Text

Part 090 ME2139 KPS (Kewaunee) Improved Technical Specifications 2010-10-21
	ML102020664
Person / Time
Site:	Kewaunee
Issue date:	02/02/2011
From:	Feintuch K; Plant Licensing Branch III
To:	Heacock D; Dominion Energy Kewaunee
	Feintuch K, NRR/DORL/LPL3-1, 415-3079
Shared Package
ML103350500	List: ML102020662; ML102020664; ML103360504; ML103370691; ML103480931; ML110260316;
References
	TAC ME2139
	Download: ML102020664 (276)
	v • d • e

TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 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 2.2 SL Violations 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 SHUTDOWN MARGIN (SDM) ........................................................................... 3.1.1-1 3.1.2 Core Reactivity ................................................................................................... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) ........................................................ 3.1.3-1 3.1.4 Rod Group Alignment Limits .............................................................................. 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits ......................................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits ............................................................................. 3.1.6-1 3.1.7 Rod Position Indication....................................................................................... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 2 ........................................................... 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ................................................................ 3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FNH ) .............................................. 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) .................................................................... 3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR) ....................................................... 3.2.4-1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation ............................................ 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation .......... 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation............................................... 3.3.3-1 3.3.4 Dedicated Shutdown System ............................................................................. 3.3.4-1 3.3.5 Loss of Offsite Power (LOOP) Diesel Generator (DG) Start Instrumentation .... 3.3.5-1 3.3.6 Containment Purge and Vent Isolation Instrumentation ..................................... 3.3.6-1 3.3.7 Control Room Post Accident Recirculation (CRPAR) System Actuation Instrumentation ............................................................................. 3.3.7-1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ..................................................................................... 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality .......................................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits .................................................... 3.4.3-1 3.4.4 RCS Loops - MODES 1 and 2............................................................................ 3.4.4-1 3.4.5 RCS Loops - MODE 3 ........................................................................................ 3.4.5-1 3.4.6 RCS Loops - MODE 4 ........................................................................................ 3.4.6-1 Kewaunee Power Station i Amendment 207

TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) (continued) 3.4.7 RCS Loops - MODE 5, Loops Filled................................................................... 3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled ............................................................ 3.4.8-1 3.4.9 Pressurizer ......................................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves ................................................................................ 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ....................................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ............................................................................ 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .................................................. 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation ......................................................... 3.4.15-1 3.4.16 RCS Specific Activity ........................................................................................ 3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity .............................................................. 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators...................................................................................................... 3.5.1-1 3.5.2 ECCS - Operating .............................................................................................. 3.5.2-1 3.5.3 ECCS - Shutdown .............................................................................................. 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) ............................................................. 3.5.4-1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment ....................................................................................................... 3.6.1-1 3.6.2 Containment Air Locks ....................................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ............................................................................. 3.6.3-1 3.6.4 Containment Pressure........................................................................................ 3.6.4-1 3.6.5 Containment Air Temperature ............................................................................ 3.6.5-1 3.6.6 Containment Spray and Cooling Systems.......................................................... 3.6.6-1 3.6.7 Spray Additive System ....................................................................................... 3.6.7-1 3.6.8 Shield Building.................................................................................................... 3.6.8-1 3.6.9 Vacuum Relief Valves ........................................................................................ 3.6.9-1 3.6.10 Shield Building Ventilation System (SBVS) ...................................................... 3.6.10-1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) .................................................................. 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................................................................ 3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and MFRV Bypass Valves................................................ 3.7.3-1 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs) ....................... 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System ................................................................... 3.7.5-1 3.7.6 Condensate Storage Tanks (CSTs) ................................................................... 3.7.6-1 3.7.7 Component Cooling (CC) System ...................................................................... 3.7.7-1 3.7.8 Service Water (SW) System............................................................................... 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)................................................................................... 3.7.9-1 3.7.10 Control Room Post Accident Recirculation (CRPAR) System ......................... 3.7.10-1 3.7.11 Control Room Air Conditioning (CRAC) Alternate Cooling System .................. 3.7.11-1 3.7.12 Auxiliary Building Special Ventilation (ASV) System ........................................ 3.7.12-1 3.7.13 Spent Fuel Pool Water Level............................................................................ 3.7.13-1 3.7.14 Spent Fuel Pool Boron Concentration .............................................................. 3.7.14-1 3.7.15 Spent Fuel Pool Storage .................................................................................. 3.7.15-1 3.7.16 Secondary Specific Activity .............................................................................. 3.7.16-1 Kewaunee Power Station ii Amendment 207

TABLE OF CONTENTS (continued) Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating ..................................................................................... 3.8.1-1 3.8.2 AC Sources - Shutdown ..................................................................................... 3.8.2-1 3.8.3 Diesel Fuel Oil and Lube Oil............................................................................... 3.8.3-1 3.8.4 DC Sources - Operating ..................................................................................... 3.8.4-1 3.8.5 DC Sources - Shutdown ..................................................................................... 3.8.5-1 3.8.6 Battery Parameters ............................................................................................ 3.8.6-1 3.8.7 Inverters - Operating .......................................................................................... 3.8.7-1 3.8.8 Inverters - Shutdown .......................................................................................... 3.8.8-1 3.8.9 Distribution Systems - Operating........................................................................ 3.8.9-1 3.8.10 Distribution Systems - Shutdown ..................................................................... 3.8.10-1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration .......................................................................................... 3.9.1-1 3.9.2 Nuclear Instrumentation ..................................................................................... 3.9.2-1 3.9.3 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level .... 3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level ..... 3.9.4-1 3.9.5 Refueling Cavity Water Level ............................................................................. 3.9.5-1 3.9.6 Containment Penetrations .................................................................................. 3.9.6-1 4.0 DESIGN FEATURES .................................................................................................. 4.0-1 4.1 Site Location.......................................................................................................... 4.0-1 4.2 Reactor Core ......................................................................................................... 4.0-1 4.3 Fuel Storage .......................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility ........................................................................................................ 5.1-1 5.2 Organization .......................................................................................................... 5.2-1 5.3 Unit Staff Qualifications ......................................................................................... 5.3-1 5.4 Procedures ............................................................................................................ 5.4-1 5.5 Programs and Manuals ......................................................................................... 5.5-1 5.6 Reporting Requirements ....................................................................................... 5.6-1 5.7 High Radiation Area .............................................................................................. 5.7-1 Kewaunee Power Station iii Amendment 207

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.

ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux signals (AFD) between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. 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.

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.

Kewaunee Power Station 1.1-1 Amendment 207

Definitions 1.1 1.1 Definitions CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE OPERATING LIMITS The COLR is the unit specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle.

