Text

Appendix a, Technical Specifications - Part 1
	ML031150490
Person / Time
Site:	Peach Bottom
Issue date:	05/07/2003
From:	; Office of Nuclear Reactor Regulation
To:	;
	Solorio, D L, NRR/DRIP/RLEP, 415-1973
References
	Download: ML031150490 (169)
	v • d • e

APPENDIX A TECHNICAL SPECIFICATIONS FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 2

TABLE OF CONTENTS 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 SL 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 3.1.1 SHUTDOWN MARGIN (SDM) . . . . . . . . . . . . . . . 3.1-1 3.1.2 Reactivity Anomalies .. 3.1-5 3.1.3 Control Rod OPERABILITY .. 3.1-7 3.1.4 Control Rod Scram Times . . . . . . . . . . . . . . 3.1-12 3.1.5 Control Rod Scram Accumulators . . . . . . . . . . . 3.1-15 3.1.6 Rod Pattern Control . . . . . . . . . . . . . . . . 3.1-18 3.1.7 Standby Liquid Control (SLC) System .. . . . . . . 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves . 3.1-26 3.2 POWER DISTRIBUTION LIMITS . . . . . 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) . . . . . . . . . . . . . . . . . . . . 3.2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) . . . . . . . . 3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) . . . . . . . . 3.2-4 3.3 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation . 3.3-1 3.3.1.2 Wide Range Neutron Monitor (WRNM) Instrumentation . 3.3-10 3.3.2.1 Control Rod Block Instrumentation .3.3-16 3.3.2.2 Feedwater and Main Turbi-ne High Water L-evel Trip Instrumentation .n.u.t. - . . .. . . . . 3.3-22 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation . . . 3.3-24 3.3.3.2 Remote Shutdown System . . . . . . . . . . . . . . . 3.3-27 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation . . . . . . 3.3-29 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation . . . . . 3.3-31a thru 3.3-31c 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation 3.3-32 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation . . . . . . . . . . . . . . . . . 3.3-44 3.3.6.1 Primary Containment Isolation Instrumentation . . 3.3-48 3.3.6.2 Secondary Containment Isolation Instrumentation . 3.3-55 3.3.7.1 Main Control Room Emergency Ventilation (MCREV)

System Instrumentation . . . . . . . . . . . . . 3.3-59 3.3.8.1 Loss of Power (LOP) Instrumentation . . . . . . . . 3.3-61 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring . . . . . . . . . . . . . . . . . . . . . 3.3-66 (continued)

PBAPS UN IT 2 i Amendment No. I. 225

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . . 3.4-1 3.4.1 Recirculation Loops Operating . . . . . . . . . . . 3.4-1 3.4.2 Jet Pumps . . . . . . . . . . . . . . . . . . . . . 3.4-6 3.4.3 Safety Relief Valves (SRVs) and Safety Valves (SVs) 3.4-8 3.4.4 RCS Operational LEAKAGE . . . . . . . . . . . . . . 3.4-10 3.4.5 RCS Leakage Detection Instrumentation . . . . . . . 3.4-12 3.4.6 RCS Specific Activity . .3.4-14 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown . . . . 3.4-16 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown . . . . 3.4-19 3.4.9 RCS Pressure and Temperature (P/T) Limits. 3.4-21 3.4.10 Reactor Steam Dome Pressure . . . . . . . . . . . . 3.4-28 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM . . . . . . . . . . . . 3.5-1 3.5.1 ECCS-Operating . . . . . . . . . . . . . . . . . . 3.5-1 3.5.2 ECCS-Shutdown . . . . . . . . . . . . . . . . . . . 3.5-8 3.5.3 RCIC System ..... . . ....... . . . . . . 3.5-12 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . . . 3.6-1 3.6.1.1 Primary Containment .... . ...... . . . . . 3.6-1 3.6.1.2 Primary Containment Air Lock . . . .3.6-3 3.6.1.3 Primary Containment Isolation Valve (PCIVs) s . . 3.6-8 3.6.1.4 Drywell Air Temperature . . . . .3.6-17 3.6.1.5 Reactor Building-to-Suppression Chamber Vacuum Breakers . . . . . . . . . . . . . . . . . . . . 3.6-18 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers . . . 3.6-21 3.6.2.1 Suppression Pool Average Temperature . . . . . . . . 3.6-23 3.6.2.2 Suppression Pool Water Level . . . . . . . . . . . . 3.6-26 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .. . 3.6-27 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray . 3.6-29 3.6.3.1 Containment Atmospheric Dilution (CAD) System . . . 3.6-31 3.6.3.2 Primary Containment Oxygen Concentration . . . . . . 3.6-33 3.6.4.1 Secondary Containment .. 3.6-34 3.6.4.2 Secondary Containment Isolation Valvesi(SCIVs) . 3.6-36 3.6.4.3 Standby Gas Treatment (SGT) System . . . . . . . . . 3.6-40 3.7 PLANT SYSTEMS . . . . . . 3.7-1 3.7.1 High Pressure Service Water (HPSW) System. 3.7-1 3.7.2 Emergency Service Water (ESW) System and Normal Heat Sink . . . . . . . . . . . . . . . . . . . 3.7-3 3.7.3 Emergency Heat Sink ..... . 3.7-5 3.7.4 Main Control Room Emergency Ventilation (MCREV) 3.7-5 System . . .3.7-7 3.7.5 Main Condenser Offgas. . . . . . . . . . . . . . . 3.7-10 (continued)

PBAPS UNIT 2 ii Revision No. 0

TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.6 Main Turbine Bypass System . . . . . . . . . . . . . 3.7-12 3.7.7 Spent Fuel Storage Pool Water Level . . . . . . . . 3.7-14 3.8 ELECTRICAL POWER SYSTEMS .... . ...... . . . . . 3.8-1 3.8.1 AC Sources-Operating . . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources-Shutdown .... .. 3.8-20 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . 3.8-25 3.8.4 DC Sources-Operating . ........... .. 3.8-28 3.8.5 DC Sources-Shutdown .... . ...... . . . . . 3.8-34 3.8.6 Battery Cell Parameters . . . .. . . . . . . . .. 3.8-37 3.8.7 Distribution Systems-Operating . . .. . . . . .. 3.8-41 3.8.8 Distribution Systems-Shutdown . . .. . . . . . .. 3.8-44 3.9 REFUELING OPERATIONS ..... . ....... . . . . . 3.9-1 3.9.1 Refueling Equipment Interlocks . . . . . . . . . . . 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock . . . . . . . 3.9-3 3.9.3 Control Rod Position . . . . . . . . . . . . . . . . 3.9-5 3.9.4 Control Rod Position Indication . . . . . . . . . . 3.9-6 3.9.5 Control Rod OPERABILITY-Refueling . .3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level . .3.9-9 3.9.7 Residual Heat Removal (RHR)-High Water Level . 3.9-10 3.9.8 Residual Heat Removal (RHR)-Low Water Level . . . . 3.9-13 3.10 SPECIAL OPERATIONS 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation. 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing . . . . . . . 3.10-4 3.10.3 Single Control Rod Withdrawal-Hot Shutdown . . . . 3.10-6 3.10.4 Single Control Rod Withdrawal-Cold Shutdown . . . . 3.10-9 3.10.5 Single Control Rod Drive (CRD)

Removal-Refueling . . . . . . . . . . . . . . . 3.10-13 3.10.6 Multiple Control Rod Withdrawal-Refueling . . . . . 3.10-16 3.10.7 Control Rod Testing-Operating . . . . . . . . . . . 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling . . . . . . . 3.10-20 4.0 DESIGN FEATURES .4.0-1 4.1 Site 4.0-1 4.2 Reactor Core .4.0-1 4.3 Fuel Storage .4.0-2 5.0 ADMINISTRATIVE CONTROLS .5.0-1 5.1 Responsibility . . . . . . . . . . . . . . . . . . . . . 5.0-1 5.2 Organization . . . 5.0-2 5.3 Unit Staff Qualifications. 5.0-5 5.4 Procedures . . . . 5.0-6 5.5 Programs and Manuals ... . . . . . . . . . . . . . . 5.0-7 5.6 Reporting Requirements .5.0-18 5.7 High Radiation Areas ...... ................................. 5.0-22 PBAPS UNIT 2 ii i Revision No. 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.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE planar height and is equal to the sum of the (APLHGR) heat generation rate per unit length of fuel rod for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

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 the entire channel,-including the required sensor, alarm, display, and trip functions, and shall include 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 so that the entire channel is calibrated.

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.

(continued)

PBAPS UNIT 2 1 .1-1 Amendment No. 210

Definitions 1.1 1.1 Definitions (continued)

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, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of wide range neutron monitors, local power range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."

(continued)

PBAPS UNIT 2 1.1-2 Amendment No. f*5,222

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial signal generation by (EOC-RPT) SYSTEM RESPONSE the associated turbine stop valve limit switch or TIME from when the turbine control valve hydraulic oil control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. 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.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the

.I operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR. shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

(continued)

PBAPS UNIT 2 1.1-3 Amendment No.9991,ff-A 225

Definitions 1.1 1.1 Definitions (continued)

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average N

reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE-OPERABILITY A system, subsystem, division, 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, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Section 13.5, Startup and Power Test Program of the UFSAR; (continued)

PBAPS UNIT 2 1.1-4 Amendment No. 210

Definitions 1.1 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 MWt.

I REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval (RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68'F; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

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.

(continued)

PBAPS UNIT 2 1.1-5 Amendment No. 247

Definitions 1.1 1.1 Definitions (continued)

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80%

of the turbine bypass capacity is established; and

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

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.

PBAPS UNIT 2 1.1-6 Amendment No. 210

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

MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE (OF)

I Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot NA Standby 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown s 212 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

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

PBAPS UNIT 2 1.1-7 Amendment No. 210

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 ARE 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 indentions 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.

(continued)

PBAPS UNIT 2 1.2-1 Amendment No. 210

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

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.

(continued)

PBAPS UNIT-2 1.2-2 Amendment No. 210

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

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.

PBAPS UNIT 2 1.2-3 Amendment No. 210

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 Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of 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. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and J, 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 associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, 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.

