 Rev. 5.0

Fuel Storage Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Fuel Storage Pool Water Level LCO 3.7.14 The fuel storage pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool water A.1 --------------NOTE---------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the fuel storage pool water level is 23 ft [ 7 days above the top of irradiated fuel assemblies seated in the storage racks. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.14-1 Rev. 5.0

[Spent Fuel Pool Boron Concentration]

3.7.15 3.7 PLANT SYSTEMS 3.7.15 [ Spent Fuel Pool Boron Concentration ]

LCO 3.7.15 The spent fuel pool boron concentration shall be [500] ppm.

APPLICABILITY: When fuel assemblies are stored in the spent fuel pool and a spent fuel pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron -------------------NOTE--------------------

concentration not within LCO 3.0.3 is not applicable.

limit. ------------------------------------------------

A.1 Suspend movement of fuel Immediately assemblies in the spent fuel pool.

AND A.2.1 Initiate action to restore Immediately spent fuel pool boron concentration to within limit.

OR A.2.2 Initiate action to perform a Immediately fuel storage pool verification.

Babcock & Wilcox STS 3.7.15-1 Rev. 5.0

[Spent Fuel Pool Boron Concentration]

3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel pool boron concentration is [ 7 days within limit.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.15-2 Rev. 5.0

[Spent Fuel Pool Storage]

3.7.16 3.7 PLANT SYSTEMS 3.7.16 [ Spent Fuel Pool Storage ]

LCO 3.7.16 The combination of initial enrichment and burnup of each fuel assembly stored in [Region 2] shall be within the acceptable [burnup domain] of Figure 3.7.16-1 or in accordance with Specification 4.3.1.1.

APPLICABILITY: Whenever any fuel assembly is stored in [Region 2] of the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 --------------NOTE---------------

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly from [Region 2].

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify by administrative means the initial enrichment Prior to storing the and burnup of the fuel assembly is in accordance fuel assembly in with Figure 3.7.16-1 or Specification 4.3.1.1. [Region 2]

Babcock & Wilcox STS 3.7.16-1 Rev. 5.0

[Spent Fuel Pool Storage]

3.7.16 Babcock & Wilcox STS 3.7.16-2 Rev. 5.0

Secondary Specific Activity 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Secondary Specific Activity LCO 3.7.17 The specific activity of the secondary coolant shall be [0.10] Ci/gm DOSE EQUIVALENT I-131.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify the specific activity of the secondary coolant [ [31] days is [0.10] Ci/gm DOSE EQUIVALENT I-131.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.17-1 Rev. 5.0

Steam Generator Level 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Steam Generator Level LCO 3.7.18 Water level of each steam generator shall be less than or equal to the maximum water level shown in Figure 3.7.18-1.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Water level in one or A.1 Restore steam generator 15 minutes more steam generators level to within limit.

greater than maximum water level in Figure 3.7.18-1.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify steam generator water level to be within [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.7.18-1 Rev. 5.0

Steam Generator Level 3.7.18 Babcock & Wilcox STS 3.7.18-2 Rev. 5.0

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System,

b. Two diesel generators (DGs) each capable of supplying one train of the onsite Class 1E AC Electrical Power Distribution System, and

[ c. Automatic load sequencers for Train A and Train B. ]

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

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One [required] offsite A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months circuit inoperable. OPERABLE [required]

offsite circuit. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND Babcock & Wilcox STS 3.8.1-1 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore [required] offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

B. One [required] DG B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE [required]

offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the inoperable discovery of DG inoperable when its Condition B redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE [24] hours DG(s) is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for [24] hours OPERABLE DG(s).

AND Babcock & Wilcox STS 3.8.1-2 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.4 Restore [required] DG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

C. Two [required] offsite C.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuits inoperable. inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required feature(s)

AND C.2 Restore one [required] 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months offsite circuit to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.8.1-3 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One [required] offsite -------------------NOTE--------------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems - Operating,"

when Condition D is entered with no One [required] DG AC power source to any train.

inoperable. ------------------------------------------------

D.1 Restore [required] offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

OR D.2 Restore [required] DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

E. Two [required] DGs E.1 Restore one [required] DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. to OPERABLE status.

Babcock & Wilcox STS 3.8.1-4 Rev. 5.0

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

REVIEWER'S NOTE----- F.1 Restore [required] [12] hours This Condition may be [automatic load sequencer]

deleted if the unit design is to OPERABLE status. [OR such that any sequencer failure mode will only affect In accordance with the ability of the associated the Risk Informed DG to power its respective Completion Time safety loads following a loss Program] ]

of offsite power independent of, or coincident with, a Design Basis Event.

F. [ One [required]

[automatic load sequencer] inoperable.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, AND C, D, E, or [F] not met.

G.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months H. Three or more [required] H.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

Babcock & Wilcox STS 3.8.1-5 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated [ 7 days power availability for each [required] offsite circuit.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

[ 2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met. ]

Verify each DG starts from standby conditions and [ 31 days achieves steady state voltage [3740] V and

[4580] V, and frequency [58.8] Hz and OR

[61.2] Hz.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-6 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3 ------------------------------NOTES-----------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and [ 31 days operates for 60 minutes at a load [4500] kW and

[5000] kW. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.4 Verify each day tank [and engine mounted tank] [ 31 days contains [220] gal of fuel oil.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-7 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 Check for and remove accumulated water from each [ [31] days day tank [and engine mounted tank].

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.6 Verify the fuel oil transfer system operates to [ [92] days

[automatically] transfer fuel oil from storage tank[s]

to the day tank [and engine mounted tank]. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.1.7 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and [ 184 days achieves:

OR

a. In [10] seconds, voltage [3740] V and frequency [58.8] Hz and In accordance with the

b. Steady state voltage [3740] V and [4580] V, Surveillance and frequency [58.8] Hz and [61.2] Hz. Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-8 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.8 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify [automatic [and] manual] transfer of AC power [ [18] months sources from the normal offsite circuit to each alternate [required] offsite circuit. OR In accordance with the Surveillance Frequency Control Program ] ]

Babcock & Wilcox STS 3.8.1-9 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ------------------------------NOTES-----------------------------

[ 1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor [0.9]. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable. ]

Verify each DG rejects a load greater than or equal [ [18] months to its associated single largest post-accident load, and: OR

a. Following load rejection, the frequency is In accordance

[63] Hz, with the Surveillance

b. Within [3] seconds following load rejection, the Frequency voltage is [3740] V and [4580] V, and Control Program ]

c. Within [3] seconds following load rejection, the frequency is [58.8] Hz and [61.2] Hz.