These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.3.

Plant operation within these limits is addressed in individual Specifications.

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

The determination of DOSE EQUIVALENT I-131 shall be performed using ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

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

Kewaunee Power Station 1.1-2 Amendment 207

Definitions 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

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

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

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

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

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

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

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

Kewaunee Power Station 1.1-3 Amendment 207

Definitions 1.1 1.1 Definitions 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 Chapter 13, "Initial Test and Operation," of the USAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 1772 MWt.

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

a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.

However, with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck RCCA in the SDM calculation. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and

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

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.

Kewaunee Power Station 1.1-4 Amendment 207

Definitions 1.1 1.1 Definitions THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip actuating OPERATIONAL TEST device and verifying the OPERABILITY of all devices in the (TADOT) channel required for trip actuating device OPERABILITY.

The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

Kewaunee Power Station 1.1-5 Amendment 207

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

MODES REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE (keff) (a) TEMPERATURE POWER

(°F) 1 Power Operation 0.99 >5 NA 2 Startup 0.99 5 NA 3 Hot Standby < 0.99 NA 350 4 (b) < 0.99 NA 350 > Tavg > 200 Hot Shutdown 5 (b) < 0.99 NA 200 Cold Shutdown 6 (c) NA NA NA Refueling (a) Excluding decay heat.

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

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

Kewaunee Power Station 1.1-6 Amendment 207

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

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

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

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

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

EXAMPLES The following examples illustrate the use of logical connectors.

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

AND A.2 Restore . . .

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

Kewaunee Power Station 1.2-1 Amendment 207

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

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

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

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

Kewaunee Power Station 1.2-2 Amendment 207

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

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

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the 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 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 trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

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

a. Must exist concurrent with the first inoperability; and

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

Kewaunee Power Station 1.3-1 Amendment 207

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

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 hours1 days 0.143 weeks 0.0329 months ; or

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

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

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 hours0.333 days 0.0476 weeks 0.011 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ."

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

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 1.3-2 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours0.25 days 0.0357 weeks 0.00822 months AND in MODE 5 within 36 hours1.5 days 0.214 weeks 0.0493 months . A total of 6 hours0.25 days 0.0357 weeks 0.00822 months is allowed for reaching MODE 3 and a total of 36 hours1.5 days 0.214 weeks 0.0493 months (not 42 hours1.75 days 0.25 weeks 0.0575 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours0.125 days 0.0179 weeks 0.00411 months , the time allowed for reaching MODE 5 is the next 33 hours1.375 days 0.196 weeks 0.0452 months because the total time allowed for reaching MODE 5 is 36 hours1.5 days 0.214 weeks 0.0493 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours1.5 days 0.214 weeks 0.0493 months .

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

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

Kewaunee Power Station 1.3-3 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

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

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

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

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.

Kewaunee Power Station 1.3-4 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

inoperable.

B. One B.1 Restore Function Y 72 hours3 days 0.429 weeks 0.0986 months Function Y train to OPERABLE train status.

inoperable.

C. One C.1 Restore Function X 72 hours3 days 0.429 weeks 0.0986 months Function X train to OPERABLE train status.

inoperable.

OR AND C.2 Restore Function Y 72 hours3 days 0.429 weeks 0.0986 months One train to OPERABLE Function Y status.

train inoperable.

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

Kewaunee Power Station 1.3-5 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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.

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

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours0.167 days 0.0238 weeks 0.00548 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Kewaunee Power Station 1.3-6 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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 hours0.167 days 0.0238 weeks 0.00548 months provided this does not result in any subsequent valve being inoperable for > 4 hours0.167 days 0.0238 weeks 0.00548 months .

If the Completion Time of 4 hours0.167 days 0.0238 weeks 0.00548 months (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

EXAMPLE 1.3-5 ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours0.167 days 0.0238 weeks 0.00548 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

Kewaunee Power Station 1.3-7 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

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

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

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable.

OR A.2 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months POWER to 50% RTP.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated Completion Time not met.

Kewaunee Power Station 1.3-8 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours0.333 days 0.0476 weeks 0.011 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.

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

inoperable. AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND A.2 Restore subsystem 72 hours3 days 0.429 weeks 0.0986 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 1.3-9 Amendment 207

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

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 hours0.333 days 0.0476 weeks 0.011 months thereafter" interval begins upon performance of Required Action A.1.

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

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

Kewaunee Power Station 1.3-10 Amendment 207

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

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

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, "Surveillance Requirement (SR)

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

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

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be 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 criteria.

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

Kewaunee Power Station 1.4-1 Amendment 207

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

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

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

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

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

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

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours0.5 days 0.0714 weeks 0.0164 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 hours0.5 days 0.0714 weeks 0.0164 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

Kewaunee Power Station 1.4-2 Amendment 207

Frequency 1.4 1.4 Frequency EXAMPLES (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, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after 25% RTP AND 24 hours1 days 0.143 weeks 0.0329 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to 25% RTP, the Surveillance must be performed within 12 hours0.5 days 0.0714 weeks 0.0164 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 25% extension allowed by SR 3.0.2. "Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

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

Kewaunee Power Station 1.4-3 Amendment 207

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after 25% RTP.

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

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours0.5 days 0.0714 weeks 0.0164 months after power reaches 25% RTP to perform the Surveillance.

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

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours0.5 days 0.0714 weeks 0.0164 months (plus the extension allowed by SR 3.0.2) with power 25% RTP.

Once the unit reaches 25% RTP, 12 hours0.5 days 0.0714 weeks 0.0164 months would be allowed for completing the Surveillance. If the Surveillance was not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Kewaunee Power Station 1.4-4 Amendment 207

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours1 days 0.143 weeks 0.0329 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 was 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 was not met), SR 3.0.4 would require satisfying the SR.

Kewaunee Power Station 1.4-5 Amendment 207

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

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

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

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

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

Kewaunee Power Station 1.4-6 Amendment 207

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours1 days 0.143 weeks 0.0329 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance was not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency was not met), SR 3.0.4 would require satisfying the SR.

Kewaunee Power Station 1.4-7 Amendment 207

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 1.17 for the WRB-1 DNB correlation and 1.14 for the HTP DNB correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU of burnup.

2.1.2 Reactor Coolant System Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 2735 psig.

2.2 SAFETY LIMIT VIOLATIONS 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

Kewaunee Power Station 2.0-1 Amendment 207

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

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

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

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

a. MODE 3 within 7 hours0.292 days 0.0417 weeks 0.00959 months ;

b. MODE 4 within 13 hours0.542 days 0.0774 weeks 0.0178 months ; and

c. MODE 5 within 37 hours1.542 days 0.22 weeks 0.0507 months .