(continued)

PBAPS UNIT 2 1 .3-1 Amendment No. 210

Completion Times Completion Times 1.3 1.3 Completion Times DESCRIPTION However, when a subsequent division, subsystem, component, (continued) 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 extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, 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.

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 . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in Example 1.3-3 may not be extended.

(continued)

PBAPS UNIT 2 1.3-2 Amendment No. 210

Completion Times 1.3 II 1.3 Completion Times (continued)

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 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 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

PBAPS UNIT 2 1.3-3 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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, Condition 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.

(continued)

PBAPS UNIT 2 1.3-4 Amendment No. 210

Completion Times Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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.

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.

(continued)

PBAPS UNIT 2 1.3-5 Amendment No. 210

Completion Times 123 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X subsystem subsystem to AND inoperable. OPERABLE status.

10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y subsystem subsystem to AND inoperable. OPERABLE status.

10 days from discovery of failure to meet the LCO C. One C.1 Restore 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function X Function X subsystem subsystem to inoperable. OPERABLE status.

AND OR One C.2 Restore 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Function Y Function Y subsystem subsystem to inoperable. OPERABLE status.

(continued)

PBAPS UNIT 2 1.3-6 Amendment No. 210

Completion Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

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

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be 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.

The separate Completion Time modified by the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

(continued)

PBAPS UNIT 2 1.3-7 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

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

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

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.

(continued)

PBAPS UNIT 2 1.3-8 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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.

(continued)

PBAPS UNIT 2 1.3-9 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

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.

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 Once per inoperable. SR 3.x.x.x. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR A.2 Place channel in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months trip.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion Time not met.

(continued)

PBAPS UNIT 2 1 .3-10 Amendment No. 210

Completion Times Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once pert 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.

(continued)

PBAPS UNIT 2 1 .3-11 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

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 inoperable. isolated. 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. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

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 (continued)

PBAPS UNIT 2 1.3-12 Amendment No. 210

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) 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.

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

PBAPS UNIT 2 1.3-13 Amendment No. 210

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 Limiting Condition for Operation (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, 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. Example 1.4-4 discusses these special situations.

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 performed 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 (continued)

PBAPS UNIT 2 1 .4-1 Amendment No. 210

Frequency Frequency 1.4 1.4 Frequency DESCRIPTION criteria. SR 3.0.4 restrictions would not apply if both the (continued) following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

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.

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 interval specified in the 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 Examples 1.4-3 and 1.4-4), then SR 3.0.3 becomes applicable.

(continued)

PBAPS UNIT 2 1.4-2 Amendment No. 210

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

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, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

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 2 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 2 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.

(continued)

PBAPS UNIT 2 1.4-3 Amendment No. 210

Frequency Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

"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.

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 2 25% RTP.

Perform channel adjustment. 7 days i

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 within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), 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 with power 2 25% RTP.

(continued)

PBAPS UNIT 2 1.4-4 Amendment No. 210

Frequency Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

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, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

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.

PBAPS UNIT 2 1.4-5 Amendment No. 210

SLs SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be

25% RTP.

2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 2 10% rated core flow:

MCPR shall be 2 1.07 for two recirculation loop operation or 2 1.09 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be

1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the Plant Manager and the Vice President-Peach Bottom Atomic Power Station.

(continued)

PBAPS UN IT 2 2 .0 -1 Amendment No. ,246

SLs 2.0 2.0 SLs 2.2 SL Violations (continued) 2.2.4 Within 30 days, a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the Plant Manager, and the Vice President-Peach Bottom Atomic Power Station.

2.2.5 Operation of the unit shall not be resumed until authorized by the NRC.

PBAPS UNIT 2 2.0-2 Amendment No. 210

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 and LCO 3.0.7.

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 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 4 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, and 3.

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

(continued)

PBAPS UNIT 2 3 .0-1 Amendment No. 210

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 Exceptions to this Specification are stated in the (continued) individual Specifications. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.

LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.

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, additional evaluations and limitations may be required in accordance with Specification 5.5.11, 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.

(continued)

PBAPS UNIT 2 3.0-2 Amendment No. 210

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

LCO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

PBAPS UNIT 2 3.0-3 Amendment No. 210

SR Applicability 3.0 Go 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. 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.

(continued)

PBAPS UNIT 2 3.0 -4 Amendment No. 910, 243

SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. 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.

SR 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.

I PBAPS UNIT 2 3.0-5 Amendment No. 210

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

LCO 3.1.1 SDM shall be:

a. ? 0.38% &k/k, with the highest worth control rod analytically determined; or

b. 2 0.28% Ak/k, with the highest worth control rod determined by test.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits A.1 Restore SDM to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in MODE 1 or 2. limits.

B. Required Action and B.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 not met.

C. SDM not within limits C.1 Initiate action to Immediately in MODE 3. fully insert all insertable control rods.

D. SDM not within limits D.1 Initiate action to Immediately in MODE 4. fully insert all insertable control rods.

AND (continued)

PBAPS UNIT 2 3.1-1 Amendment No. 210

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.2 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

AND D.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore one standby gas treatment (SGT) subsystem for Unit 2 to OPERABLE status.

AND D.4 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore isolation capability in each required secondary containment penetration flow path not isolated.

E. SDM not within limits E.1 Suspend CORE Immediately in MODE 5. ALTERATIONS except for control rod insertion and fuel assembly removal.

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

AND (continued)

PBAPS UNIT 2 3.1-2 Amendment No. 210

SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

AND E.4 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore one SGT subsystem for Unit 2 to OPERABLE status.

AND E.5 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore isolation capability in each required secondary containment penetration flow path not isolated.

PBAPS UNIT 2 3.1-3 Amendment No. 210

SDM 3.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is: Prior to each in vessel fuel

a. 2 0.38% Ak/k with the highest worth movement during control rod analytically determined; fuel loading or sequence

b. 2 0.28% Ak/k with the highest worth AND control rod determined by test.

Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel or control rod replacement PBAPS UNIT 2 3.1-4 Amendment No. 210

Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored rod density and the predicted rod density shall be within +/- 1% &k/k.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity A.1 Restore core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months difference not within reactivity difference limit. to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

PBAPS UNIT 2 3.1-5 Amendment No. 210

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1*

SR 3.1.2.1 Verify core reactivity difference between Once within the monitored rod density and the predicted 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after rod density is within +/- 1% Ak/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/T thereafter during operations in MODE 1

1. _____________________________

PBAPS UNIT 2 3.1-6 Amendment No. 210

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control ------------NOTE-------------

rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, 'Control Rod Block Instrumentation," if required, to allow continued operation.

A.1 Verify stuck control Immediately rod separation criteria are met.

AND A.2 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND (continued)

PBAPS UNIT 2 3.1-7 Amendment No. 210

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from and SR 3.1.3.3 for discovery of each withdrawn Condition A OPERABLE control rod. concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM AND A.4 Perform SR 3.1.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two or more withdrawn B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods stuck.

C. One or more control C.1 -------- NOTE---------

rods inoperable for RWM may be bypassed reasons other than as allowed by Condition A or B. LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

AND C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

(continued)

PBAPS UNIT 2 3.1-8 Amendment No. 210

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. --------- NOTE--------- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when with BPWS.

THERMAL POWER

> 10% RTP. OR D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Two or more inoperable to OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.

E. Required Action and E.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, C, or D not met.

OR Nine or more control rods inoperable.

PBAPS UNIT 2 3.1-9 Amendment No. 210

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 -------------------NOTE--------------------

Not required to be performed until 7 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each fully withdrawn control rod at 7 days least one notch.

SR 3.1.3.3 -------------------NOTE--------------------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each partially withdrawn control rod 31 days at least one notch.

SR 3.1.3.4 Verify each control rod scram time from In accordance fully withdrawn to notch position 06 is with c 7 seconds. SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

PBAPS UNIT 2 3.1-10 Amendment No. 210

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY t

SR 3.1.3.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling

.1 ___________________________

PBAPS UNIT 2 3. 1-11 Amendment No. 210

Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 13 OPERABLE control rods shall be "slow,"

in accordance with Table 3.1.4-1; and

b. No more than 2 OPERABLE control rods that are 'slow' shall occupy adjacent locations.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS

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

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure 2 800 psig. 40% RTP after each refueling AND (continued)

PBAPS UNIT-2 3.1-12 Amendment No. 210

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 (continued) Prior to exceeding 40% RTP after each reactor shutdown 2 120 days SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure > 800 psig. MODE I SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure > 800 psig. 40% RTP after work on control rod or CRD System that could affect scram time AND Prior to exceeding 40%

RTP after fuel movement within the reactor pressure vessel PBAPS UNIT 2 3.1-13 Amendment No. 210

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

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

1. OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 06. These control rods are inoperable, in accordance with SR 3.1.3.4, and are not considered "slow."

SCRAM TIMES WHEN REACTOR STEAM DOME PRESSURE

? 800 psig(a)(g)

NOTCH POSITION (seconds) 46 0.44 36 1.08 26 1.83 06 3.35 (a) Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.

(b) When reactor steam dome pressure is < 800 psig, established scram time limits apply.

Q_ ~

PBAPS UNIT 2 3.1-14 Amendment No. 210

Control Rod Scram Accumulators 3.1.5 II 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 Each control rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each control rod scram accumulator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 -------- NOTE---------

accumulator inoperable Only applicable if with reactor steam the associated dome pressure control rod scram 2 900 psig. time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod scram time "slow.,

OR A.2 Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod inoperable.

(continued)

PBAPS UNIT 2 3.1-15 Amendment No. 210

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME B. Two or more control B.1 Restore charging 20 minutes from rod scram accumulators water header pressure discovery of inoperable with to 2 940 psig. Condition B reactor steam dome concurrent with pressure 2 900 psig. charging water header pressure

< 940 psig B.2.1 -------- NOTE---------

Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during

-the last scram time Surveillance.

Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod scram time

'slow..

OR B.2.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

(continued)

PBAPS UNIT 2 3.1-16 Amendment No.i-Zf 211

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable with inoperable charging water reactor steam dome accumulators are header pressure pressure < 900 psig. fully inserted. < 940 psig ANQ C.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

D. Required Action B.1 or D.1 - --- NOTE---------

C.1 and associated Not applicable if all Completion Time not inoperable control met. rod scram accumulators are associated with fully inserted control rods.