Babcock & Wilcox STS 3.8.1-10 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 ------------------------------NOTES-----------------------------

[1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor [0.9]. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable. ]

Verify each DG does not trip, and voltage is [ [18] months maintained [5000] V during and following a load rejection of [4500] kW and [5000] kW. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-11 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power [ [18] months signal:

OR

a. De-energization of emergency buses, In accordance

b. Load shedding from emergency buses, and with the Surveillance

c. DG auto-starts from standby condition and: Frequency Control Program ]

1. Energizes permanently connected loads in [10] seconds,

2. Energizes auto-connected shutdown load through [automatic load sequencer],

3. Maintains steady-state voltage [3740] V and [4580] V,

4. Maintains steady-state frequency

[58.8] Hz and [61.2] Hz, and

5. Supplies permanently connected and auto-connected shutdown loads for 5 minutes.

Babcock & Wilcox STS 3.8.1-12 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated [Engineered Safety [ [18] months Feature (ESF)] actuation signal each DG auto-starts from standby condition and: OR

a. In [12] seconds after auto-start and during In accordance tests, achieves voltage [3740] V and with the frequency [58.8] Hz, Surveillance Frequency

b. Achieves steady state voltage [3740] V Control and [4580] V and frequency [58.8] Hz and Program ] ]

[61.2] Hz,

c. Operates for 5 minutes,

d. Permanently connected loads remain energized from the offsite power system, and

e. Emergency loads are energized [or auto-connected through the automatic load sequencer] from the offsite power system.

Babcock & Wilcox STS 3.8.1-13 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR. ]

Verify each DG's noncritical automatic trips are [ [18] months bypassed on [actual or simulated loss of voltage signal on the emergency bus concurrent with an OR actual or simulated ESF actuation signal].

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-14 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

3. If performed with DC synchronized with offsite power, it shall be performed at a power factor

[0.9]. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each DG operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: [ [18] months

a. For [2] hours loaded [5250] kW and OR

[6000] kW and In accordance

b. For the remaining hours of the test loaded with the

[4500] kW and [5000] kW. Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-15 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated [2] hours loaded [4500] kW and [5000] kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves: [ [18] months

a. In [10] seconds, voltage [3740] V and OR frequency [58.8] Hz and In accordance

b. Steady state voltage [3740] V and [4580] V, with the and frequency [58.8] Hz and [61.2] Hz. Surveillance Frequency Control Program ]

SR 3.8.1.16 -------------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG: [ [18] months

a. Synchronizes with offsite power source while OR loaded with emergency loads upon a simulated restoration of offsite power, In accordance with the

b. Transfers loads to offsite power source, and Surveillance Frequency

c. Returns to ready-to-load operation. Control Program ]

Babcock & Wilcox STS 3.8.1-16 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify, with a DG operating in test mode and [ [18] months connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by: OR

a. Returning DG to ready-to-load operation and In accordance with the

[ b. Automatically energizing the emergency load Surveillance from offsite power. ] Frequency Control Program ] ]

SR 3.8.1.18 -------------------------------NOTE------------------------------

[ This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR. ]

Verify interval between each sequenced load block [ [18] months is within +/- [10% of design interval] for each emergency [and shutdown] load sequencer. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-17 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power [ [18] months signal in conjunction with an actual or simulated ESF actuation signal: OR

a. De-energization of emergency buses, In accordance with the

b. Load shedding from emergency buses, Surveillance Frequency

c. DG auto-starts from standby condition and: Control Program ]

1. Energizes permanently connected loads in [10] seconds,

2. Energizes auto-connected emergency loads through [load sequencer],

3. Achieves steady-state voltage [3740] V and [4580] V,

4. Achieves steady-state frequency

[58.8] Hz and [61.2] Hz, and

5. Supplies permanently connected and auto-connected emergency loads for

[5] minutes.

Babcock & Wilcox STS 3.8.1-18 Rev. 5.0

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube period.

Verify, when started simultaneously from standby [ 10 years condition, each DG achieves, in [10] seconds, voltage [3740] V and [4580] V, and frequency OR

[58.8] Hz and [61.2] Hz.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.1-19 Rev. 5.0

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown," and

b. One diesel generator (DG) capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6, During movement of [recently] irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite -------------------NOTE--------------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s) with no offsite power available inoperable.

OR Babcock & Wilcox STS 3.8.2-1 Rev. 5.0

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One required DG B.1 Suspend movement of Immediately inoperable. [recently] irradiated fuel assemblies.

AND B.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.3 Initiate action to restore Immediately required DG to OPERABLE status.

Babcock & Wilcox STS 3.8.2-2 Rev. 5.0

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ------------------------------NOTE------------------------------

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.9 through SR 3.8.1.11, SR 3.8.1.13 through SR 3.8.1.16, and

[SR 3.8.1.18].

For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.1, "AC Sources - Operating," with applicable except SR 3.8.1.8, SR 3.8.1.12, SR 3.8.1.17, SRs SR 3.8.1.19, and SR 3.8.1.20, are applicable.

Babcock & Wilcox STS 3.8.2-3 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel level less than a within limits.

[7] day supply and greater than a [6] day supply in storage tank.

B. One or more DGs with B.1 Restore lube oil inventory to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory less within limits.

than a [7] day supply and greater than a

[6] day supply.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limits.

particulates not within limit.

D. One or more DGs with D.1 Restore stored fuel oil 30 days new fuel oil properties properties to within limits.

not within limits.

Babcock & Wilcox STS 3.8.3-1 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

E. One or more DGs with E.1 Restore starting air receiver 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months starting air receiver pressure to [225] psig.

pressure < [225] psig and [125] psig.

F. Required Action and F.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

OR One or more DGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains a [7] day [ 31 days supply of fuel.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.3.2 Verify lube oil inventory is a [7] day supply. [ 31 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.3-2 Rev. 5.0

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is [ 31 days

[225] psig.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.3.5 Check for and remove accumulated water from each [ [31] days fuel oil storage tank.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.3-3 Rev. 5.0

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One [or two] battery A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger[s] on one voltage to greater than or subsystem inoperable. equal to the minimum established float voltage.

AND A.2 Verify battery float current Once per [12] hours

[2] amps.

AND A.3 Restore battery charger[s] [72] hours to OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

[ B. One [or two] batter[y][ies B.1 Restore batter[y][ies] to [2] hours on one subsystem] OPERABLE status.

inoperable. [OR In accordance with the Risk Informed Completion Time Program] ]

Babcock & Wilcox STS 3.8.4-1 Rev. 5.0

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One DC electrical power C.1 Restore DC electrical [2] hours subsystem inoperable power subsystem to for reasons other than OPERABLE status. [OR Condition A [or B].

In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time not met. AND D.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or [ 7 days equal to the minimum established float voltage.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.4-2 Rev. 5.0

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.2 Verify each battery charger supplies [400] amps at [ [18] months greater than or equal to the minimum established float voltage for [8] hours. OR OR In accordance with the Verify each battery charger can recharge the battery Surveillance to the fully charged state within [24] hours while Frequency supplying the largest combined demands of the Control Program ]

various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.3 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and [ [18] months maintain in OPERABLE status, the required emergency loads for the design duty cycle when OR subjected to a battery service test.