Exceptions to this Specification are stated in the individual Specifications.

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

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

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

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

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

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

Kewaunee Power Station 3.0-1 Amendment 207

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 (continued)

This Specification 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.

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

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

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

LCO 3.0.7 Test Exception LCO 3.1.8 allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

Kewaunee Power Station 3.0-2 Amendment 207

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

a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours3 days 0.429 weeks 0.0986 months ; or

b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 24 hours1 days 0.143 weeks 0.0329 months .

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

Kewaunee Power Station 3.0-3 Amendment 207

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

Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

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

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

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

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

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours1 days 0.143 weeks 0.0329 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 hours1 days 0.143 weeks 0.0329 months and the risk impact shall be managed.

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

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

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

Kewaunee Power Station 3.0-4 Amendment 207

SR Applicability 3.0 3.0 SR Applicability SR 3.0.4 (continued)

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

Kewaunee Power Station 3.0-5 Amendment 207

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

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

APPLICABILITY: MODE 2 with keff < 1.0, MODES 3, 4, and 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within the limits specified in the 24 hours1 days 0.143 weeks 0.0329 months COLR.

Kewaunee Power Station 3.1.1-1 Amendment 207

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

APPLICABILITY: MODES 1 and 2.

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

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

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.1.2-1 Amendment 207

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ---------------------------NOTE----------------------------------

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

Verify measured core reactivity is within +/- 1% k/k Once prior to of predicted values. entering MODE 1 after each refueling AND

NOTE--------

Only required after 60 EFPD 31 EFPD thereafter Kewaunee Power Station 3.1.2-2 Amendment 207

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

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be 5 pcm/°F with THERMAL POWER 60%

RTP and 0 pcm/°F with THERMAL POWER > 60% RTP.

APPLICABILITY: MODE 1 and MODE 2 with keff 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish administrative 24 hours1 days 0.143 weeks 0.0329 months limit. withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion keff < 1.0.

Time of Condition A not met.

C. MTC not within lower C.1 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Prior to entering MODE 1 after each refueling Kewaunee Power Station 3.1.3-1 Amendment 207

MTC 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.3.2 ---------------------------NOTES--------------------------------

1. Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm.

2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.

3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.

Verify MTC is within lower limit. Once each cycle Kewaunee Power Station 3.1.3-2 Amendment 207

Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.

AND Individual indicated rod positions shall be as follows:

a. With THERMAL POWER 85% RTP, within 12 steps from their respective banks; and

b. With THERMAL POWER < 85% RTP, within 24 steps from their respective banks.

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

Individual rod position indictors may be outside of their limits for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following substantial rod movement.

APPLICABILITY: MODES 1 and 2.

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

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

AND 6 hours0.25 days 0.0357 weeks 0.00822 months A.2 Be in MODE 3.

Kewaunee Power Station 3.1.4-1 Amendment 207

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

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

THERMAL POWER is 85% RTP. OR B.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limits.

AND B.2 Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months POWER to < 85% RTP.

Kewaunee Power Station 3.1.4-2 Amendment 207

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

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

THERMAL POWER is

< 85% RTP. OR C.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limits.

AND C.2 Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months POWER to < 50% RTP.

AND C.3 Verify SDM is within limits Once per specified in the COLR. 12 hours0.5 days 0.0714 weeks 0.0164 months AND C.4 Perform SR 3.2.1.1 and 72 hours3 days 0.429 weeks 0.0986 months SR 3.2.1.2.

AND C.5 Perform SR 3.2.2.1. 72 hours3 days 0.429 weeks 0.0986 months AND C.6 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition B or C not met.

Kewaunee Power Station 3.1.4-3 Amendment 207

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. More than one rod not E.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment limit. limits specified in the COLR.

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

AND E.2 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.1.4.2 Verify rod freedom of movement (trippability) by 92 days moving each rod not fully inserted in the core 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to criticality withdrawn position, is 1.8 seconds from the after each beginning of decay of stationary gripper coil voltage removal of the to dashpot entry, with: reactor head

a. Tavg 500°F and

b. All reactor coolant pumps operating.

Kewaunee Power Station 3.1.4-4 Amendment 207

Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within insertion limits specified in the COLR.

APPLICABILITY: MODES 1 and 2.

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

This LCO is not applicable while performing SR 3.1.4.2.

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

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

AND A.2 Restore shutdown banks to 2 hours0.0833 days 0.0119 weeks 0.00274 months within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.1.5-1 Amendment 207

Shutdown Bank Insertion Limits 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the insertion 12 hours0.5 days 0.0714 weeks 0.0164 months limits specified in the COLR.

Kewaunee Power Station 3.1.5-2 Amendment 207

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR.

APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

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

This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits not met. limits specified in the COLR.

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

AND A.2 Restore control bank(s) to 2 hours0.0833 days 0.0119 weeks 0.00274 months within limits.

B. Control bank sequence B.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or overlap limits not met. limits specified in the COLR.

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

AND Kewaunee Power Station 3.1.6-1 Amendment 207

Control Bank Insertion Limits 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Restore control bank 2 hours0.0833 days 0.0119 weeks 0.00274 months sequence and overlap to within limits.

C. Required Action and C.1 Be in MODE 2 with keff 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion < 1.0.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank position is Within 4 hours0.167 days 0.0238 weeks 0.00548 months within the insertion limits specified in the COLR. prior to achieving criticality SR 3.1.6.2 Verify each control bank insertion is within the 12 hours0.5 days 0.0714 weeks 0.0164 months insertion limits specified in the COLR.

SR 3.1.6.3 Verify sequence and overlap limits specified in the 12 hours0.5 days 0.0714 weeks 0.0164 months COLR are met for control banks not fully withdrawn from the core.

Kewaunee Power Station 3.1.6-2 Amendment 207

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Individual Rod Position Indication (IRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One IRPI per group A.1 Verify the position of the Once per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable for one or rod with an inoperable more groups. position indicator indirectly AND by using movable incore detectors. 4 hours0.167 days 0.0238 weeks 0.00548 months after a rod with an inoperable position indicator has been moved in excess of 24 steps in one direction since the last determination of the rod's position OR A.2 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months POWER to 50% RTP.

B. More than one IRPI per B.1 Place the control rods Immediately group inoperable. under manual control.

AND Kewaunee Power Station 3.1.7-1 Amendment 207

Rod Position Indication 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Monitor and record Reactor Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Coolant System Tavg.