Place the reactor Immediately mode switch in the shutdown position.

SURVEILLANCEREQUIREMENTS ________

SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is - 940 psig.

I PBAPS UNIT 2 3.1-17 Amendment No.¢f0.

211

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES 1 and 2 with THERMAL POWER s 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 -------- NOTE---------

control rods not in Rod worth minimizer compliance with BPWS. (RWM) may be bypassed as allowed by LCO 3.3.2.1, 'Control Rod Block Instrumentation.m Move associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) to correct position.

OR A.2 Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) inoperable.

(continued)

PBAPS UNIT 2 ' ~-' 3.1-18 Amendment No. 210

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE B.1 ---- NOTE---------

control rods not in RWM may be bypassed compliance with BPWS. as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with BPWS.

PBAPS UNIT-2 3. 1-19 Amendment No. 210

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of boron A.1 Verify the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months in solution > 9.82% concentration and weight. temperature of boron AND in solution and pump suction piping Once per temperature are 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within the limits of thereafter Figure 3.1.7-1.

AND A.2 Restore concentration 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of boron in solution to s 9.82% weight. AND 10 days from discovery of failure to meet the LCO B. One SLC subsystem B.1 Restore SLC subsystem 7 days inoperable for reasons to OPERABLE status.

other than AND Condition A.

10 days from discovery of failure to meet the LCO (continued)

PBAPS UNIT 2- 3.1-20 Amendment No. 210

SLC System 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to OPERABLE other than status.

Condition A.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS__

SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium pentaborate solution 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the SLC tank is - 46%.

SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is 2 530F.

SR 3.1.7.3 Verify temperature of pump suction piping 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is - 53F.

SR 3.1.7.4 Verify continuity of explosive charge. 31 days (continued)

PBAPS UNIT 2 3.1-21 Amendment No. 210

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.5 Verify the concentration of boron in 31 days solution is s 9.82% weight and within the limits of Table 3.1.7-1. AD Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within limits SR 3.1.7.6 Verify each SLC subsystem manual and power 31 days operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify the quantity of B-10 stored in the 31 days SLC tank is Z 162.7 lbm.

SR 3.1.7.8 Verify each pump develops a flow rate In accordance Z 43.0 gpm at a discharge pressure with the

> 1255 psig. Inservice Testing Program (continued)

PBAPS UNIT 2 3.1-22 Amendment No. 210

SLC System 3.1.7

., SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.9 Verify flow through one SLC subsystem from 24 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.10 Verify sodium pentaborate atom percent B-10 Once within 8 enrichment is within the limits of hours after Table 3.1.7-1. addition to SLC tank PBAPS UNIT 2 3.1-23 Amendment No. 210

SLC System 3.1.7 Table 3.1.7-1 (page 1 of 1)

Standby Liquid Control System Boron Concentration, Pump Flow Rate, and Boron Enrichment Limits The combination of SLC System boron concentration, pump flow rate, and boron enrichment shall be in accordance with the following equation:

C Q E x x ;t 1 13% weight 86 gpm 19.8% atom where, C = % weight sodium pentaborate solution concentration, Q = Pump flow rate (gpm) at a discharge pressure of ; 1255 psig, and E = Boron-10 enrichment (% atom Boron-10).

PBAPS UNIT 2 3.1-24 Amendment No. 210

SLC System 3.1.7 1100 I -j J- - (24 % jll O 1 -I I - - -I-90.0 AC EPT BLE U

L0 U

LL r

W.01 L-a 7 0.0 -- - -

QC U.-

U.

601 - - -I I

- -F I 9.0 10.0

.0(9.82%.

11.0 54.

20

i i i~

13.0 14.0 15.0 16.0 17. 18.0 19.0 20.0 21.0 220 23.0 24.0 CONCENTRATION (Weight Percent Pentaborate Solution)

Figure 3.1.7-1 (page 1 of 1)

Sodium Pentaborate Solution Temperature Versus Concentration Requirements PBAPS UNIT 2 3.1-25 Amendment No. 210

SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each SDV vent and drain line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Restore valve to 7 days or drain lines with OPERABLE status.

one valve inoperable.

B. One or more SDV vent B.1 -------- NOTE---------

or drain lines with An isolated line may both valves be unisolated under inoperable. administrative control to allow draining and venting of the SDV.

Isolate the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated line.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

PBAPS UNIT 2 3.1-26 Amendment No. 210

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4

SR 3.1.8.1 -------------------NOTE--------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2 or SR 3.3.1.1.9 for Function 13 of Table 3.3.1.1-1.

Verify each SDV vent and drain valve is 31 days open.

SR 3.1.8.2 Cycle each SDV vent and drain valve to the 92 days fully closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve closes 24 months in < 15 seconds after receipt of an actual or simulated scram signal.

PBAPS UNIT 2 3.1-27 Amendment No. 210

APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER 2 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after x 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter PBAPS UNIT 2 3.2-1 Amendment No. 210

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER 2 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 2 3.2-2 Amendment No. 210

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS (continued) I.

SURVEILLANCE FREQUENCY 4.

SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.1 AND Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.2 PBAPS UNIT 2 3.2-3 Amendment No. 210

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER ; 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. within limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to Once within the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter PBAPS UNIT 2 3.2-4 Amendment No. 210

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable. trip.

OR A.2 --------NOTE--------- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not applicable for Functions 2.a, 2.b, 2.c, or 2.d.

Place associated trip system in trip.

B. ---------NOTE--------- B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Not applicable for trip system in trip.

Functions 2.a, 2.b, 2.c, or 2.d. OR One or more Functions B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more in trip.

required channels inoperable in both trip systems.

(continued)

PBAPS UNIT 2 3.3-1 Amendment No. 21-O,4-4, 232

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more automatic C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with RPS capability.

trip capability not maintained.

OR Two or more manual Functions with RPS trip capability not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B, or C not met. the channel.

E. As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 29.5% RTP.

and referenced in I Table 3.3.1.1-1.

F. As required by F.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

(continued)

PBAPS UNIT 2 3.3 -2 Amendment No. 247

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1. rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

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

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 ------------------NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 2 25% RTP.

Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power is

< 2% RTP while operating at 2 25% RTP.

(continued)

PBAPS UNIT 2 3.3-3 Amendment No. 210

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.3 (Not Used.)

SR 3.3.1.1.4 Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.5 -----------------NOTE-------------------

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

Perform CHANNEL FUNCTIONAL TEST 31 days SR 3.3.1.1.6 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.1.1.7 (Not Used.)

SR 3.3.1.1.8 Calibrate the local power range monitors. 1000 MWD/T average core exposure (continued)

PBAPS UNIT 2 3.3-4 Amendment No. 2l-,2?,

232

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1.10 ------------------NOTE-------------------

Radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.1.1.11 ------------------NOTES------------------

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

2. For Function 2.b, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL-TEST. 184 days SR 3.3.1.1.12 ------------------NOTES------------------

1. Neutron detectors are excluded.

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

3. For Function 2.b, the recirculation flow transmitters that feed the APRMs are included.

Perform__CHANNEL__CALIBRATION. __24_months Perform CHANNEL CALIBRATION. 24 months (continued)

PBAPS UNIT 2 3.3-5 Amendment No.2;-,2;6,-19, 22 232

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.13 Verify Turbine Stop Valve-Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29.5% RTP. I SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1.15 Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.16 Calibrate each radiation detector. 24 months SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.

PBAPS UNIT 2 3.3 -6 Amendment No. 247

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION 0.1 REQUIREMENTS VALUE

1. Wide Range Neutron Monitors

a. Period-Short 2 3 G SR 3.3.1.1.1 2 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 5 (a) 3 H SR 3.3.1.1.1 2 13 seconds SR 3.3.1.1.6 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18

b. Inop 2 3 G SR 3.3 .1.1.5 NA SR 3.3.1.1.17 5 (a) 3 H SR 3.3.1.1.6 NA SR 3.3.1.1.17

2. Average Power Range Monitors

a. Neutron Flux-High 2 3(c) G SR 3.3.1.1.1 s15.0S RTP lSetdown) SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.12

b. Simulated Thermal 3 (c) F SR 3.3.1.1.1 s 0.65 W Power-High SR 3.3.1.1.2 + 63.7S RTP(b) and s 116.0O I

RTP SR 3.3 .1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12

c. Neutron Flux-High 3 (c) F SR 3.3.1.1.1 s 119.71 RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12

d. Inop 1.2 3 (c) G SR 3.3.1.1.11 NA

e. 2-Out-Of-4 Voter 1.2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.11 SR 3.3.1.1.17 SR 3.3.1.1.18 (continued)

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

lb) 0.65 W+ 63.7S - 0.65 AW RTP when reset for single loop operation per LCO 3.4.1, 'Recirculation Loops I Operating.'

Cc) Each APRM channel provides inputs to both trip systems.

PBAPS UNIT 2 3.3-7 Amendment No. 247

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

3. Reactor Pressure -High 1,2 2 G SR 3.3.1.1.1 s 1085.0 psig SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

4. Reactor Vessel Water 1,2 2 G SR 3.3.1.1.1 2 1.0 inches Level-Low (Level 3) SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 S. Main Steam Isolation 1 B F SR 3.3.1.1.9 s 10 closed Valve -Closure SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

6. Drywell Pressure-High 1.2 2 G SR 3.3.1.1.1 s 2.0 psig SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

7. Scram Discharge Volume 1.2 2 G SR 3.3.1.1.9 s 50.0 gallons Water Level -High SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 5 (a) 2 H SR 3.3.1.1.9 S 50.0 gallons SR 3.3.1.1.15 SR 3.3.1.1.17 S. Turbine Stop 2 29.5S RTP 4 E SR 3.3.1.1.9, s 101 closed Valve-Closure I SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

9. Turbine Control Valve 2 29.5S RTP 2 E SR 3.3.1.1.9 Z 500.0 psig Fast Closure. Trip Oil I SR 3.3.1.1.13 Pressure-Low SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3 .1.1.18

10. Turbine Condenser-Low 1 2 F SR 3.3.1.1.1 k 23.0 inches Vacuum SR 3.3.1.1.9 Hg vacuum SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

11. Main Steam Line -High 1,2 2 G SR 3.3.1.1.1 s 15 X Full Radiation SR 3.3.1.1.10 Power SR 3.3 .1.1.16 Background SR 3.3 .1.1.17 SR 3.3.1.1.18

12. Reactor Mode Switch - 1.2 1 G SR 3.3.1.1.14 NA Shutdown Position SR 3.3.1.1.17 5 (a) 1 H SR 3.3.1.1.14 NA SR 3.3.1.1.17 (continued)

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

PBAPS UNIT 2 3.3-8 Amendment No. 247

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrunentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

13. Manual Scram 1,2 1 G SR 3.3.1.1.9 NA SR 3.3.1.1.17 5 (a) 1 H SR 3.3.1.1.9 NA SR 3.3.1.1.17

14. RPS Channel Test Switch 1,2 2 G SR 3.3.1.1.4 NA SR 3.3.1.1.17 5 (a) 2 H SR 3.3.1.1.4 NA SR 3.3.1.1.17 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

PBAPS UNIT 2 3 .3-9 Amendment No. 210

I WRNM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION l 3.3.1.2 Wide Range Neutron Monitor (WRNM) Instrumentation I LCO 3.3.1.2 The WRNM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months WRNMs inoperable in WRNMs to OPERABLE MODE 2. status.