In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.4-3 Rev. 5.0

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 [DC electrical power subsystem shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown."]

[One DC electrical power subsystem shall be OPERABLE.]

REVIEWER'S NOTE-----------------------------------

The second option above applies for plants having a pre-ITS licensing basis (CTS) for electrical power requirements during shutdown conditions that required only one DC electrical power subsystem to be OPERABLE.

Action A and the bracketed optional wording in Condition B are also eliminated for this case. The first option above is adopted for plants that have a CTS requiring the same level of DC electrical power subsystem support as is required for power operating conditions.

APPLICABILITY: MODES 5 and 6, During movement of [recently] irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

[A. One [or two] battery A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger[s on one voltage to greater than or subsystem] inoperable. equal to the minimum established float voltage.

AND AND The redundant subsystem battery and A.2 Verify battery float current Once per [12] hours charger[s] OPERABLE. [2] amps.

AND Babcock & Wilcox STS 3.8.5-1 Rev. 5.0

DC Sources - Shutdown 3.8.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore battery charger[s] [72] hours ]

to OPERABLE status.

B. One [or more] required B.1 Declare affected required Immediately DC electrical power feature(s) inoperable.

subsystem[s] inoperable

[for reasons other than OR Condition A.

B.2.1 Suspend movement of Immediately OR [recently] irradiated fuel assemblies.

Required Action and associated Completion AND Time of Condition A not met]. B.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.2.3 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

Babcock & Wilcox STS 3.8.5-2 Rev. 5.0

DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------------------NOTE------------------------------

The following SRs are not required to be performed:

SR 3.8.4.2 and SR 3.8.4.3.

For DC sources required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 Babcock & Wilcox STS 3.8.5-3 Rev. 5.0

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for the Train A and Train B electrical power subsystem batteries shall be within limits.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One [or two] batter[y][ies A.1 Perform SR 3.8.4.1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on one subsystem] with one or more battery cells AND float voltage < [2.07] V.

A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months voltage [2.07] V.

B. One [or two] batter[y][ies B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on one subsystem] with float current > [2] amps. AND B.2 Restore battery float current [12] hours to [2] amps.

Babcock & Wilcox STS 3.8.6-1 Rev. 5.0

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ -------------------NOTE--------------------

Required Action C.2 Required Actions C.1 and C.2 are shall be completed if only applicable if electrolyte level electrolyte level was was below the top of plates.

below the top of plates. ------------------------------------------------

C.1 Restore electrolyte level to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months One [or two] batter[y][ies above top of plates.

on one subsystem] with one or more cells AND electrolyte level less than minimum C.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months established design leakage.

limits.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

D. One [or two] batter[y][ies D.1 Restore battery pilot cell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on one subsystem] with temperature to greater than pilot cell electrolyte or equal to minimum temperature less than established design limits.

minimum established design limits.

E. One or more batteries in E.1 Restore battery parameters 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months redundant subsystem for batteries in one with battery parameters subsystem to within limits.

not within limits.

Babcock & Wilcox STS 3.8.6-2 Rev. 5.0

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

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

OR One [or two] batter[y][ies on one subsystem] with one or more battery cells float voltage < [2.07] V and float current > [2]

amps.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 -------------------------------NOTE------------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is [2] amps. [ 7 days OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.6-3 Rev. 5.0

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify each battery pilot cell float voltage is [ 31 days

[2.07] V.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.6.3 Verify each battery connected cell electrolyte level is [ 31 days greater than or equal to minimum established design limits. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.8.6.4 Verify each battery pilot cell temperature is greater [ 31 days than or equal to minimum established design limits.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.6-4 Rev. 5.0

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell float voltage is [ 92 days

[2.07] V.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.6-5 Rev. 5.0

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.6 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is [80%] of the [ 60 months manufacturer's rating when subjected to a performance discharge test or a modified OR performance discharge test.

In accordance with the Surveillance Frequency Control Program ]

AND 12 months when battery shows degradation, or has reached

[85]% of the expected life with capacity < 100%

of manufacturer's rating AND 24 months when battery has reached [85]% of the expected life with capacity 100% of manufacturer's rating Babcock & Wilcox STS 3.8.6-6 Rev. 5.0

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE.

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

[ [One/two] inverter[s] may be disconnected from [its/their] associated DC bus for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform an equalizing charge on [its/their]

associated [common] battery provided:

a. The associated AC vital bus(es) [is/are] energized from [its/their]

[Class 1E constant voltage source transformers] [inverter using internal AC source] and

b. All other AC vital buses are energized from their associated OPERABLE inverters. ]

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One [required] inverter A.1 --------------NOTE---------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any vital bus de-energized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

[OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.8.7-1 Rev. 5.0

Inverters - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, [frequency,] and [ 7 days alignment to required AC vital buses.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.7-2 Rev. 5.0

Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 [Inverters shall be OPERABLE to support the onsite Class 1E AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown."]

[One] inverter[s] shall be OPERABLE.]

REVIEWER'S NOTE-----------------------------------

This second option above applies for plants having a pre-ITS licensing basis (CTS) for electrical power requirements during shutdown conditions that required only [one] inverter to be OPERABLE. The "[or more]"

optional wording in Condition A is also eliminated for this case. The first option above is adopted for plants that have a CTS requiring the same level of DC electrical power subsystem/inverter support as is required for power operating conditions.

APPLICABILITY: MODES 5 and 6, During movement of [recently] irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One [or more] [required] A.1 Declare affected required Immediately inverters inoperable. feature(s) inoperable.

OR A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND Babcock & Wilcox STS 3.8.8-1 Rev. 5.0

Inverters - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required inverters to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, [frequency,] and [ 7 days alignments to required AC vital buses.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.8-2 Rev. 5.0

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Train A and Train B AC, DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC A.1 --------------NOTE---------------

electrical power Enter applicable Conditions distribution subsystems and Required Actions of inoperable. LCO 3.0.4, "DC Sources -

Operating," for DC trains made inoperable by inoperable power distribution subsystems.

Restore AC electrical power 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months distribution subsystem(s) to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

B. One or more AC vital B.1 Restore AC vital bus 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months buses inoperable. subsystem(s) to OPERABLE status. [OR In accordance with the Risk Informed Completion Time Program]

Babcock & Wilcox STS 3.8.9-1 Rev. 5.0

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DC C.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power power distribution distribution subsystems subsystem(s) to [OR inoperable. OPERABLE status.

In accordance with the Risk Informed Completion Time Program]

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND D.2 --------------NOTE---------------

LCO 3.0.4.a is not applicable when entering MODE 4.

Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two or more electrical E.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

Babcock & Wilcox STS 3.8.9-2 Rev. 5.0

Distribution Systems - Operating 3.8.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to [ 7 days

[required] AC, DC, and AC vital bus electrical power distribution subsystems. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.9-3 Rev. 5.0

Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of [recently] irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC vital bus supported required electrical power feature(s) inoperable.

distribution subsystems inoperable. OR A.2.1 Suspend movement of Immediately

[recently] irradiated fuel assemblies.

AND Immediately A.2.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND Babcock & Wilcox STS 3.8.10-1 Rev. 5.0

Distribution Systems - Shutdown 3.8.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.3 Initiate actions to restore Immediately required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.4 Declare associated Immediately required decay heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to [ 7 days required AC, DC, and AC vital bus electrical power distribution subsystems. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.8.10-2 Rev. 5.0

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

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

Only applicable to the refueling canal and refueling cavity when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend positive reactivity Immediately within limit. additions.

AND A.2 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit [ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months specified in the COLR.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.1-1 Rev. 5.0

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One [required] source A.1 Suspend positive reactivity Immediately range neutron flux additions.

monitor inoperable.

AND A.2 ------------ NOTE -------------

Fuel assemblies, sources, and reactivity control components may be moved if necessary to restore an inoperable source range neutron flux monitor or to complete movement of a component to a safe condition.

Suspend movement of fuel, Immediately sources, and reactivity control components within the reactor vessel.

B. Two [required] source B.1 Initiate action to restore one Immediately range neutron flux source range neutron flux monitors inoperable. monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Babcock & Wilcox STS 3.9.2-1 Rev. 5.0

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.2.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. [ [18] months OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.2-2 Rev. 5.0

Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:

a. The equipment hatch closed and held in place by four bolts,

b. One door in each air lock is [capable of being] closed, and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. Closed by a manual or automatic isolation valve, blind flange, or equivalent or

2. Capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

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

Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

APPLICABILITY: During movement of [recently] irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Suspend movement of Immediately containment [recently] irradiated fuel penetrations not in assemblies within required status. containment.

Babcock & Wilcox STS 3.9.3-1 Rev. 5.0

Containment Penetrations 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment penetration is in [ 7 days the required status.

OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.3.2 -------------------------------NOTE------------------------------

Not required to be met for containment purge and exhaust valve(s) in penetrations closed to comply with LCO 3.9.3.c.1.

Verify each required containment purge and [ [18] months exhaust valve actuates to the isolation position on an actual or simulated actuation signal. OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.3-2 Rev. 5.0

DHR and Coolant Circulation - High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Decay Heat Removal (DHR) and Coolant Circulation - High Water Level LCO 3.9.4 One DHR loop shall be OPERABLE and in operation.

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

The required DHR loop may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1.

APPLICABILITY: MODE 6 with the water level 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DHR loop requirements A.1 Suspend operations that Immediately not met. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately DHR loop requirements.

AND Babcock & Wilcox STS 3.9.4-1 Rev. 5.0

DHR and Coolant Circulation - High Water Level 3.9.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.4 Close equipment hatch and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months secure with [four] bolts.

AND A.5 Close one door in each air 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months lock.

AND A.6.1 Close each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR A.6.2 Verify each penetration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one DHR loop is in operation and circulating [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of [2800] gpm.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.4-2 Rev. 5.0

DHR and Coolant Circulation - High Water Level 3.9.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.4.2 Verify required DHR loop locations susceptible to [ 31 days gas accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.4-3 Rev. 5.0

DHR and Coolant Circulation - Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Decay Heat Removal (DHR) and Coolant Circulation - Low Water Level LCO 3.9.5 Two DHR loops shall be OPERABLE, and one DHR loop shall be in operation.

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

1. All DHR pumps may be removed from operation for 15 minutes when switching from one train to another provided:

a. The core outlet temperature is maintained > 10 degrees F below saturation temperature,

b. No operations are permitted that would cause introduction of coolant into the Reactor Coolant System with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, and

c. No draining operations to further reduce RCS water volume are permitted.

2. One required DHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided that the other DHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than required A.1 Initiate action to restore Immediately number of DHR loops DHR loop to OPERABLE OPERABLE. status.

OR A.2 Initiate action to establish Immediately 23 ft of water above the top of reactor vessel flange.

Babcock & Wilcox STS 3.9.5-1 Rev. 5.0

DHR and Coolant Circulation - Low Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No DHR loop B.1 Suspend operations that Immediately OPERABLE or in would cause introduction of operation. coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore one Immediately DHR loop to OPERABLE status and to operation.

AND B.3 Close equipment hatch and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months secure with [four] bolts.

AND B.4 Close one door in each air 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months lock.

AND B.5.1 Close each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR Babcock & Wilcox STS 3.9.5-2 Rev. 5.0

DHR and Coolant Circulation - Low Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.5.2 Verify each penetration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one DHR loop is in operation. [ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.5.2 Verify correct breaker alignment and indicated [ 7 days power available to the required DHR pump that is not in operation. OR In accordance with the Surveillance Frequency Control Program ]

SR 3.9.5.3 Verify DHR loop locations susceptible to gas [ 31 days accumulation are sufficiently filled with water.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.5-3 Rev. 5.0

Refueling Canal Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Canal Water Level LCO 3.9.6 Refueling canal water level shall be maintained 23 ft above the top of the reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within limit. irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling canal water level is 23 ft above the [ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months top of reactor vessel flange.

OR In accordance with the Surveillance Frequency Control Program ]

Babcock & Wilcox STS 3.9.6-1 Rev. 5.0

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location

[ Text description of site location. ]

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain [177] fuel assemblies. Each assembly shall consist of a matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rods The reactor core shall contain [60] safety and regulating CONTROL ROD assemblies and [8] APSR assemblies. The material shall be [silver indium cadmium, boron carbide, or hafnium metal] as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent,

b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in [Section 9.1 of the FSAR],

[ c. A nominal [ ] inch center to center distance between fuel assemblies placed in [the high density fuel storage racks], ]

[ d. A nominal [ ] inch center to center distance between fuel assemblies placed in [the low density fuel storage racks], ]

Babcock & Wilcox STS 4.0-1 Rev. 5.0

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

[ e. New or partially spent fuel assemblies with a discharge burnup in the "acceptable range" of Figure [3.7.17-1] may be allowed unrestricted storage in [either] fuel storage rack(s), and ]

[ f. New or partially spent fuel assemblies with a discharge burnup in the "unacceptable range" of Figure [3.7.17-1] will be stored in compliance with the NRC approved [specific document containing the analytical methods, title, date, or specific configuration or figure]. ]

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent,

b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in [Section 9.1 of the FSAR],

c. keff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in [Section 9.1 of the FSAR], and

d. A nominal [21.125] inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation [138 ft 4 inches].

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than [1357] fuel assemblies [and six failed fuel containers].