AND B.3 Restore inoperable position 24 hours1 days 0.143 weeks 0.0329 months indicators to OPERABLE status such that a maximum of one IRPI per group is inoperable.

C. One demand position C.1.1 Verify by administrative Once per 8 hours0.333 days 0.0476 weeks 0.011 months indicator per bank means all IRPIs for the inoperable for one or affected bank are more banks. OPERABLE.

AND C.1.2 Verify the most withdrawn Once per 8 hours0.333 days 0.0476 weeks 0.011 months rod and the least withdrawn rod of the affected bank are within the required rod alignment limits of LCO 3.1.4, "Rod Group Alignment Limits."

OR C.2 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months POWER to 50% RTP.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.1.7-2 Amendment 207

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Perform CHANNEL CALIBRATION of each IRPI. 18 months SR 3.1.7.2 Perform system functional test of the Demand 18 months Position Indication System.

Kewaunee Power Station 3.1.7-3 Amendment 207

PHYSICS TESTS Exceptions - MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of:

LCO 3.1.3, "Moderator Temperature Coefficient;"

LCO 3.1.4, "Rod Group Alignment Limits;"

LCO 3.1.5, "Shutdown Bank Insertion Limits;"

LCO 3.1.6, "Control Bank Insertion Limits;" and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended and the number of required channels for LCO 3.3.1, "RPS Instrumentation," Functions 2, 3, 6 and 16.d, may be reduced to 3 required channels, provided:

a. RCS lowest loop average temperature is 530°F;

b. SDM is within the limits specified in the COLR; and

c. THERMAL POWER is < 5% RTP.

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2.

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

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

B. THERMAL POWER not B.1 Open reactor trip breakers. Immediately within limit.

C. RCS lowest loop C.1 Restore RCS lowest loop 15 minutes average temperature not average temperature to within limit. within limit.

Kewaunee Power Station 3.1.8-1 Amendment 207

PHYSICS TESTS Exceptions - MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify the RCS lowest loop average temperature is 30 minutes 530°F.

SR 3.1.8.2 Verify THERMAL POWER is < 5% RTP. 30 minutes SR 3.1.8.3 Verify SDM is within the limits specified in the 24 hours1 days 0.143 weeks 0.0329 months COLR.

Kewaunee Power Station 3.1.8-2 Amendment 207

FQ(Z) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FQ(Z), as approximated by FQC ( Z ) and FQT (Z) , shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

NOTE-------------- A.1 Reduce THERMAL 15 minutes after each Required Action A.4 shall be POWER 1% RTP for FQC ( Z) determination completed whenever this each 1% FQC ( Z ) exceeds Condition is entered. limit.

AND A. FQC ( Z) not within limit.

A.2 Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months after each Neutron Flux - High trip FQC ( Z) determination setpoints 1% for each 1% FQC ( Z) exceeds limit.

AND A.3 Reduce Overpower T trip 72 hours3 days 0.429 weeks 0.0986 months after each setpoints 1% for each FQC ( Z) determination 1% FQC ( Z) exceeds limit.

AND A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 Kewaunee Power Station 3.2.1-1 Amendment 207

FQ(Z) 3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE-------------- B.1 Reduce AFD limits 1% for 4 hours0.167 days 0.0238 weeks 0.00548 months Required Action B.4 shall be each 1% FQT (Z) exceeds completed whenever this limit.

Condition is entered.

AND B. FQT (Z) not within limits. B.2 Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months Neutron Flux - High trip setpoints 1% for each 1%

that the maximum allowable power of the AFD limits is reduced.

AND B.3 Reduce Overpower T trip 72 hours3 days 0.429 weeks 0.0986 months setpoints 1% for each 1%

that the maximum allowable power of the AFD limits is reduced.

AND B.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the maximum allowable power of the AFD limits C. Required Action and C.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.2.1-2 Amendment 207

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS

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

During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify FQC ( Z ) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQC ( Z ) was last verified AND 31 EFPD thereafter Kewaunee Power Station 3.2.1-3 Amendment 207

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 -------------------------------NOTE------------------------------

If measurements indicate that the maximum over z [ FQC ( Z ) / K(Z) ]

has increased since the previous evaluation of FQC ( Z) :

a. Increase FQT ( Z ) by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify FQT ( Z ) is within limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either

a. above is met or two successive flux maps indicate that the maximum over z [ FQC ( Z ) / K(Z) ]

has not increased.

Verify FQT ( Z ) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQT ( Z ) was last verified AND 31 EFPD thereafter Kewaunee Power Station 3.2.1-4 Amendment 207

FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( FNH )

LCO 3.2.2 FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months Required Actions A.2 POWER to < 50% RTP.

and A.4 must be completed whenever AND Condition A is entered.

A.2 Perform SR 3.2.2.1. 24 hours1 days 0.143 weeks 0.0329 months FNH not within limit. AND A.3. Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months Neutron Flux - High trip setpoints to 55% RTP.

AND Kewaunee Power Station 3.2.2-1 Amendment 207

FNH 3.2.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 --------------NOTE--------------

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER reaching 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.2.2-2 Amendment 207

FNH 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FNH is within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter Kewaunee Power Station 3.2.2-3 Amendment 207

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.

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

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore 7 days channel.

Kewaunee Power Station 3.2.3-1 Amendment 207

QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be 1.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months after each POWER 3% from RTP for QPTR determination each 1% of QPTR > 1.00.

AND A.2 Determine QPTR. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months AND A.3 Perform SR 3.2.1.1, 24 hours1 days 0.143 weeks 0.0329 months after SR 3.2.1.2, and SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND Kewaunee Power Station 3.2.4-1 Amendment 207

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Reevaluate safety analyses Prior to increasing and confirm results remain THERMAL POWER valid for duration of above the limit of operation under this Required Action A.1 condition.

AND A.5 -------------NOTES-------------

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required Action A.6 shall be completed whenever Required Action A.5 is performed.

Normalize excore detectors Prior to increasing to restore QPTR to within THERMAL POWER limit. above the limit of Required Action A.1 AND A.6 ---------------NOTE--------------

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1, Within 24 hours1 days 0.143 weeks 0.0329 months after SR 3.2.1.2, and SR 3.2.2.1. achieving equilibrium conditions at RTP not to exceed 48 hours2 days 0.286 weeks 0.0658 months after increasing THERMAL POWER above the limit of Required Action A.1 Kewaunee Power Station 3.2.4-2 Amendment 207

QPTR 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to 50% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ------------------------------NOTES-----------------------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation. 7 days SR 3.2.4.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER

> 75% RTP.