B. Three required WRNMs B.1 Suspend control rod Immediately I inoperable in MODE 2. withdrawal.

C. Required Action and C.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 or B not met.

(continued)

PBAPS UNIT 2 3.3-10 Amendment No. -O0f-222

I WRNM Instrumentation 3.3.1.2 ACTTINS (cnntinued}

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months I WRNMs inoperable in insertable control MODE 3 or 4. rods.

AND D.2 Place reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

E. One or more required E.1 Suspend CORE Immediately I WRNMs inoperable in ALTERATIONS except MODE 5. for control rod insertion.

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

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

PBAPS UNIT 2 3.3-11 Amendment No. ff1,-222

I WRNM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.2 ------------------NOTES------------------

1. Only required to be met during CORE ALTERATIONS.

I 2. One WRNM may be used to satisfy more than one of the following.

I Verify an OPERABLE WRNM detector is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when I the associated WRNM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, I when the associated WRNM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. 124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months (continued)

PBAPS UNIT 2 3.3-12 Amendment No. -f0,222

I WRNM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.4 - ------------- NOTES------------------

1. Not required to be met with less than or equal to four fuel assemblies I adjacent to the WRNM and no other fuel assemblies in the associated core quadrant.

2. Not required to be met during spiral unloading.

Verify count rate is: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE

a. a 3.0 cps; or ALTERATIONS

b. Within the limits of AND Figure 3.3.1.2-1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.2.5 ------------------ NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after WRNMs indicate 125E-5 %

power or below.

Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to noise ratio.

SR 3.3.1.2.6 ------------------NOTES------------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after WRNMs indicate 125E-5 %

power or below.

Perform__CHANEL__CALIBRATION. __24_months Perform CHANNEL CALIBRATION. 24 months PBAPS UNIT 2 3.3-13 Amendment No. -i*-,222

I WRNM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)

I Wide Range Neutron Monitor Instrumentation APPLICABLE HODES OR OTHER REOUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS I 1. Wide Range Neutron Monitor 2 (a) 3 (d) SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.5 I SR 3.3.1.2.6 3,4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.5 I SR 3.3.1.2.6 S 2 (b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 I SR 3.3.1.2.6 I Ca) With WRNHs reading 125E-5 X power or below.

Cb) Only one WRNM channel is required to be OPERABLE during spiral offLoad or reload when the fueled region I includes only that WRNN detector.

I Cc) Special movable detectors may be used in place of WRNMs if connected to normal WRNM circuits.

I td) Channels must be in3 of 4 core quadrants.

PBAPS UNIT 2 3 .3-14 Amendment No. _fi~,222

I WRNM Instrumentation 3.3.1.2 3.0 2.9 2.8 2.7 2.6 2.5 2.4 - -F-B l n l.

2-3 S =

- 2.1 la2.C B

C, 1.l -- ~1~-

1 l - - - ---

O .. 2 - -

0 1.,

__ I. _-__ - F- -_ -

1. ) 8 i N M I Actl<ER-E-

. . .......i......

1.

0 0

0 2 B 10 14 18 22 26 30 Signal-toNoise Ratio Figure 3.3.1.2-1 (page 1 of 1)

I Minimum WRNM Count Rate Versus Signal to Noise Ratio PBAPS UNIT 2 3 .3-15 Amendment No. -1M0 222

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (RBM) channel to OPERABLE status.

inoperable.

B. Required Action and B.1 Place one RBM channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion in trip.

Time of Condition A not met.

OR Two RBM channels inoperable.

C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor scram.

startup.

OR (continued)

PBAPS UNIT 2 3.3-16 Amendment No. 210

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.1 Verify 2 12 rods Immediately withdrawn.

OR C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable has not been performed in the last calendar year.

AND C.2.2 Verify movement of During control control rods is in rod movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control reactor shutdown. control rods is in rod movement accordance with BPWS by a second licensed operator or other qualified member of the technical staff.

(continued)

PBAPS UNIT 2 3.3-17 Amendment No. 210

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Reactor E.1 Suspend control rod Immediately Mode Switch- Shutdown withdrawal.

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

SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

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

SURVEILLANCE FREQUENCY I SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 184 days (continued)

PBAPS UNIT 2 3.3-18 Amendment No.2;0,232

Control Rod Block Instrumentation 3.3.2.1 I SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.2 ----------- NOTE-------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at s 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------------------NOTE-------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is g 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 ------------------NOTE-------------------

Neutron detectors are excluded.

Verify the RBM: 24 months

a. Low Power Range -Upscale Function is not bypassed when THERMAL POWER is 2 28.4% RTP.

b. Intermediate Power Range- Upscale Function is not bypassed when THERMAL POWER is 2 63.4% RTP.

c. High Power Range-Upscale Function is not bypassed when THERMAL POWER is 2 83.4% RTP.

(continued)

PBAPS UNIT 2 3.3-19 Amendment No. 2X0,232

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 ------------------NOTE-------------------

Neutron detectors are excluded.

I Perform CHANNEL CALIBRATION. 24 months SR 3.3.2.1.6 Verify the RWM is not bypassed when 24 months THERMAL POWER is s 10% RTP.

SR 3.3.2.1.7 ------------------NOTE-------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after-reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.8 Verify control rod sequences input to the Prior to RWM are in conformance with BPWS. declaring RWM OPERABLE following loading of sequence into RWM PBAPS UNIT 2 3.3-20 Amendment No. 2t0, 232

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

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

1. Rod Block Monitor

a. Low Power Range - Upscale (a) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.5

b. Intermediate Power (b) 2 SR 3.3.2.1.1 (h)

Range - Upscale SR 3.3.2.1.4 SR 3.3.2.1.5 I C. High Power Range-Upscale (c) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.5

d. Inop (a) 2 SR 3.3.2.1.1 NA I

2. Rod Worth Minimizer 1 Cf), 2 (f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.8

3. Reactor Mode Switch -Shutdown Cg) 2 SR 3.3.2.1.7 NA Position I (a) THERMAL POWER 2 28.4X RTP and MCPR less than the limit specified in the COLR.

I (b) THERMAL POWER 2 63.4% RTP and MCPR less than. the Limit specified in the COLR.

I (c) THERMAL POWER 2 83.4x and MCPR less than the limit specified in the COLR.

I (d) Deleted.

I (e) Deleted.

Cf) With THERMAL POWER S 10X RTP.

(C) Reactor mode switch in the shutdown position.

(h) Less than or equal to the Allowable Value specified in the COLR.

I PBAPS UNIT 2 3.3-21 Amendment No.2W-,232

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Two channels per trip system of the Digital Feedwater Control System (DFCS) high water level trip instrumentation Function shall be OPERABLE.

APPLICABILITY: THERMAL POWER ; 25% RTP.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DFCS high A.1 Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months water level trip trip.

channels inoperable.

B. DFCS high water level B.1 Restore DFCS high 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months trip capability not water level trip maintained. capability.

C. Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

PBAPS UNIT 2 3.3-22 Amendment No. 210

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Value shall be S 49.0 inches.

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including valve actuation.

PBAPS UNIT 2 3.3-23 Amendment No. 210

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

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

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.6.

not met.

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

(continued)

PBAPS UNIT 2 3.3-24 Amendment No. 210

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for not met. the channel.

E. As required by E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in Immediately Required Action D.1 accordance with and referenced in Specification 5.6.6.

Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK for each required 31 days PAM instrumentation channel.

SR 3.3.3.1.2 Perform CHANNEL CALIBRATION of the 92 days Drywell and Suppression Chamber H2 & 02 Analyzers.

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for each 24 months required PAM instrumentation channel except for the Drywell and Suppression Chamber H2 & 02 Analyzers.

PBAPS UNIT 2 3.3-25 Amendment No. 210

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)

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

1. Reactor Pressure 2 E

2. Reactor Vessel Water Level (Wide Range) 2 E

3. Reactor Vessel Water Level (Fuel Zone) 2 E

4. Suppression Chamber Water Level (Wide Range) 2 E

5. Drywell Pressure (Wide Range) 2 E

6. Drywell Pressure (Subatmospheric Range) 2 E

7. Drywell High Range Radiation 2 F

8. PCIV Position 2 per penetw T flow E

9. Drywell H2 & 02 Analyzer 2 E

10. Suppression Chamber H2 & 02 Analyzer 2 E

11. Suppression Chamber Water Temperature ?Cc) E (a) Not required for isolation valves whose associated penetration flow path 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) Each charnel requires 10 resistance temperature detectors (RTDs) to be OPERABLE with no two adjacent RTDs inoperable.

PBAPS UNIT 2 3.3-26 Amendment No. 210

Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

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

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

(continued)

PBAPS UNIT 2 3.3-27 Amendment No. 210

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE REQUIREMENTS FREQUENCY SR 3.3.3.2.2 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.

PBAPS UNIT 2 3.3-28 Amendment No. 210

ATWS-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation LCO 3.3.4.1 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE:

a. Reactor Vessel Water Level-Low Low (Level 2); and

b. Reactor Pressure-High.