Babcock & Wilcox STS 4.0-2 Rev. 5.0

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility

REVIEWER'S NOTE----------------------------------------

Titles for members of the unit staff shall be specified by use of an overall statement referencing an ANSI Standard acceptable to the NRC staff from which the titles were obtained, or an alternative title may be designated for this position.

Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special titles because of unique organizational structures.

The ANSI Standard shall be the same ANSI Standard referenced in Section 5.3, Unit Staff Qualifications. If alternative titles are used, all requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Unit staff titles shall be specified in the Final Safety Analysis Report or Quality Assurance Plan. Unit staff titles shall be maintained and revised using those procedures approved for modifying/revising the Final Safety Analysis Report or Quality Assurance Plan.

5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The [Shift Supervisor (SS)] shall be responsible for the control room command function. During any absence of the [SS] from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the [SS] from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

Babcock & Wilcox STS 5.1-1 Rev. 5.0

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the [FSAR/QA Plan],

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant,

c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety, and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

REVIEWER'S NOTE----------------------------------------

Two unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

Babcock & Wilcox STS 5.2-1 Rev. 5.0

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. A radiation protection technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The operations manager or assistant operations manager shall hold an SRO license.

e. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Babcock & Wilcox STS 5.2-2 Rev. 5.0

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications

REVIEWER'S NOTE-------------------------------------------------

Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of

[Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable to the NRC staff]. [The staff not covered by Regulatory Guide 1.8 shall meet or exceed the minimum qualifications of Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff].

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

Babcock & Wilcox STS 5.3-1 Rev. 5.0

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978,

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in [Generic Letter 82-33],

c. Quality assurance for effluent and environmental monitoring,

d. Fire Protection Program implementation, and

e. All programs specified in Specification 5.5.

Babcock & Wilcox STS 5.4-1 Rev. 5.0

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program, and

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification [5.6.1] and Specification [5.6.2].

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s) and

2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Shall become effective after the approval of the plant manager, and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

Babcock & Wilcox STS 5.5-1 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include

[Low Pressure Injection, Reactor Building Spray, Makeup and Purification, and Hydrogen Recombiner]. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements and

b. Integrated leak test requirements for each system at least once per [18]

months.

The provisions of SR 3.0.2 are applicable.

[ 5.5.3 Post Accident Sampling

REVIEWERS NOTE--------------------------------------------

This program may be eliminated based on the implementation of BAW-2387, "Justification for the Elimination of the Post Accident Sampling System From the Licensing Bases of Babcock and Wilcox-Designed Plants," the associated NRC Safety Evaluation, and implementation of the following commitments:

1. [Licensee] [verified it has or is making a regulatory commitment to develop]

contingency plans for obtaining and analyzing highly radioactive samples from the RCS, containment sump, and containment atmosphere. The contingency plans will be contained in [specified document or program] and implementation [is complete, will be completed with the implementation of the License amendment, or will be completed within x days (< 6 months) after the implementation of the License amendment]. Establishment and maintenance of contingency plans is considered a regulatory commitment.

2. The capability for classifying fuel damage events at the Alert level threshold

[has been or will be] established for [PLANT] at radioactivity levels of

[300 mCi/cc dose equivalent iodine]. This capability will be described in

[specified document or program] and implementation [is complete, will be completed with the implementation of the License amendment, or will be completed within x days (< 6 months) after the implementation of the License amendment]. The capability for classifying fuel damage events is considered a regulatory commitment.

3. [Licensee] [verified that it has or is making a regulatory commitment to develop] an ability to assess radioactive iodines released to offsite environs. The capability for monitoring iodines will be maintained within the

[specified document or program]. Implementation of this commitment [is complete, will be completed with the implementation of the License amendment, or will be completed within x days (< 6 months) after the Babcock & Wilcox STS 5.5-2 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Post Accident Sampling (continued) implementation of the License amendment]. The capability to monitor radioactive iodines is considered a regulatory commitment.

This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel,

b. Procedures for sampling and analysis, and

c. Provisions for maintenance of sampling and analysis equipment. ]

5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402,

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM,

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I,

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days, Babcock & Wilcox STS 5.5-3 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I,

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate 500 mrem/yr to the whole body and a dose rate 3000 mrem/yr to the skin and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate 1500 mrem/yr to any organ,

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I,

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I, and

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section [ ], cyclic and transient occurrences to ensure that components are maintained within the design limits.

[ 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in Babcock & Wilcox STS 5.5-4 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program (continued) accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR50.55a, except where an alternative, exemption, or relief has been authorized by the NRC.

The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies. ]

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendation of Regulatory position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

5.5.8 Steam Generator (SG) Program An SG Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the SG Program shall include the following:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging [or repair] of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected, plugged, [or repaired] to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service SG tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down), all anticipated transients included in the design specification and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the Babcock & Wilcox STS 5.5-5 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued) design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed [1 gpm] per SG [, except for specific types of degradation at specific locations as described in paragraph c of the SG Program].

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

c. Provisions for SG tube plugging [or repair] criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding

[40%] of the nominal tube wall thickness shall be plugged [or repaired].

REVIEWER'S NOTE----------------------------------------

Alternate tube plugging [or repair] criteria currently permitted by plant technical specifications are listed here. The description of these alternate tube plugging

[or repair] criteria should be equivalent to the descriptions in current technical specifications and should also include any allowed accident induced leakage rates for specific types of degradation at specific locations associated with tube plugging [or repair] criteria.

[The following alternate tube plugging [or repair] criteria may be applied as an alternative to the 40% depth based criteria:

1. . . .]

Babcock & Wilcox STS 5.5-6 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

REVIEWER'S NOTE----------------------------------------

The bracketed phrase in Paragraph d regarding exempt portions of the tube is only applicable to SGs with Alloy 600 thermally treated tubing.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet [except for any portions of the tube that are exempt from inspection by alternate repair criteria], and that may satisfy the applicable tube plugging [or repair]

criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

REVIEWER'S NOTE-------------------------------------

Plants are to include the appropriate Frequency (e.g., select the appropriate Item 2.) for their SG design. The first Item 2 is applicable to SGs with Alloy 600 mill annealed tubing. The second Item 2 is applicable to SGs with Alloy 600 thermally treated tubing. The third Item 2 is applicable to SGs with Alloy 690 thermally treated tubing.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 24 effective full power months, which defines the inspection period. ]

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 54 effective full power months, which defines the inspection period. If none of the SG tubes have ever experienced cracking other than in regions that are exempt from inspection by alternate repair criteria and the SG inspection was performed with enhanced probes, the inspection period may be extended to 72 effective full power months. Enhanced probes have a capability to detect flaws of any type equivalent to or better than array Babcock & Wilcox STS 5.5-7 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued) probe technology. The enhanced probes shall be used from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet except any portions of the tube that are exempt from inspection by alternate repair criteria. If there are regions where enhanced probes cannot be used, the tube inspection techniques shall be capable of detecting all forms of existing and potential degradation in that region.]