Verify QPTR is within limit using the movable incore 12 hours0.5 days 0.0714 weeks 0.0164 months detectors.

Kewaunee Power Station 3.2.4-3 Amendment 207

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

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One Manual Reactor B.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Trip channel inoperable. OPERABLE status.

OR B.2 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months C. One channel or train C.1 Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR C.2.1 Initiate action to fully insert 48 hours2 days 0.286 weeks 0.0658 months all rods.

AND Kewaunee Power Station 3.3.1-1 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.2 Place the Rod Control 49 hours2.042 days 0.292 weeks 0.0671 months System in a condition incapable of rod withdrawal.

D. One Power Range --------------------NOTE-------------------

Neutron Flux - High The inoperable channel may be channel inoperable. bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing and setpoint adjustment of other channels.

D.1.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months AND D.1.2 Reduce THERMAL 78 hours3.25 days 0.464 weeks 0.107 months POWER to 75% RTP.

OR D.2.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months AND D.2.2 --------------NOTE--------------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

Perform SR 3.2.4.2. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months OR D.3 Be in MODE 3. 78 hours3.25 days 0.464 weeks 0.107 months Kewaunee Power Station 3.3.1-2 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

E.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR E.2 Be in MODE 3. 78 hours3.25 days 0.464 weeks 0.107 months F. One Intermediate Range F.1 Reduce THERMAL 24 hours1 days 0.143 weeks 0.0329 months Neutron Flux channel POWER to < P-6.

inoperable.

OR F.2 Increase THERMAL 24 hours1 days 0.143 weeks 0.0329 months POWER to > P-10.

G. Two Intermediate Range G.1 --------------NOTE--------------

Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

AND G.2 Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months POWER to < P-6.

Kewaunee Power Station 3.3.1-3 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One Source Range --------------------NOTE-------------------

Neutron Flux channel Limited plant cooldown or boron inoperable. dilution is allowed provided the change is accounted for in the calculated SDM.

H.1 Suspend operations Immediately involving positive reactivity additions.

I. Two Source Range I.1 Open reactor trip breakers Immediately Neutron Flux channels (RTBs).

inoperable.

J. One Source Range J.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Neutron Flux channel OPERABLE status.

inoperable.

OR J.2.1 Initiate action to fully insert 48 hours2 days 0.286 weeks 0.0658 months all rods.

AND J.2.2. Place the Rod Control 49 hours2.042 days 0.292 weeks 0.0671 months System in a condition incapable of rod withdrawal.

K. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

K.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR K.2 Reduce THERMAL 78 hours3.25 days 0.464 weeks 0.107 months POWER to < P-7.

Kewaunee Power Station 3.3.1-4 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One Reactor Coolant --------------------NOTE-------------------

Pump Breaker Position The inoperable channel may be (Single Loop) channel bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for inoperable. surveillance testing of other channels.

L.1 Restore channel to 6 hours0.25 days 0.0357 weeks 0.00822 months OPERABLE status.

OR L.2 Reduce THERMAL 10 hours0.417 days 0.0595 weeks 0.0137 months POWER to < P-8.

M. One Reactor Coolant --------------------NOTE-------------------

Pump Breaker Position The inoperable channel may be (Two Loops) channel bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for inoperable. surveillance testing of other channels.

M.1 Place the channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR M.2 Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months POWER to <P-7.

N. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing provided the other train is OPERABLE.

N.1 Restore train to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

OR N.2 Be in MODE 3. 30 hours1.25 days 0.179 weeks 0.0411 months Kewaunee Power Station 3.3.1-5 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One RTB train --------------------NOTE------------------

inoperable. One train may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing, provided the other train is OPERABLE.

O.1 Restore train to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

OR O.2 Be in MODE 3. 30 hours1.25 days 0.179 weeks 0.0411 months P. One or more channels P.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR P.2 Be in MODE 3. 7 hours0.292 days 0.0417 weeks 0.00959 months Q. One or more channels Q.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR Q.2 Be in MODE 2. 7 hours0.292 days 0.0417 weeks 0.00959 months R. One trip mechanism R.1 Restore inoperable trip 48 hours2 days 0.286 weeks 0.0658 months inoperable for one RTB. mechanism to OPERABLE status.

OR R.2 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months Kewaunee Power Station 3.3.1-6 Amendment 207

RPS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME S. One Turbine Trip --------------------NOTE------------------

channel inoperable. The inoperable channel may be bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

S.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR S.2 Reduce THERMAL 76 hours3.167 days 0.452 weeks 0.104 months POWER to < P-7 Kewaunee Power Station 3.3.1-7 Amendment 207

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.1.2 -----------------------------NOTE-------------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance 24 hours1 days 0.143 weeks 0.0329 months calculation to power range channel output. Adjust power range channel output if calorimetric heat balance calculations results exceed power range channel output by more than +2% RTP.

SR 3.3.1.3 -----------------------------NOTE-------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER is 15% RTP.

Compare results of the incore detector 31 effective full measurements to Nuclear Instrumentation System power days (NIS) AFD. Adjust NIS channel if absolute (EFPD) difference is 3%.

SR 3.3.1.4 ------------------------------NOTE-------------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT. 31 days Kewaunee Power Station 3.3.1-8 Amendment 207

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.5 ---------------------------NOTES--------------------------------

1. For Function 16.b, when 10% RTP, the SR consists only of verifying the P-7 interlock is in its required state. However, all the applicable requirements of an ACTUATION LOGIC TEST are required to be performed within 12 hours0.5 days 0.0714 weeks 0.0164 months of reducing THERMAL POWER to < 10% RTP.

2. For Function 19, testing the logic matrix associated with Functions 2.b, 4, and 5, when 10% RTP consists only of verifying the logic is in its required state. However, all applicable requirements of an ACTUATION LOGIC TEST are required to be performed within 12 hours0.5 days 0.0714 weeks 0.0164 months of reducing THERMAL POWER to <10% RTP.

3. For Function 19, this SR does not include testing the logic matrices associated with Functions 11.a, 11.b, 13, (tested by SR 3.3.1.16) and Safety Injection-Reactor Trip (tested by SR. 3.8.1.16).

Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.1.6 ------------------------------NOTE-------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER is 50% RTP.

Calibrate excore channels to agree with incore 92 EFPD detector measurements.

SR 3.3.1.7 ------------------------------NOTE-------------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours0.167 days 0.0238 weeks 0.00548 months after entry into MODE 3.

Perform COT in accordance with the Setpoint 184 days Control Program.