APPLICABILITY: MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

OR A.2 -------- NOTE---------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 14 days trip.

(continued)

PBAPS UNIT 2 3.3-29 Amendment No. 210

ATWS-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one capability not Function.

maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump Time not met. from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

PBAPS UNIT 2 3.3-30 Amendment No. 210

ATWS-RPT Instrumentation 3.3.4.1, SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

a. Reactor Vessel Water Level-Low Low (Level 2): x -48.0 inches; and

b. Reactor Pressure-High:

5 1106.0 psig.

SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

PBAPS UNIT 2 3.3-31 Amendment No. 210

EOC-RPT Instrumentation 3.3.4.2 3.3 INSTRUMENTATION 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.2 a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV)-Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure-Low.

DR

b. The following limits are made applicable:

1. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for inoperable EOC-RPT as specified in the COLR; and

2. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

limits for inoperable EOC-RPT as specified in the COLR.

APPLICABILITY: THERMAL POWER 2 29.5% RTP. I ACTIONS

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

Separate Condition entry is allowed for each channel.

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

A.2 --------NOTE---------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

(continued)

PBAPS UNIT 2 3.3-31a Amendment No. 247

EOC-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with EOC-RPT trip capability.

capability not maintained.

C. Required Action and C.1 Remove the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion recirculation pump Time not met. from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 29.5% RTP. I SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL FUNCTIONAL TEST. 92 days (continued)

PBAPS UNIT 2 3.3-31b Amendment No. 247

EOC-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

TSV-Closure:

10% closed; and TCV Fast Closure, Trip Oil Pressure-Low:

2 500 psig.

SR 3.3.4.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

SR 3.3.4.2.4 Verify TSV-Closure and TCV Fast Closure, 24 months Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29.5% RTP.

I SR 3.3.4.2.5 ------------------ NOTE-------------------

Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.2.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME 24 months on a is within limits. STAGGERED TEST BASIS SR 3.3.4.2.6 Determine RPT breaker interruption time. 60 months PBAPS UNIT 2 3.3-31c Amendment No. 247

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.1-1 for the channel.

B. As required by B.1 -------- NOTES--------

Required Action A.1 1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

2. Only applicable for Functions 1.a, I.b, 2.a, and 2.b.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature feature ECCS initiation initiation capability capability in is inoperable. both trip systems AND (continued)

PBAPS UNIT 2 3.3-32 Amendment No. 210

ECCS Instrumentation 3.3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 -------- NOTE---------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable. initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.1 -------- NOTES--------

Required Action A.1 1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

2. Only applicable for Functions 1.c, 1.e, 1.f, 2.c, 2.d, and 2.f.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS subsystem initiation capability initiation is inoperable. capability in both subsystems AND C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

PBAPS UNIT 2 3.3-33 Amendment No. 210

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 --------NOTE---------

Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1. not aligned to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of HPCI initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

(continued)

PBAPS UNIT 2 3.3-34 Amendment No. 210

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 -------- NOTES--------

Required Action A.1 1. Only applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

2. Only applicable to Functions 1.d and 2.g.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature(s) inoperable discovery of when its redundant loss of feature ECCS subsystem initiation capability initiation is inoperable. capability in both subsystems AND E.2 Restore channel to 7 days OPERABLE status.

(continued)

PBAPS UNIT 2 3.3-35 Amendment No. 210

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1. inoperable. initiation capability in both trip systems AND F.2 Place channel in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from trip. discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days (continued)

PBAPS UNIT 2 3.3-36 Amendment No. 210

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by G.1 Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 inoperable. discovery of and referenced in loss of ADS Table 3.3.5.1-1. initiation capability in both trip systems AND G.2 Restore channel to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, inoperable.

C, D, E, F, or G not met.

PBAPS UNIT 2 3.3-37 Amendment No. 210

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.f; and (b)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months PBAPS UNIT 2 3.3-38 Amendment No. 210

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Vessel Water 1,2,3, 4 (b) B SR 3.3.5.1.1 2 -160.0 Level -Low Low Low SR 3.3.5.1.2 inches (Level 1) 4 Ca), 5 (a) SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1,2,3 4 Cb) B SR 3.3.5.1.1 S 2.0 psig Pressure -High SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Pressure -Low 1.2,3 4 C SR 3.3.5.1.1 2 425.0 psig (Injection Permissive) SR 3.3.5.1.2 and SR 3.3.5.1.4 S 475.0 psig SR 3.3.5.1.5 4{(). 5 Cm) 4 B SR 3.3.5.1.1 2 425.0 psig SR 3.3.5.1.2 and SR 3.3.5.1.4 S 475.0 psig SR 3.3.5.1.5

d. Core Spray Pump 1,2,3, 4 E SR 3.3.5.1.2 2 319.0 psid Discharge Flow -Low (1 per .SR 3.3.5.1.4 and (Bypass) 4 (a), 5 Ca) pump) S 351.0 psid

e. Core Spray Pump Start- 1,2,3 4 C SR 3.3.5.1.4 2 5.0 seconds Time Delay Relay (loss (1 per SR 3.3.5.1.5 and of offsite power) 4Cm), 5 Ca) pump) S 7.0 seconds

f. Core Spray Pump Start-Time Delay Relay (offsite power available)

Pumps A,C 1,2,3 2 C SR 3.3.5.1.4 2 12.1 Cl per SR 3.3.5.1.5 seconds and 4t)() pump) S513.9 seconds Pumps BD 1,2,3 2 C SR 3.3.5.1.4 2 21.4 (1 per SR 3.3.5.1.5 seconds and 4 (a) 5 (a) pump) S 24.6 seconds (continued)

(a) When associated subsystemts) are required to be OPERABLE.

(b) Also required to initiate the associated diesel generator tDG).

PBAPS UNIT 2- 3. 3-39 Amendment No. 210

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrunentation APPLICABLE CONDITIONS NODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. Low Pressure Coolant Injection CLPCI) System

a. Reactor Vessel Water 1,2,3, 4 B SR 3.3.5.1.1 2 -160 inches Level -Low Low Low SR 3.3.5.1.2 (Level 1) 4 (a), 5 (a) SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1,2,3 B SR 3.3.5.1.1 S 2.0 psig Pressure -High SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Pressure-Low 1,2,3 C SR 3.3.5.1.1 2 425.0 psig (Injection Permissive) SR 3.3.5.1.2 and SR 3.3.5.1.4 < 475.0 psig SR 3.3.5.1.5 4 ta), Sa) B SR 3.3.5.1.1 2 425.0 psig SR 3.3.5.1.2 and SR 3.3.5.1.4 < 475.0 psig SR 3.3.5.1.5

d. Reactor Pressure-Low c),2c), 4 C SR 3.3.5.1.1 2 211.0 psig Low (Recirculation SR 3.3.5.1.2 Discharge Valve 3 (C) SR 3.3.5.1.4 Permissive) SR 3.3.5.1.5

e. Reactor Vessel Shroud 1,2,3 2 B SR 3.3.5.1.1 2 -226.0 Level -Level 0 SR 3.3.5.1.2 inches SR 3.3.5.1.4 SR 3.3.5.1.5

f. Low Pressure Coolant 1,2,3, C SR 3.3.5.1.4 Injection Pumnp (2 per SR 3.3.5.1.5 Start -Time Delay 4 (a), 5(a) pump)

Relay (offsite power available)

Pumps A,B 2 1.9 seconds and S 2.1 seconds Pumps C,D 2 7.5 seconds and S 8.5 seconds

9. Low Pressure Coolant 1,2.3 4 E SR 3.3.5.1.2 > 299.0 psid Injection Pump (1 per SR 3.3.5.1.4 and Discharge Flow -Low 4(a), 5 (a) pump) SR 3.3.5.1.5 < 331.0 psid (Bypass)

(continued)

(a) When associated subsystem(s) are required to be OPERABLE.

tc) With associated recirculation pump discharge valve open.

PBAPS UNIT 2 3.3-40 Amendment No. 210

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

3. High Pressure Coolant Injection CHPCI) System

a. Reactor Vessel Water 1, B SR 3.3.5.1.1 2 -48.0 Level -Low Low SR 3.3.5.1.2 inches (Level 2) 2(d), 3 (d) SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1, 4 B SR 3.3.5.1.1 S 2.0 psig Pressure -High SR 3.3.5.1.2 2(d), 3(d) SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Vessel Water 1, 2 C SR 3.3.5.1.1 ! 46.0 inches Level -High (Level 8) SR 3.3.5.1.2 2(d), 3(d) SR 3.3.5.1.4 SR 3.3.5.1.5

d. Condensate Storage 1, 2 D SR 3.3.5.1.2 2 5.25 ft Tank Level -Low SR 3.3.5.1.4 above tank 2 (d), 3 (d) SR 3.3.5.1.5 bottom

e. Suppression Pool Water 1, 2 D SR 3.3.5.1.2 ! 5.0 inches Level -High SR 3.3.5.1.4 above torus 2 (d), 3 (d) SR 3.3.5.1.5 midpoint

f. High Pressure Coolant 1, 1 E SR 3.3.5.1.2 2 3.5 in-wc Injection Pump SR 3.3.5.1.4 and S 19.0 Discharge Flow -Low 2(d), 3(d) SR 3.3.5.1.5 in-wc (Bypass)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water 1, 2 F SR 3.3.5.1.1 2 -160.0 Level -Low Low Low SR 3.3.5.1.2 inches (Level 1) 2 (e), 3 "e) SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1, 2 F SR 3.3.5.1.1 S 2.0 psig Pressure -High SR 3.3.5.1.2 2 (e), 3 "e) SR 3.3.5.1.4 SR 3.3.5.1.5

c. Automatic 1, 1 G SR 3.3.5.1.4 5 115.0 Depressurization SR 3.3.5.1.5 seconds System Initiation 2 (e), 3 (e)

Timer (continued)

(d) With reactor steam dome pressure > 150 psig.

(e) With reactor steam dome pressure > 100 psig.