[2. After the first refueling outage following SG installation, inspect 100%

of the tubes in each SG at least every 96 effective full power months, which defines the inspection period. ]

REVIEWER'S NOTE----------------------------------------

The bracketed phrases in Paragraph 3 are only applicable to SGs with Alloy 600 thermally treated tubing.

3. If crack indications are found in any SG tube [excluding any region that is exempt from inspection by alternate repair criteria], then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall be at the next refueling outage [, but may be deferred to the following refueling outage if the 100% inspection of all SGs was performed with enhanced probes as described in paragraph d.2]. If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

[f. Provisions for SG tube repair methods. SG tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of SG tubes without removing the tube from service. For the purposes of these Specifications, tube plugging is not a repair. All acceptable tube repair methods are listed below.

REVIEWER'S NOTE----------------------------------------

Tube repair methods currently permitted by plant technical specifications are to be listed here. The description of these tube repair methods should be equivalent to the descriptions in current technical specifications. If there are no approved tube repair methods, this section should not be used.

1. . . .]

Babcock & Wilcox STS 5.5-8 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables,

b. Identification of the procedures used to measure the values of the critical variables,

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage,

d. Procedures for the recording and management of data,

e. Procedures defining corrective actions for all off control point chemistry conditions, and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.10 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in [Regulatory Guide], and in accordance with [Regulatory Guide 1.52, Revision 2, ASME N510-1989, and AG-1].

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < [0.05]% when tested in accordance with [Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below

[+/- 10%].

ESF Ventilation System Flowrate

[ ] [ ]

Babcock & Wilcox STS 5.5-9 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < [0.05]% when tested in accordance with [Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below [+/- 10%].

ESF Ventilation System Flowrate

[ ] [ ]

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in [Regulatory Guide 1.52, Revision 2], shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30C (86F) and the relative humidity specified below.

ESF Ventilation System Penetration RH Face Velocity

[ ] [See Reviewer's [See [See Reviewer's Note] Reviewer's Note]

Note]

REVIEWER'S NOTE----------------------------------------

The use of any standard other than ASTM D3803-1989 to test the charcoal sample may result in an overestimation of the capability of the charcoal to adsorb radioiodine. As a result, the ability of the charcoal filters to perform in a manner consistent with the licensing basis for the facility is indeterminate.

ASTM D 3803-1989 is a more stringent testing standard because it does not differentiate between used and new charcoal, it has a longer equilibration period performed at a temperature of 30C (86F) and a relative humidity (RH) of 95%

(or 70% RH with humidity control), and it has more stringent tolerances that improve repeatability of the test.

Allowable Penetration = [(100% - Methyl Iodide Efficiently

for Charcoal Credited in Licensee's Accident Analysis) / Safety Factor]

When ASTM D3803-1989 is used with 30C (86F) and 95% RH (or 70% RH with humidity control) is used, the staff will accept the following:

Safety factor 2 for systems with or without humidity control.

Humidity control can be provided by heaters or an NRC-approved analysis that demonstrates that the air entering the charcoal will be maintained less than or equal to 70 percent RH under worst-case design-basis conditions.

Babcock & Wilcox STS 5.5-10 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP) (continued)

If the system has a face velocity greater than 110 percent of 0.203 m/s (40 ft/min), the face velocity should be specified.

This value should be the efficiency that was incorporated in the licensee's accident analysis which was reviewed and approved by the staff in a safety evaluation.

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with [Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below [+/- 10%].

ESF Ventilation System Delta P Flowrate

[ ] [ ] [ ]

[ e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [+/- 10%] when tested in accordance with

[ASME N510-1989].

ESF Ventilation System Wattage ]

[ ] [ ]

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

Babcock & Wilcox STS 5.5-11 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals

[ 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the [Waste Gas Holdup System], [the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks]. The gaseous radioactivity quantities shall be determined following the methodology in [Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure"]. The liquid radwaste quantities shall be determined in accordance with [Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures"].

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the [Waste Gas Holdup System] and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion),

b. A surveillance program to ensure that the quantity of radioactivity contained in [each gas storage tank and fed into the offgas treatment system] is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of [an uncontrolled release of the tanks' contents], and

c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the [Liquid Radwaste Treatment System] is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies. ]

Babcock & Wilcox STS 5.5-12 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within limits,

2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. A clear and bright appearance with proper color or a water and sediment content within limits,

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a.,

above, are within limits for ASTM 2D fuel oil, and

c. Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program testing frequencies.

5.5.13 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

Babcock & Wilcox STS 5.5-13 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Technical Specifications (TS) Bases Control Program (continued)

d. Proposed changes that meet the criteria of 5.5.13b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.14 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected,

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists,

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities, and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable, or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable, or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

Babcock & Wilcox STS 5.5-14 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (SFDP) (continued)

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.15 Containment Leakage Rate Testing Program

[OPTION A]

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option A, as modified by approved exemptions.

b. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]%

of containment air weight per day.

c. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and < 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is [0.05 La] when tested at Pa.

b) For each door, leakage rate is [0.01 La] when pressurized to

[ 10 psig].

d. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

e. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

[OPTION B]

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exceptions:

Babcock & Wilcox STS 5.5-15 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.

2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC.

[ 3. ...]

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is [45 psig]. The containment design pressure is

[50 psig].

c. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]%

of containment air weight per day.

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is [0.05 La] when tested at Pa.

b) For each door, leakage rate is [0.01 La] when pressurized to

[ 10 psig].

e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

f. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

[OPTION A/B Combined]

Babcock & Wilcox STS 5.5-16 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. [Type A][Type B and C] test requirements are in accordance with 10 CFR 50, Appendix J, Option A, as modified by approved exemptions. [Type B and C][Type A]

test requirements are in accordance with 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. The 10 CFR 50, Appendix J, Option B test requirements shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exceptions:

1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.

2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC.

[ 3. ...]

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is [45 psig]. The containment design pressure is

[50 psig].

c. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]%

of containment air weight per day.

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and [< 0.75 La for Option A Type A tests] [ 0.75 La for Option B Type A tests].

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is [0.05 La] when tested at Pa.

Babcock & Wilcox STS 5.5-17 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued) b) For each door, leakage rate is [0.01 La] when pressurized to

[ 10 psig].

e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

f. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J 5.5.16 Battery Monitoring and Maintenance Program

REVIEWERS NOTE------------------------------------------

This program and the corresponding requirements in LCO 3.8.4, LCO 3.8.5, and LCO 3.8.6 require providing the information and verifications requested in the Notice of Availability for TSTF-500, Revision 2, "DC Electrical Rewrite - Update to TSTF-360," (76FR54510).