Kewaunee Power Station 3.3.1-9 Amendment 207

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.8 ------------------------------NOTE-------------------------------

This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT in accordance with the Setpoint --------NOTE--------

Control Program. Only required when not performed within previous 184 days Prior to reactor startup AND Four hours after reducing power below P-6 for source range instrumentation AND Twelve hours after reducing power below P-10 for power and intermediate range instrumentation AND Every 184 days thereafter SR 3.3.1.9 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. 92 days Kewaunee Power Station 3.3.1-10 Amendment 207

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.10 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

SR 3.3.1.11 ------------------------------NOTE-------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

SR 3.3.1.12 ------------------------------NOTE-------------------------------

This Surveillance shall include verification of Reactor Coolant System resistance temperature detector bypass loop flow rate.

Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

SR 3.3.1.13 Perform COT. 18 months SR 3.3.1.14 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3.1.15 ------------------------------NOTE-------------------------------

Verification of setpoint is not required.

Perform TADOT. Prior to exceeding the P-7 interlock whenever the unit has been in MODE 3, if not performed within the previous 31 days Kewaunee Power Station 3.3.1-11 Amendment 207

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.16 Perform ACTUATION LOGIC TEST for Functions 18 months 11.a, 11.b, and 13.

Kewaunee Power Station 3.3.1-12 Amendment 207

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

Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

1. Manual Reactor Trip 1,2 2 B SR 3.3.1.14 (a) (a) (a) 2 C SR 3.3.1.14 3 ,4 ,5

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11

b. Low (b) 4 E SR 3.3.1.1 1 ,2 SR 3.3.1.8 SR 3.3.1.11

3. Power Range Neutron Flux Rate

a. High Positive Rate 1,2 4 E SR 3.3.1.7 SR 3.3.1.11

b. High Negative Rate 1,2 4 E SR 3.3.1.7 SR 3.3.1.11

4. Intermediate Range Neutron Flux (b) (c) 2 F,G SR 3.3.1.1 1 ,2 SR 3.3.1.8 SR 3.3.1.11

5. Source Range Neutron Flux (d) 2 H,I SR 3.3.1.1 2

SR 3.3.1.8 SR 3.3.1.11 (a) (a) (a) 2 I,J SR 3.3.1.1 3 ,4 ,5 SR 3.3.1.7 SR 3.3.1.11

6. Overtemperature T 1,2 4 E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12

7. Overpower T 1,2 4 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.12 (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) Below the P-10 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

Kewaunee Power Station 3.3.1-13 Amendment 207

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

Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

8. Pressurizer Pressure (e)

a. Low 1 4 K SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10

b. High 1,2 3 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 (e)

9. Pressurizer Water Level - High 1 3 K SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 (f)

10. Reactor Coolant Flow - Low 1 3 per loop K SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10

11. Reactor Coolant Pump (RCP)

Breaker Position (f)

a. Single Loop 1 1 per RCP L SR 3.3.1.14 (e)

b. Two Loops 1 1 per RCP M SR 3.3.1.14 (e)

12. Undervoltage RCPs 1 2 per bus K SR 3.3.1.9 SR 3.3.1.10 (e)

13. Underfrequency RCPs 1 2 per bus K SR 3.3.1.9 SR 3.3.1.10

14. Steam Generator (SG) Water 1,2 3 per SG E SR 3.3.1.1 Level - Low Low SR 3.3.1.7 SR 3.3.1.10

15. SG Water Level - Low 1,2 2 per SG E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 Coincident with Steam 1,2 2 per SG E SR 3.3.1.1 Flow/Feedwater Flow Mismatch SR 3.3.1.7 SR 3.3.1.10 (e) Above the P-7 (Low Power Reactor Trips Block) interlock.

(f) Above the P-8 (Power Range Neutron Flux) interlock.

Kewaunee Power Station 3.3.1-14 Amendment 207

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

Reactor Protection System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

16. Reactor Protection System Interlocks (d)

a. Intermediate Range Neutron 2 2 P SR 3.3.1.11 Flux, P-6 SR 3.3.1.13

b. Low Power Reactor Trips Block, 1 1 per train Q SR 3.3.1.5 P-7

c. Power Range Neutron Flux, P-8 1 4 Q SR 3.3.1.11 SR 3.3.1.13

d. Power Range Neutron Flux, 1,2 4 P SR 3.3.1.11 P-10 SR 3.3.1.13

e. Turbine Impulse Pressure, P-13 1 2 Q SR 3.3.1.1 SR 3.3.1.10 SR 3.3.1.13 (g)

17. Reactor Trip Breakers (RTBs) 1,2 2 trains O SR 3.3.1.4 (b) (b) (b) 3 ,4 ,5 2 trains C SR 3.3.1.4

18. Reactor Trip Breaker Undervoltage 1,2 2 each per RTB R SR 3.3.1.4 and Shunt Trip Mechanisms (b) (b) (b) 3 ,4 ,5 2 each per RTB C SR 3.3.1.4

19. Automatic Trip Logic 1,2 2 trains N SR 3.3.1.5 SR 3.3.1.16 (b) (b) (b) 3 ,4 ,5 2 trains C SR 3.3.1.5 SR 3.3.1.16

20. Turbine Trip (e)

a. Low Fluid Oil Pressure 1 3 S SR 3.3.1.10 SR 3.3.1.15 (e)

b. Turbine Stop Valve Closure 1 2 S SR 3.3.1.15 (b) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e) Above the P-7 (Low Power Reactor Trips Block) interlock.

(g) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

Kewaunee Power Station 3.3.1-15 Amendment 207

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.2-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One channel or train B.1 Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months AND B.2.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months Kewaunee Power Station 3.3.2-1 Amendment 207

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing provided the other train is OPERABLE.

C.1 Restore train to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

OR C.2.1 Be in MODE 3. 30 hours1.25 days 0.179 weeks 0.0411 months AND C.2.2 Be in MODE 5. 60 hours2.5 days 0.357 weeks 0.0822 months D. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

D.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR D.2.1 Be in MODE 3. 78 hours3.25 days 0.464 weeks 0.107 months AND D.2.2 Be in MODE 4. 84 hours3.5 days 0.5 weeks 0.115 months Kewaunee Power Station 3.3.2-2 Amendment 207

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment --------------------NOTE-------------------

Pressure channel One additional channel may be inoperable. bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

E.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR E.2.1 Be in MODE 3. 78 hours3.25 days 0.464 weeks 0.107 months AND E.2.2 Be in MODE 4. 84 hours3.5 days 0.5 weeks 0.115 months F. One channel or train F.1 Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR F.2.1 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months AND F.2.2 Be in MODE 4. 60 hours2.5 days 0.357 weeks 0.0822 months G. One train inoperable. --------------------NOTE-------------------

One train may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing provided the other train is OPERABLE.