PBAPS UNIT-2 3 .3-41 Amendment No. 210

ECCS Instrumentati on 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS NODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

4. ADS Trip System A (continued)

d. Reactor Vessel Water 1, 2 F SR 3.3.5.1.1 2 -160.0 Level-Low Low Low SR 3.3.5.1.2 inches (Level 1), 2 Ce" 3(") SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.5

e. Reactor Vessel Water 1, l F SR 3.3.5.1.1 2 6.0 Inches Confirmatory SR 3.3.5.1.2 Level -Low (Level 4) 2 (e). 3 Ce) SR 3.3.5.1.4 SR 3.3.5.1.5

f. Core Spray Pump 1, 4 G SR 3.3.5.1.3 2 175.0 psig Discharge SR 3.3.5.1.5 and Pressure -High 2 (e), 3 Ce) 5 195.0 psig

g. Low Pressure Coolant 1, a G SR 3.3.5.1.3 2 40.0 psig Injection Pump SR 3.3.5.1.5 and Discharge 2 Ce)' 3 "e) 5 60.0 psig Pressure -High

h. Automatic 1, 2 G SR 3.3.5.1.4 ! 9.5 minutes Depressurization SR 3.3.5.1.5 System Low Water Level 2Ce), 3(e)

Actuation Timer S. ADS Trip System B

a. Reactor Vessel Water 1, 2 F SR 3.3.5.1.1 2 -160.0 Level -Low Low Low SR 3.3.5.1.2 inches (Level 1) 2 (e) 3(e) SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1, 2 F SR 3.3.5.1.1 5 2.0 psig Pressure -High SR 3.3.5.1.2 2 te), 3 (e) SR 3.3.5.1.4 SR 3.3.5.1.5

c. Automatic 1, 1 G SR 3.3.5.1.4 S 115.0 Depressurization SR 3.3.5.1.5 seconds System Initiation 2 Ce), 3 Ce)

Timer

d. Reactor Vessel Water 1, 2 F SR 3.3.5.1.1 2 -160.0 Level-Low Low Low SR 3.3.5.1.2 inches (Level 1), 2 "e), 3 "e) SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.5 (continued)

(e) With reactor steam dome pressure > 100 psig.

PBAPS UNIT 2- 3.3 -42 Amendment No. 210

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS NODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

5. ADS Trip System B (continued)

e. Reactor Vessel Water 1, 1 F SR 3.3.5.1.1 k 6.0 inches Confirmatory SR 3.3.5.1.2 Level -Low (Level 4) 2(e), 3 (e) SR 3.3.5.1.4 SR 3.3.5.1.5

f. Core Spray Pump 1, 4 G SR 3.3.5.1.3 2 175.0 psig Discharge 2 (e) SR 3.3.5.1.5 and Pressure --High 3(e) s 195.0 psig

g. Low Pressure Coolant 1, 8 G SR 3.3.5.1.3 2 40.0 psig Injection Pump SR 3.3.5.1.5 and Discharge 2 (e), 3 Ce) 3 SS .0 psig Pressure -High

h. Automatic 1, 2 G SR 3.3.5.1.4 S 9.5 minutes Depressurization SR 3.3.5.1.5 System Low Water Level 2 (e), 3(e)

Actuation Timer (e) With reactor steam dome pressure > 100 psig.

PBAPS UNIT 2 3 .3-43 Amendment No. 210

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

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

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 inoperable. discovery of and referenced in loss of RCIC Table 3.3.5.2-1. initiation capability AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B.2 Place channel in trip.

C. As required by C.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action A.1 OPERABLE status.

and referenced in Table 3.3.5.2-1.

(continued)

PBAPS UNIT 3.3-44 A Amendment No. 210

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 -------- NOTE---------

Required Action A.1 Only applicable if and referenced in RCIC pump suction is Table 3.3.5.2-1. not aligned to the suppression pool.

Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of RCIC initiation capability AND D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR D.2.2 Align RCIC pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.

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

PBAPS UNIT 2 3.3-45 Amendment No. 210

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 2; and (b)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months PBAPS UNIT-2 3.3-46 Amendment No. 210

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM REQUIRED SURVEILLANCE ALLOWABLE FUNCTION PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 4B SR 3.3.5.2.1 2 -48.0 inches Level -Low Low (Level 2) SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4

2. Reactor Vessel Water 2 C SR 3.3.5.2.1 ' 46.0 inches Level -High CLevel 8) SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4

3. Condensate Storage Tank 2 D SR 3.3.5.2.1 2 5.25 ft above Level -Low SR 3.3.5.2.2 tank bottom SR 3.3.5.2.3 SR 3.3.5.2.4 PBAPS UNIT-2-- _ 3 .3-47 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. trip. Functions 1.d, 2.a, and 2.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 1.d, 2.a, and 2.b B. One or more Functions B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with isolation capability.

capability not maintained.

C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or Table 3.3.6.1-1 for B not met. the channel.

(continued)

PBAPS UNIT 2 3.3-48 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 Isolate associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action C.1 main steam line and referenced in (MSL).

Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.1 penetration flow and referenced in path(s).

Table 3.3.6.1-1.

G. As required by G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action C.1 and referenced in AND Table 3.3.6.1-1.

G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Action and associated Completion Time of Condition F not met.

(continued)

PBAPS UNIT 2 3.3-49 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by H.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.1 standby liquid and referenced in control (SLC)

Table 3.3.6.1-1. subsystem inoperable.

OR H.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System.

I. As required by I.1 Initiate action to Immediately Required Action C.1 restore channel to and referenced in OPERABLE status.

Table 3.3.6.1-1.

OR I.2 Initiate action to Immediately isolate the Residual Heat Removal (RHR)

Shutdown Cooling System.

PBAPS UNIT 2 3.3-50 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

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

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 ------------------NOTE-------------------

For Function 1.d, radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Calibrate each radiation detector. 24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months PBAPS UNIT 2 3 .3-51 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REOUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1 2 -160.0 Level -Low Low Low SR 3.3.6.1.2 inches (Level 1) SR 3.3.6.1.5 SR 3.3.6.1.7

b. Main Steam Line 1 2 E SR 3.3.6.1.3 2 850.0 pslg Pressure -Low SR 3.3.6.1.7

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 s 123.3 psid Flow -High MSL SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

d. Main Steam Line -High 1,2,3 2 D SR 3.3.6.1.1 5 15 X Full Radiation SR 3.3.6.1.3 Power SR 3.3.6.1.6 Background SR 3.3.6.1.7

e. Main Steam Tunnel 1,2,3 a D SR 3.3.6.1.1 S 200.0F Temperature -High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

2. Primary Contairvment Isolation

a. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 2 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

b. Drywell Pressure -High 1,2,3 2 G SR 3.3.6.1.1 5 2.0 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

c. Main Stack Monitor 1,2,3 1 F SR 3.3.6.1.1 S 2 X 10.2 Radiation -High SR 3.3.6.1.2 pCi/cc SR 3.3.6.1.4 SR 3.3.6.1.7

d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 S 16.0 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation -High SR 3.3.6.1.7

e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 5 16.0 umR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation -High SR 3.3.6.1.7 (continued) ,

PBAPS UNIT 2 3.3-52 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

3. High Pressure Coolant Injection CHPCI) System Isolation

a. HPCI Steam Line 1,2,3 1 F SR 3.3.6.1.3 5 225.0 in-wc Flow -High SR 3.3.6.1.7

b. HPCI Steam Line 1,2,3 1 F SR 3.3.6.1.5 S 10.0 seconds Flow -Time Delay SR 3.3.6.1.7 Relays

c. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.3 z 60.0 psig Pressure -Low SR 3.3.6.1.7

d. Drywell Pressure -High 1,2.3 2 - F SR 3.3.6.1.1 5 2.0 psig CVacuum Breakers) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

e. HPCI Compartment and 1,2,3 8 F SR 3.3.6.1.1 5 200.OOF Steam Line Area SR 3.3.6.1.2 Temperature -High SR 3.3.6.1.5 SR 3.3.6.1.7

4. Reactor Core Isolation Cooling tRCIC) System Isolation

a. RCIC Steam Line 1,2,3 1 F SR 3.3.6.1.3 S 450.0 in-wc Flow -High SR 3.3.6.1.7

b. RCIC Steam Line 1,2,3 1 F SR 3.3.6.1.5 5 10.0 seconds Flow -Time Delay SR 3.3.6.1.7 Relays

c. RCIC Steam Supply Line 1,2,3 2 F SR 3.3.6.1.3 2 60.0 psig Pressure -Low SR 3.3.6.1.7

d. Drywell Pressure--High 1,2,3 2 F SR 3.3.6.1.1 5 2.0 psig (Vacuum Breakers) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

e. RCIC Compartment and 1,2,3 8 F SR 3.3.6.1.1 S 200.00F Steam Line Area SR 3.3.6.1.2 Temperature -High SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)

(3 PBAPS UNIT 2 3.3-53 Amendment No. 210

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)

Primary Contaimnent Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. Reactor Water Cleanup CRWCU) System Isolation

a. RWCU Flow-High 1,2,3 1 F SR 3.3.6.1.1 S 125X rated SR 3.3.6.1.3 flow (23.0 SR 3.3.6.1.7 in-wc)

b. SLC System Initiation 1,2 1 H SR 3.3.6.1.7 NA

c. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 2 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

6. RHR Shutdown Cooling System Isolation

a. Reactor Pressure-High 1,2,3 1 F SR 3.3.6.1.3 S 70.0 psig SR 3.3.6.1.7

b. Reactor Vessel Water 3,4,5 2 Ca) I SR 3.3.6.1.1 2 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

7. Feedwater Recirculation Isolation

a. Reactor Pressure-High 1,2,3 2 F SR 3.3.6.1.1 S 600 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 (a) In MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained, only one channel per trip system with an isolation signal available to one shutdown cooling pump suction isolation valve is required.

PBAPS UNIT 2 3.3-54 Amendment No. 210

Secondary Containment Isolation Instrumentation 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inoperable. trip. Functions 1 and 2

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 1

-and 2 B. One or more Functions B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with isolation capability.

capability not maintained.

(continued)

PBAPS UNIT 2 3.3-55 Amendment No. 210

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Isolate the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion associated secondary Time of Condition A or containment B not met. penetration flow path(s).

OR C.1.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment isolation valves inoperable.

AND C.2.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem(s) in operation.

OR C.2.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SGT subsystem(s) inoperable.