This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (Std) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a. The program allows the following RG 1.129, Revision 2 exceptions:

1. Battery temperature correction may be performed before or after conducting discharge tests.

2. RG 1.129, Regulatory Position 1, Subsection 2, "References," is not applicable to this program.

3. In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery."

4 In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

Babcock & Wilcox STS 5.5-18 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Battery Monitoring and Maintenance Program (continued)

5. In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

b. The program shall include the following provisions:

1. Actions to restore battery cells with float voltage < [2.13] V;

2. Actions to determine whether the float voltage of the remaining battery cells is [2.13] V when the float voltage of a battery cell has been found to be < [2.13] V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

5.5.17 Control Room Envelope (CRE) Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Air Cleanup System (CREACS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of [5 rem whole body or its equivalent to any part of the body] [5 rem total effective dose equivalent (TEDE)] for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Babcock & Wilcox STS 5.5-19 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.17 Control Room Envelope (CRE) Habitability Program (continued)

Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

[The following are exceptions to Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0:

1. ;and]

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREACS, operating at the flow rate required by the VFTP, at a Frequency of [18] months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the

[18] month assessment of the CRE boundary.

e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

[ 5.5.18 Setpoint Control Program

REVIEWER'S NOTE----------------------------------------

Adoption of a Setpoint Control Program requires changes to other technical specifications. See TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions," Option B, for guidance (Agencywide Documents Access and Management System (ADAMS) Accession Number ML101160026).

This program shall establish the requirements for ensuring that setpoints for automatic protective devices are initially within and remain within the assumptions of the applicable safety analyses, provides a means for processing changes to instrumentation setpoints, and identifies setpoint methodologies to ensure instrumentation will function as required. The program shall ensure that Babcock & Wilcox STS 5.5-20 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Setpoint Control Program (continued) testing of automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A) verifies that instrumentation will function as required.

a. The program shall list the Functions in the following specifications to which it applies:

1. LCO 3.3.1, Reactor Protection System (RPS) Instrumentation;

2. LCO 3.3.3, Reactor Protection System (RPS) - Reactor Trip Module (RTM);

3. LCO 3.3.4, CONTROL ROD Drive (CRD) Trip Devices;

4. LCO 3.3.5, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation;

5. LCO 3.3.8, Emergency Diesel Generator (EDG) Loss of Power Start (LOPS);

6. LCO 3.3.9, Source Range Neutron Flux;

7. LCO 3.3.10, Intermediate Range Neutron Flux;

8. LCO 3.3.11, Emergency Feedwater Initiation and Control (EFIC)

System Instrumentation;

9. LCO 3.3.15, Reactor Building (RB) Purge Isolation - High Radiation;

10. LCO 3.3.16, Control Room Isolation - High Radiation.

b. The program shall require the [Limiting Trip Setpoint (LTSP)], [Nominal Trip Setpoint (NTSP)], Allowable Value (AV), As-Found Tolerance (AFT), and As-Left Tolerance (ALT) (as applicable) of the Functions described in paragraph a. are calculated using the NRC approved setpoint methodology, as listed below. In addition, the program shall contain the value of the

[LTSP], [NTSP], AV, AFT, and ALT (as applicable) for each Function described in paragraph a. and shall identify the setpoint methodology used to calculate these values.

Reviewer's Note ---------------------------------------

List the NRC safety evaluation report by letter, date, and ADAMS accession number (if available) that approved the setpoint methodologies.

1. [Insert reference to NRC safety evaluation that approved the setpoint methodology.]

c. The program shall establish methods to ensure that Functions described in paragraph a. will function as required by verifying the as-left and as-found settings are consistent with those established by the setpoint methodology.

Babcock & Wilcox STS 5.5-21 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Setpoint Control Program (continued)

d. -----------------------------------REVIEWERS NOTE-------------------------------------

A license amendment request to implement a Setpoint Control Program must list the instrument functions to which the program requirements of paragraph d. will be applied. Paragraph d. shall apply to all Functions in the Reactor Protection System and Engineered Safety Feature Actuation System specifications unless one or more of the following exclusions apply:

1. Manual actuation circuits, automatic actuation logic circuits or to instrument functions that derive input from contacts which have no associated sensor or adjustable device, e.g., limit switches, breaker position switches, manual actuation switches, float switches, proximity detectors, etc. are excluded. In addition, those permissives and interlocks that derive input from a sensor or adjustable device that is tested as part of another TS function are excluded.

2. Settings associated with safety relief valves are excluded. The performance of these components is already controlled (i.e., trended with as-left and as-found limits) under the ASME Code for Operation and Maintenance of Nuclear Power Plants testing program.

3. Functions and Surveillance Requirements which test only digital components are normally excluded. There is no expected change in result between SR performances for these components. Where separate as-left and as-found tolerance is established for digital component SRs, the requirements would apply.

The program shall identify the Functions described in paragraph a. that are automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A). The [LTSP] of these Functions are Limiting Safety System Settings. These Functions shall be demonstrated to be functioning as required by applying the following requirements during CHANNEL CALIBRATIONS and CHANNEL FUNCTIONAL TESTS that verify the [LTSP or NTSP].

1 The as-found value of the instrument channel trip setting shall be compared with the previous as-left value or the specified [LTSP or NTSP].

2. If the as-found value of the instrument channel trip setting differs from the previous as-left value or the specified [LTSP or NTSP] by more than the pre-defined test acceptance criteria band (i.e., the specified AFT), then the instrument channel shall be evaluated before declaring the SR met and returning the instrument channel to service. This condition shall be entered in the plant corrective action program.

Babcock & Wilcox STS 5.5-22 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Setpoint Control Program (continued)

3. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

4. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the [LTSP or NTSP] at the completion of the surveillance test; otherwise, the channel is inoperable (setpoints may be more conservative than the [LTSP or NTSP] provided that the as-found and as-left tolerances apply to the actual setpoint used to confirm channel performance).

e. The program shall be specified in [insert the facility FSAR reference or the name of any document incorporated into the facility FSAR by reference]. ]

[ 5.5.19 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program. ]

[ 5.5.20 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:

a. The RICT may not exceed 30 days; Babcock & Wilcox STS 5.5-23 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.20 Risk Informed Completion Time Program (continued)

REVIEWER'S NOTE ----------------------------------

The Risk Informed Completion Time is only applicable in MODES supported by the licensee's PRA. Licensees applying the RICT Program to MODES other than MODES 1 and 2 must demonstrate that they have the capability to calculate a RICT in those MODES or that the risk indicated by their MODE 1 and 2 PRA model is bounding with respect to the lower MODE conditions.

b. A RICT may only be utilized in MODE 1, 2 [, and 3, and MODE 4 while relying on steam generators for heat removal];

c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.

1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.

2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.

d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:

1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or

2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.