G.1 Restore train to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

OR G.2.1 Be in MODE 3. 30 hours1.25 days 0.179 weeks 0.0411 months AND Kewaunee Power Station 3.3.2-3 Amendment 207

ESFAS Instrumentation 3.3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G. (continued) G.2.2 Be in MODE 4. 36 hours1.5 days 0.214 weeks 0.0493 months H. One channel inoperable. --------------------NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours0.5 days 0.0714 weeks 0.0164 months for surveillance testing of other channels.

H.1 Place channel in trip. 72 hours3 days 0.429 weeks 0.0986 months OR H.2 Be in MODE 3. 78 hours3.25 days 0.464 weeks 0.107 months I. One Main Feedwater I.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Pumps trip channel OPERABLE status.

inoperable.

OR I.2 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months J. One or more trains or J.1 Declare the associated Immediately channels inoperable. Service Water (SW) train inoperable.

Kewaunee Power Station 3.3.2-4 Amendment 207

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.2.2 ------------------------------NOTE-------------------------------

For Function 4.b, when steam flow is the Hi Steam Flow nominal trip setpoint, the Hi Steam Flow logic portion of this SR consists only of verifying the Hi Steam Flow logic is in its required state. However, all applicable requirements of an ACTUATION LOGIC TEST are required to be performed within 12 hours0.5 days 0.0714 weeks 0.0164 months of reducing steam flow < the Hi Steam Flow nominal trip setpoint.

Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.3 ------------------------------NOTE-------------------------------

Verification of relay setpoints not required.

Perform TADOT. 92 days SR 3.3.2.4 Perform COT in accordance with the Setpoint 184 days Control Program.

SR 3.3.2.5 ------------------------------NOTE-------------------------------

Verification of setpoint not required for manual initiation functions.

Perform TADOT. 18 months SR 3.3.2.6 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

Kewaunee Power Station 3.3.2-5 Amendment 207

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.7 ------------------------------NOTE-------------------------------

Verification of setpoint not required.

Perform TADOT. Prior to closing the reactor trip breaker or reactor trip bypass breaker following each reactor trip breaker cycle SR 3.3.2.8 Perform ACTUATION LOGIC TEST. 18 months Kewaunee Power Station 3.3.2-6 Amendment 207

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 3)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

1. Safety Injection

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.5

b. Automatic Actuation Logic and 1,2,3,4 2 trains C SR 3.3.2.2 Actuation Relays

c. Containment Pressure - High 1,2,3 3 D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6

d. Pressurizer Pressure - Low (a) 3 D SR 3.3.2.1 1,2,3 SR 3.3.2.4 SR 3.3.2.6

e. Steam Line Pressure - Low (a) 3 per steam line D SR 3.3.2.1 1,2,3 SR 3.3.2.4 SR 3.3.2.6

2. Containment Spray

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.5

b. Automatic Actuation Logic and 1,2,3,4 2 trains C SR 3.3.2.2 Actuation Relays

c. Containment Pressure - High 1,2,3 3 sets of 2 E SR 3.3.2.1 High SR 3.3.2.4 SR 3.3.2.6

3. Containment Isolation

a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.5

b. Automatic Actuation Logic and 1,2,3,4 2 trains C SR 3.3.2.2 Actuation Relays

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

4. Steam Line Isolation (b) (b)

a. Manual Initiation 1,2 ,3 2 F SR 3.3.2.5 (b) (b)

b. Automatic Actuation Logic and 1,2 ,3 2 trains G SR 3.3.2.2 Actuation Relays (a) With pressurizer pressure 2000 psig.

(b) Except when all MSIVs are closed and de-activated.

Kewaunee Power Station 3.3.2-7 Amendment 207

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 3)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

4. Steam Line Isolation (b) (b)

c. Containment Pressure - High 1, 2 ,3 3 D SR 3.3.2.1 High SR 3.3.2.4 SR 3.3.2.6 (b) (b)

d. High Steam Flow 1,2 ,3 2 per steam line D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6 Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

and (b) (b) (c)

Coincident with Tavg - Low Low 1,2 ,3 2 per loop D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6 (b) (b)

e. High High Steam Flow 1,2 ,3 2 per steam line D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6 Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

5. Feedwater Isolation (d) (d)

a. Automatic Actuation Logic and 1,2 ,3 2 trains G SR 3.3.2.2 Actuation Relays (d) (d)

b. SG Water Level - High High 1,2 ,3 3 per SG D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

6. Auxiliary Feedwater

a. Automatic Actuation Logic and 1,2,3 2 trains G SR 3.3.2.2 Actuation Relays

b. SG Water Level - Low Low 1,2,3 3 per SG D SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.6

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d. Undervoltage Reactor Coolant 1,2 2 per bus H SR 3.3.2.3 Pump SR 3.3.2.6 (b) Except when all MSIVs are closed and de-activated.

(c) Reactor Coolant System (RCS) Tavg 540°F.

(d) Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

Kewaunee Power Station 3.3.2-8 Amendment 207

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS

6. Auxiliary Feedwater

e. Trip of both Main Feedwater 1,2 1 per pump I SR 3.3.2.5 Pumps

7. Turbine Building Service Water Header Isolation (e) (e) (e)

a. Automatic Actuation Logic and 1 ,2 ,3 2 trains J SR 3.3.2.8 Actuation Relays (e) (e) (e)

b. Service Water Pressure - Low 1 ,2 ,3 2 J SR 3.3.2.4 SR 3.3.2.6 Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

8. ESFAS Interlocks - Reactor Trip, P-4 1,2,3 1 per train F SR 3.3.2.7 (e) Except when one turbine building service water header isolation valve is closed and de-activated.

Kewaunee Power Station 3.3.2-9 Amendment 207

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

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

channel inoperable.

B. Required Action and B.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.4.

Time of Condition A not met.

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

inoperable.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition C not for the channel.

met.

Kewaunee Power Station 3.3.3-1 Amendment 207

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action D.1 and referenced in AND Table 3.3.3-1.

E.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS

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

These SRs apply to each PAM instrumentation Function in Table 3.3.3-1 except where identified in the SR.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 Perform CHANNEL CALIBRATION for Function 20. 12 months SR 3.3.3.3 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for Functions 18 months other than Function 20.