( -

PBAPS UNIT 2 3.3-56 Amendment No.- 210

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

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

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months PBAPS UNIT 2 3.3-57 Amendment No. 210

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Contairment Isolation Instrumentation APPLICABLE NODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1,2,3, 2 SR 3.3.6.2.1 2 1.0 inches Level -Low (Level 3) (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

2. Drywell Pressure -High 1,2,3 2 SR 3.3.6.2.1 S 2.0 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

3. Reactor Building 1,2,3. 2 SR 3.3.6.2.1 S 16.0 mR/hr Ventilation Exhaust (a),(b) SR 3.3.6.2.3 Radiation -High SR 3.3.6.2.5

4. Refueling Floor 1,2,3, 2 SR 3.3.6.2.1 S 16.0 tR/hr Ventilation Exhaust (a),(b) SR 3.3.6.2.3 Radiation -High SR 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel.

(b) During CORE ALTERATIONS, and during movement of irradiated fuel assemblies In secondary containment.

PBAPS UNIT 2 3.3-58 Amendment No. 210

MCREV System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Main Control Room Emergency Ventilation (MCREV) System Instrumentation LCO 3.3.7.1 Two channels per trip system of the Control Room Air Intake Radiation-High Function shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from channels inoperable. MCREV subsystems discovery of inoperable. loss of MCREV System initiation capability AND A.2 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

(continued)

PBAPS UNIT 2 3.3-59 Amendment No. 210

MCREV System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion MCREV subsystem(s) in Time not met. operation.

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

SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. The 18 months Allowable Value shall be < 400 cpm.

SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months PBAPS UNIT 2 3.3-60 Amendment No. 210

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The Unit 2 LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

AND The Unit 3 LOP instrumentation for Functions 1, 2, 3, and 5 in Unit 3 Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: When the associated diesel generator and offsite circuit are required to be OPERABLE by LCO 3.8.1, "AC Sources-Operating," or LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One 4 kV emergency bus A.1 -------- NOTE---------

with one or two Enter applicable required Function 3 Conditions and channels inoperable. Required Actions of LCO 3.8.1 for offsite OR circuits made inoperable by LOP One 4 kV emergency bus instrumentation.

with one or two required Function 5 channels inoperable. Place channel in 14 days trip.

(continued)

PBAPS UNIT 2 3.3-61 Amendment No. 210

LOP Instrumentation 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two 4 kV emergency B.1 --------NOTE---------

buses with one Enter applicable required Function 3 Conditions and channel inoperable. Required Actions of LCO 3.8.1 for offsite OR circuits made inoperable by LOP Two 4 kV emergency instrumentation.

buses with one _

required Function 5 channel inoperable. Place the channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

OR One 4 kV emergency bus with one required Function 3 channel inoperable and a different 4 kV emergency bus with one required Function 5 channel inoperable.

(continued)

PBAPS UNIT 2 3.3-62 Amendment No. 210

LOP Instrumentation 3.3.8.1 ACTIONS (continued)_

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more 4 kV C.1 -------- NOTE---------

emergency buses with Enter applicable one or more required Conditions and Function 1, 2, or 4 Required Actions of channels inoperable. LCO 3.8.1 for offsite circuits made OR inoperable by LOP instrumentation.

One 4 kV emergency bus with one required Function 3 channel and Place the channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one required Function trip.

5 channel inoperable.

OR Any combination of three or more required Function 3 and Function 5 channels inoperable.

D. Required Action and D.1 Declare associated Immediately associated Completion diesel generator (DG)

Time not met. inoperable.

( l,z

. EY&

I PBAPS UNIT 2 3.3-63 Amendment No.-210-

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each Unit 2 LOP Function. SR 3.3.8.1.5 is applicable only to the Unit 3 LOP instrumentation.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided: (a)for Function 1, the associated Function maintains initiation capability for three DGs; and (b)for Functions 2, 3, 4, and 5, the associated Function maintains undervoltage transfer capability for three 4 kV emergency buses.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. 18 months SR 3.3.8.1.3 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.8.1.5 For required Unit 3 LOP instrumentation In accordance Functions, the SRs of Unit 3 with applicable Specification 3.3.8.1 are applicable. SRs

-I PBAPS UNIT-2 - 3.3-64 Amendment No. 210

LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)

,Loss of Power Instrumentation REQUI RED CHANNELS SURVEILLANCE ALLOWABLE FUNCTION PER BUS REQUIREMENTS VALUE

1. 4 kV Emergency Bus Undervoltage (Loss of Voltage)

a. Bus Undervoltage 1 SR 3.3.8.1.3 NA SR 3.3.8.1.4

2. 4 kV Emergency Bus Undervoltage (Degraded Voltage Low Setting)

a. Bus Undervoltage 2 SR 3.3.8.1.1 2 2286 V and i 2706 V (1 per SR 3.3.8.1.2 l source) SR 3.3.8.1.4

b. Time Delay 2 SR 3.3.8.1.1 2 1.5 seconds and (1 per SR 3.3.8.1.2 i 2.1 seconds source) SR 3.3.8.1.4

3. 4 kV Emergency Bus Undervoltage (Degraded Voltage High Setting)

a. Bus Undervoltage 2 SR 3.3.8.1.1 2 3409 V and s 3829 V (1 per SR 3.3.8.1.2 source) SR 3.3.8.1.4

b. Time Delay 2 SR 3.3.8.1.1 2 23.0 seconds and I (1 per source)

SR 3.3.8.1.2 SR 3.3.8.1.4 i 37.0 seconds

4. 4 kV Emergency Bus Undervoltage (Degraded Voltage LOCA)

a. Bus Undervoltage 2 SR 3.3.8.1.1 2 3766 V and ! 3836 V (a)

(1 per SR 3.3.8.1.2 source) SR 3.3.8.1.4

b. Time Delay 2 SR 3.3.8.1.1 2 9.2 seconds and I (1 per source)

SR 3.3.8.1.2 ! 10.8 seconds (a)

SR 3.3.8.1.4

5. 4 kV Emergency Bus Undervoltage (Degraded Voltage non-LOCA)

a. Bus UndervoLtage 2 SR 3.3.8.1.1 2 4116 V and i 4186 V (a)

(1 per SR 3.3.8.1.2 source) SR 3.3.8.1.4

b. Time Delay 2 SR 3.3.8.1.1 2 57.8 seconds and ! 64.2 I (1 per source)

SR 3.3.8.1.2 SR 3.3.8.1.4 seconds (a)

(a) Prior to the implementation of modification 96-01511, on a particular Function 4 or 5 relay, its Allowable Values are:

4.a 2 3691 V and I 3713 V, with internal time delay set i 0.9 seconds and < 1.1 seconds, 4.b > 8.4 seconds and 5 9.6 seconds, 5.a 2 4065 V and S 4089 V, with internal time delay set 2 0.9 seconds and S 1.1 seconds, 5.b > 57.0 seconds and ! 63.0 seconds. -

This note expired upon completion of modification 96-01511, but no later than March 1, 2000.

PBAPS UNIT 2 3.3-65 Amendment No. 230

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with inservice power one electric power supply(s) from monitoring assembly service.

inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with inservice power both electric power supply(s) from monitoring assemblies service.

inoperable.

C. Required Action and C.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 or B not met in MODE 1 or 2.

(continued)

PBAPS UNIT 2 3.3-66 Amendment No. 210

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to Immediately associated Completion fully insert all Time of Condition A or insertable control B not met in MODE 3, rods in core cells 4, or 5 with any containing one or control rod withdrawn more fuel assemblies.

from a core cell containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 ------------------NOTE-------------------

Only required to be performed prior to entering MODE 2 or 3 from MODE 4, when in MODE 4 for 2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATION for each RPS 24 months motor generator set electric power monitoring assembly. The Allowable Values shall be:

a. Overvoltage s 133 V, with time delay set to < 1.5 seconds.

b. Undervoltage 2 111 V, with time delay set to s 1.5 seconds.

c. Underfrequency 2 56.8 Hz, with time delay set to s 7.0 seconds.

(continued)

PBAPS UNIT 2 3.3-67 Amendment No. 210

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2.3 Perform CHANNEL CALIBRATION for each RPS 24 months alternate power supply electric power monitoring assembly. The Allowable Values shall be:

a. Overvoltage s 133 V, with time delay set to s 1.5 seconds.

b. Undervoltage x 111 V, with time delay set to s 4.0 seconds.

c. Underfrequency 2 56.8 Hz, with time delay set to s 1.5 seconds.

SR 3.3.8.2.4 Perform a system functional test. 24 months PBAPS UNIT 2 3.3-68 Amendment No. 210

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation with core flow as a function of THERMAL POWER in the "Unrestricted" Region of Figure 3.4.1-1.

OR One recirculation loop shall be in operation with core flow as a function of THERMAL POWER in the "Unrestricted" Region of Figure 3.4.1-1 and with the following limits applied when the associated LCO is applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR), " single loop operation limits specific in the COLR;

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; and

c. LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

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

Required limit modifications for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY: MODES 1 and 2.

PBAPS UNIT2 3.4-1 Amendment No.210,232

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two A.1 Verify APRM and LPRM 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recirculation loops in neutron flux noise operation with core levels are a 4% and AND flow as a function of q 3 times baseline THERMAL POWER in the noise levels. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months "Restricted" Region of thereafter Figure 3.4.1-1.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after completion of any THERMAL POWER increase

>- 5% RTP B. Required Action and B.1 Restore APRM and LPRM 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months associated Completion neutron flux noise Time of Condition A levels to s 4% and not met. s 3 times baseline noise levels.

C. One recirculation loop C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months in operation with core to the "Unrestricted" flow < 39% of rated Region of core flow and THERMAL Figure 3.4.1-1.

POWER in the "Restricted" Region of OR Figure 3.4.1-1.

C.2 Increase core flow to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

> 39% of rated core flow.

(continued)

PBAPS UNIT 2 3.4-2 Amendment No. 210

Recirculation Loops Operating 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Requirements of the D.1 Satisfy the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met for requirements of the reasons other than LCO.

Conditions A, B, C, and F.

E. Required Action and E.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 B, C, or D not met.

F. No recirculation loops F.1 Initiate action to Immediately in operation. reduce THERMAL POWER to the "Unrestricted" Region of Figure 3.4.1-1.