Babcock & Wilcox STS 5.5-24 Rev. 5.0

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.20 Risk Informed Completion Time Program (continued)

e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods used to support this license amendment, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundaries require prior NRC approval. ]

[ 5.5.21 Spent Fuel Storage Rack Neutron Absorber Monitoring Program This Program provides controls for monitoring the condition of the neutron absorber used in the spent fuel pool storage racks to verify the Boron-10 areal density is consistent with the assumptions in the spent fuel pool criticality analysis. The program shall be in accordance with NEI 16-03-A, "Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools," Revision 0, May 2017 [, with the following exceptions:

1. . . . ].]

Babcock & Wilcox STS 5.5-25 Rev. 5.0

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radiological Environmental Operating Report

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

[ A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. ]

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979]. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.2 Radiological Effluent Release Report

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

[ A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. ]

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

Babcock & Wilcox STS 5.6-1 Rev. 5.0

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

[ The individual specifications that address core operating limits must be referenced here. ]

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

REVIEWERS NOTE----------------------------------------

Licensees that have received prior NRC approval to relocate Topical Report revision numbers and dates to licensee control need only list the number and title of the Topical Report, and the COLR will contain the complete identification for each of the Technical Specification referenced Topical Reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements). See NRC ADAMS Accession No: ML110660285 for details.

[ Identify the Topical Report(s) by number, title, date, and NRC staff approval document or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date. ]

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.4 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

[ The individual specifications that address RCS pressure and temperature limits must be referenced here. ]

Babcock & Wilcox STS 5.6-2 Rev. 5.0

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (continued)

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

REVIEWERS NOTE----------------------------------------

Licensees that have received prior NRC approval to relocate Topical Report revision numbers and dates to licensee control need only list the number and title of the Topical Report, and the PTLR will contain the complete identification for each of the Technical Specification referenced Topical Reports used to prepare the PTLR (i.e., report number, title, revision, date, and any supplements). See NRC ADAMS Accession No: ML110660285 for details.

[ Identify the NRC staff approval document by date. ]

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

REVIEWER'S NOTE----------------------------------------

The methodology for the calculation of the P-T limits for NRC approval should include the following provisions:

1. The methodology shall describe how the neutron fluence is calculated (reference new Regulatory Guide when issued).

2. The Reactor Vessel Material Surveillance Program shall comply with Appendix H to 10 CFR 50. The reactor vessel material irradiation surveillance specimen removal schedule shall be provided, along with how the specimen examinations shall be used to update the PTLR curves.

3. Low Temperature Overpressure Protection (LTOP) System lift setting limits for the Power Operated Relief Valves (PORVs), developed using NRC-approved methodologies may be included in the PTLR.

4. The adjusted reference temperature (ART) for each reactor beltline material shall be calculated, accounting for radiation embrittlement, in accordance with Regulatory Guide 1.99, Revision 2.

5. The limiting ART shall be incorporated into the calculation of the pressure and temperature limit curves in accordance with NUREG-0800 Standard Review Plan 5.3.2, Pressure-Temperature Limits.

6. The minimum temperature requirements of Appendix G to 10 CFR Part 50 shall be incorporated into the pressure and temperature limit curves.

Babcock & Wilcox STS 5.6-3 Rev. 5.0

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (continued)

7. Licensees who have removed two or more capsules should compare for each surveillance material the measured increase in reference temperature (RTNDT) to the predicted increase in RTNDT; where the predicted increase in RTNDT is based on the mean shift in RTNDT plus the two standard deviation value (2) specified in Regulatory Guide 1.99, Revision 2. If the measured value exceeds the predicted value (increase in RTNDT + 2), the licensee should provide a supplement to the PTLR to demonstrate how the results affect the approved methodology.

5.6.5 Post Accident Monitoring Report When a report is required by Condition B or F of LCO 3.3.[17], "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

[ 5.6.6 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken. ]

5.6.7 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9, "Steam Generator (SG) Program." The report shall include:

a. The scope of inspections performed on each SG;

b. The nondestructive examination techniques utilized for tubes with increased degradation susceptibility;

c. For each degradation mechanism found:

1. The nondestructive examination techniques utilized; Babcock & Wilcox STS 5.6-4 Rev. 5.0

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

2. The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported;

3. A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment;

4. The number of tubes plugged [or repaired] during the inspection outage; and

[5. The repair methods utilized and the number of tubes repaired by each repair method.]

d. An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results;

e. The number and percentage of tubes plugged [or repaired] to date, and the effective plugging percentage in each SG;

f. The results of any SG secondary side inspections; and

[g. Insert any plant-specific reporting requirements, if applicable.]

Babcock & Wilcox STS 5.6-5 Rev. 5.0

[High Radiation Area]

5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, or an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or Babcock & Wilcox STS 5.7-1 Rev. 5.0

[High Radiation Area]

5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee,

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

Babcock & Wilcox STS 5.7-2 Rev. 5.0

[High Radiation Area]

5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

d. Each individual or group entering such an area shall possess (one of the following:)

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

Babcock & Wilcox STS 5.7-3 Rev. 5.0

[High Radiation Area]

5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Babcock & Wilcox STS 5.7-4 Rev. 5.0

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (12-2010) (Assigned by NRC, Add Vol., Supp., Rev.,

NRCMD 3.7 and Addendum Numbers, if any.)

BIBLIOGRAPHIC DATA SHEET NUREG-1430, Volume 1, (See instructions on the reverse) Revision 5.0

2. TITLE AND SUBTITLE 3. DATE REPORT PUBLISHED Standard Technical Specifications, Babcok and Wilcox Plants: Specifications (Revision 5) MONTH YEAR September 2021

4. FIN OR GRANT NUMBER

5. AUTHOR(S) 6. TYPE OF REPORT Multiple Technical

7. PERIOD COVERED (Inclusive Dates)

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U. S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.)

Division of Safety Systems Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above", if contractor, provide NRC Division, Office or Region, U. S. Nuclear Regulatory Commission, and mailing address.)

Save as above

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B&W) plants. The changes reflected in Revision 5 result from the experience gained from plant operation using the improved STS and extensive public technical meetings and discussions among the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees and the Nuclear Steam Supply System (NSSS) Owners Groups.

The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.36) (60 FR 36953). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the practical extent, to Revision 5 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

Users may access the STS NUREGs in the PDF format at (http://www.nrc.gov). Users may print or download copies from the NRC Web site.

12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.) 13. AVAILABILITY STATEMENT NUREG-1430 unlimited Standard Technical Specifications 14. SECURITY CLASSIFICATION STS (This Page)

Babcock and Wilcox unclassified B&W (This Report) unclassified

15. NUMBER OF PAGES

16. PRICE NRC FORM 335 (12-2010)

NUREG-1430, Volume 1 Standard Technical Specifications September 2021 Revision 5 Babcock and Wilcox Plants: Specifications

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