AND F.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months PBAPS UNIT--2 -- 3 .4-3 Amendment No. 210

Recirculation Loops Operating 3.4.1 SURVEILLANCE REOUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 --------------------NOTE-------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a. s 10.25 X 106 lbm/hr when operating at

< 71.75 X 106 lbm/hr; and

b. s 5.125 X 106 Ibm/hr when operating at

- 71.75 X 106 ibm/hr.

SR 3.4.1.2 Verify core flow as a function of THERMAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months POWER is in the "Unrestricted" Region of Figure 3.4.1-1.

PBAPS UNIT -2~ 3.4-4 Amendment No. 210

Recirculation Loops Operating 3.4.1 70 60 30 1D a F-20 110 20 25 30 35 40 45 so 55 so 85 70 Core Flow(%Rzted)

Figure 3.4.1-1 (page 1 of 1)

THERMAL POWER VERSUS CORE FLOW STABILITY REGIONS PBAPS UNIT 2 3.4-5 Amendment No. 247

Jet Pumps 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

PBAPS UNIT 2 3.4-6 Amendment No. 210

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 -------------------NOTES-------------------

1. Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP.

Verify at least one of the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months criteria (a, b, or c) is satisfied for each operating recirculation loop:

a. Recirculation pump flow to speed ratio differs by < 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by c 5% from established patterns.

b. Each jet pump diffuser to lower plenum differential pressure differs by c 20%

from established patterns.

c. Each jet pump flow differs by c 10%

from established patterns.

PBAPS UNIT 2 3 .4-7 Amendment No. 210

SRVs and SVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety Relief Valves (SRVs) and Safety Valves (SVs)

LCO 3.4.3 The safety function of 11 valves (any combination of SRVs and SVs) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SRVs or SVs inoperable. AND A.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PBAPS UNIT 2- 3.4-8 Amendment No. 210

SRVs and SVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints Inaccordance of the required SRVs'and SVs are as with the follows: Inservice Testing Program Number of Setpoint SRVs (..Sipil 4 1135

11.0 4 1145

11.0 3 1155

12.0 Number of Setpoint SVs (osia) 2 1260

13.0 SR 3.4.3.2 Verify each required SRV actuator strokes 24 months when manually actuated in the depressurization mode.

PBAPS UNIT 2 3.4-9 Amendment No.-ffi,-224

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. - 5 gpm unidentified LEAKAGE;

c. S 25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period; and

d. S 2 gpm increase in unidentified LEAKAGE within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period in MODE 1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limit. within limits.

OR Total LEAKAGE not within limit.

B. Unidentified LEAKAGE B.1 Reduce LEAKAGE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months increase not within increase to within limit. limits.

OR (continued)

PBAPS UNIT 2 3.4-10 Amendment No. 210

RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.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 or AND B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and unidentified LEAKAGE increase are within limits.

PBAPS UNIT 2 3 .4-11 Amendment No. 210

RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell sump monitoring system; and

b. One channel of primary containment atmospheric gaseous monitoring system.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell sump A.1 Restore drywell sump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months monitoring system monitoring system to inoperable. OPERABLE status.

B. Required primary- ---- NOTE-------------

containment LCO 3.0.4 is not applicable.

atmospheric monitoring __

system inoperable.

B.1 Analyze grab samples Once per of primary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere.

AND B.2 Restore required 30 days primary containment atmospheric monitoring system to OPERABLE status.

(continued)

PBAPS UNIT 2 3.4-12 Amendment No. 210

RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.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 or AND B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required leakage D.1 Enter LCO 3.0.3. Immediately detection systems inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of required primary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmospheric monitoring system.

SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required leakage detection instrumentation.

SR 3.4.5.3 Perform a CHANNEL CALIBRATION of required 92 days leakage detection instrumentation.

PBAPS UNIT 2-,- 3.4-13 Amendment No. 210

RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT I-131 specific activity

< 0.2 pCi/gm.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant ------------- NOTE------------

specific activity LCO 3.0.4 is not applicable.

> 0.2 pCi/gm and _

< 4.0 pCi/gm DOSE EQUIVALENT I-131. A.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131.

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 limits.

B. Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT I-131.

Time of Condition A not met. AND OR B.2.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam lines.

Reactor coolant specific activity OR

> 4.0 pCi/gm DOSE EQUIVALENT I-131.

(continued)

PBAPS UNIT 2 3.4-14 Amendment No. 210

RCS Specific Activity 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 ------------------- NOTE--------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days I-131 specific activity is < 0.2 pCi/gm.

PBAPS UNIT 2 3. 4-15 Amendment No. 210

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

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

1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Initiate action to Immediately RHR shutdown cooling restore required RHR subsystems inoperable. shutdown cooling subsystem(s) to OPERABLE status.

AND (continued)

PBAPS UNIT 2 3.4-16 Amendment No. 210

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each required inoperable RHR shutdown cooling subsystem.

AND A.3 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. No RHR shutdown B.1 Initiate action to Immediately cooling subsystem in restore one RHR operation. shutdown cooling subsystem or one AND recirculation pump to operation.

No recirculation pump in operation. AND B.2 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from coolant circulation discovery of no by an alternate reactor coolant method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Monitor reactor Once per hour coolant temperature and pressure.

PBAPS UNIT-2 3.4-17 Amendment No. 210

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 -------------------NOTE--------------------

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

Verify one required RHR shutdown cooling 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystem or recirculation pump is operating.

PBAPS UNIT 2 3 .4-18 Amendment No. 210

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

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

1. Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY: MODE 4.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RHR shutdown cooling method of decay heat subsystems inoperable. removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 2 3 .4-19 Amendment No. 210

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem in coolant circulating discovery of no operation. by an alternate reactor coolant method. circulation AND AND No recirculation pump in operation. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Monitor reactor Once per hour coolant temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystem or recirculation pump is operating.

PBAPS UNIT 2 3.4-20 Amendment No. 210

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within limits.

APPLICABILITY: At all times.

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

shall be completed if this Condition is AND entered.

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

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

B. Required Action and B.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 AND not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

PBAPS UNIT 2 3.4-21 Amendment No. 210

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------NOTE--------- C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed if to within limits.

this Condition is entered. AND C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation. or 3.

than MODES 1, 2, and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------NOTE--------------------

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

Verify: 30 minutes

a. RCS pressure and RCS temperature are within the applicable limits specified in Figures 3.4.9-1 and 3.4.9-2; and

b. RCS heatup and cooldown rates are

< 100F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

(continued)

PBAPS UNIT 2 3.4-22 Amendment No. 210

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes Figure 3.4.9-3. prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3 --------------------NOTE-------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel (RPV) coolant temperature prior to each is = 145F. startup of a recirculation pump SR 3.4.9.4 ------------------- NOTE--------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes loop to be started and the RPV coolant prior to each temperature is 5 50F. startup of a recirculation pump (continued)

PBAPS UNIT 2 3.4-23 Amendment No. 210

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5 -------------------NOTE--------------------

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head 30 minutes flange temperatures are > 70F.

SR 3.4.9.6 -------------------NOTE--------------------

Not required to be performed until 30 minutes after RCS temperature s 80OF in MODE 4.

Verify reactor vessel flange and head 30 minutes flange temperatures are > 70*F.

SR 3.4.9.7 -------------------NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature 5 100*F in MODE 4.

Verify reactor vessel flange and head 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months flange temperatures are > 70F.

PBAPS UNIT 2 3.4-24 Amendment No. 210

RCS P/T Limits 3.4.9 1400

._1 W

a 1200 0

CLJ 0 1000' I-

-J U)

LJ Uf)

= 800 0

C),

IAn Z 600 5-J

' 400I En LO EL 200 0

0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-1 (page 1 of 1)

Temperature/Pressure Limits for Inservice Hydrostatic and Inservice Leakage Tests PBAPS UNIT 2 3 .4-25 Amendment No. 210

RCS P/T Limits 3.4.9 1600 1400 0~

CL 1200 _ - - 1 ___ __ _

0~

0 I-_ 1,000

-j Lr) 800

_ - - - I B - NON-NUCLEAR HEATUP/

- COOLDOWN UMIT 0

L (BASED ON FW NOZZLE) i B.,, - NON-NUCLEAR HEATUP/

- -COOLDOWN UMIT FOR z 600 _ - *BOTTOM HEAD REGION

/ 1'ITH RT NDT =52*F 1E

- .VESSEL DISCONTINUITY

- - - -IMITS U) 400 BOTTOM HEAD U)

Li

_ - . _ 7DISCONTINUITY UMGS 0M

- - CURVES B AND BS. ARE VAUD 200 FOR 32 EFFY OF OPERATION BOLTIJ 70-F ! 32 EFPY BELTUNE CURVE IS LESS INUMllNG THAN DISCONTINUITY CURV'E B 0

0 100 200 300 . 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 3.4.9-2 (page 1 of 1)

Temperature/Pressure Limits for Non-Nuclear Heatup and Cooldown Following a Shutdown PBAPS UNIT 2 !4o 3 3.4-26 Amendment No. 210

RCS P/T Limits 3.4.9 VALID 70 32 EFPY 1 . '- I 1400 BELTLINE 1/4 T FLAW WITH 32 EFPY SHIFT

1. PER *R.G.1.99,Rev 2 IS LESS LIMITING THAN NON-BELTLINE 0- 1200

.I 0~

EL 0 SAFE I- 1000 OPERATING w REGION

-j Li U)

En 800 0

0 z

600 M

0:

. . . I . I

-i NON-8ELTLINE M

- FW NOZZLE LIMITST U) 400 1/4 T FLAW, RTNDT = 52°F U,

hJ Lt En 200 z .

I -

1 i

I

I--- r=::;4 I -------

11 7'

1 a

BOLT PRELOAD TEMPERATURE = 70°F FLANGE REGION, RTNDT = 10°F . II

. . i

.i 0 ; I Ia 0 100 200 300 400 500 600 MINIMUM REACTOR VESEL METAL TEMPERATURE (OF)

Figure 3.4.9-3 (page 1 of 1)

Temperature/Pressure Limits for Criticality PBAPS UNIT-2 3.4-27 Amendment No. 210

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be c 1053 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to limit. within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months c 1053 psig.

PBAPS UNIT 2 3.4-28 Amendment No. 210

ML031150490

Text

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