Kewaunee Power Station 3.3.3-2 Amendment 207

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 2)

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

1. Intermediate Range Neutron Flux 2 E

2. Steam Generator Pressure 2 per steam generator E

3. Reactor Coolant System (RCS) Hot Leg 2 E Temperature

4. RCS Cold Leg Temperature 2 E

5. RCS Pressure (Wide Range) 2 E

6. Coolant Inventory (Reactor Vessel Level Indicating System)

a. Reactor Coolant Pumps (RCPs) ON 2 E

b. RCPs OFF 2 E

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

8. Containment Pressure (Wide Range) 2 E

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

10. Containment Area Radiation (High Range) 2 E

11. Pressurizer Level 2 E

12. Steam Generator Water Level (Wide Range) 2 per steam generator E

13. Auxiliary Feedwater (AFW) System Service Water (SW) Supply

a. SW Supply Valve to AFW Pumps 3 E

b. SW Pump Breaker Indication 1 per pump E

c. SW Pump Amp Indication 1 per pump E

14. Core Exit Temperature - Quadrant 1 4 E

15. Core Exit Temperature - Quadrant 2 4 E

16. Core Exit Temperature - Quadrant 3 4 E

17. Core Exit Temperature - Quadrant 4 4 E

18. RCS Subcooling Margin Monitor 2 E

19. Steam Generator Level (Narrow Range) 2 per steam generator E (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

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

Kewaunee Power Station 3.3.3-3 Amendment 207

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 2 of 2)

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

20. Refueling Water Storage Tank Level 2 E

21. Heat Removal by the Containment Fan Coil Units 4 E (Service Water Supply Valve Position Indication)

Kewaunee Power Station 3.3.3-4 Amendment 207

Dedicated Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Dedicated Shutdown System LCO 3.3.4 The Dedicated Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each Function.

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

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

Kewaunee Power Station 3.3.4-1 Amendment 207

Dedicated Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.3 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each 18 months required instrumentation channel.

Kewaunee Power Station 3.3.4-2 Amendment 207

LOOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Offsite Power (LOOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 One channel per bus of the Safeguards Bus Undervoltage (loss of voltage) Function and one channel per bus of the Safeguards Bus Second Level Undervoltage (degraded voltage) Function shall be OPERABLE.

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

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 --------------NOTES-------------

with one required 1. Only applicable if channel per bus inoperable channel is the inoperable. result of one inoperable relay.

2. The inoperable relay may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of the other relay of the channel.

Place affected portion of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the required channel in trip.

OR A.2 Restore required channel to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

Kewaunee Power Station 3.3.5-1 Amendment 207

LOOP DG Start Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Enter applicable Immediately associated Completion Condition(s) and Required Time not met. Action(s) for the associated DG made inoperable by LOOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform TADOT in accordance with the Setpoint 31 days Control Program.

SR 3.3.5.2 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

Kewaunee Power Station 3.3.5-2 Amendment 207

Containment Purge and Vent Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Purge and Vent Isolation Instrumentation LCO 3.3.6 The Containment Purge and Vent Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitoring A.1 Restore the affected 4 hours0.167 days 0.0238 weeks 0.00548 months channel inoperable. channel to OPERABLE status.

B. ------------NOTE------------ B.1 Enter applicable Conditions Immediately Only applicable in and Required Actions of MODE 1, 2, 3, OR 4. LCO 3.6.3, "Containment

Isolation Valves," for containment purge and vent One or more Functions isolation valves made with one or more inoperable by isolation automatic actuation instrumentation.

trains inoperable.

OR Two or more radiation monitoring channels inoperable.

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

Kewaunee Power Station 3.3.6-1 Amendment 207

Containment Purge and Vent Isolation Instrumentation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Place and maintain Immediately Only applicable during containment purge and vent movement of irradiated valves in closed position.

fuel assemblies within containment. OR C.2 Enter applicable Conditions Immediately One or more Functions and Required Actions of with one or more LCO 3.9.6, "Containment automatic actuation Penetrations," for trains inoperable. containment purge and vent isolation valves made OR inoperable by isolation instrumentation.

Two or more radiation monitoring channels inoperable.

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

Kewaunee Power Station 3.3.6-2 Amendment 207

Containment Purge and Vent Isolation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Vent Isolation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.6.2 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.

Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform COT in accordance with the Setpoint 92 days Control Program.

SR 3.3.6.4 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

Kewaunee Power Station 3.3.6-3 Amendment 207

Containment Purge and Vent Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Purge and Vent Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. Automatic Actuation Logic and Actuation 1,2,3,4, (a) 2 trains SR 3.3.6.2 Relays

2. Containment Radiation

a. Gaseous 1,2,3,4, (a) 2 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4

b. Particulate 1,2,3,4, (a) 1 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4

3. Containment Isolation - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"

Function 3.a, for all initiation functions and requirements.

4. Containment Spray - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"

Function 2.a, for all initiation functions and requirement.

5. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all functions and requirements.

(a) During movement of irradiated fuel assemblies within containment.

Kewaunee Power Station 3.3.6-4 Amendment 207

CRPAR System Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Post Accident Recirculation (CRPAR) System Actuation Instrumentation LCO 3.3.7 The CRPAR System actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Automatic Actuation A.1 Place associated CRPAR 7 days Logic and Actuation train in emergency mode.

Relay train inoperable.

B. Two Automatic Actuation B.1.1 Place one CRPAR train in Immediately Logic and Actuation emergency mode.

Relay trains inoperable.

AND OR B.1.2 Enter applicable Conditions Immediately Control Room Vent and Required Actions for Radiation Monitor one CRPAR train made inoperable. inoperable by inoperable CRPAR System actuation instrumentation.

OR B.2 Place both CRPAR trains in Immediately emergency mode.

Kewaunee Power Station 3.3.7-1 Amendment 207

CRPAR System Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months D. Required Action and D.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies.

Time for Condition A or B not met during movement of irradiated fuel assemblies.

E. Required Action and E.1 Initiate action to restore one Immediately associated Completion CRPAR train to Time for Condition A OPERABLE status.

or B not met in MODE 5 or 6.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7-1 to determine which SRs apply for each CRPAR System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.7.2 Perform COT in accordance with the Setpoint 92 days Control Program.

Kewaunee Power Station 3.3.7-2 Amendment 207

CRPAR System Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.7.3 -------------------------------NOTE------------------------------

This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.

Perform ACTUATION LOGIC TEST. 18 months SR 3.3.7.4 Perform CHANNEL CALIBRATION in accordance 18 months with the Setpoint Control Program.

Kewaunee Power Station 3.3.7-3 Amendment 207

CRPAR System Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CRPAR System Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. Automatic Actuation Logic and 1, 2, 3, 4, 5, 6, 2 trains SR 3.3.7.3 Actuation Relays (a) 2 Control Room Vent Radiation 1, 2, 3, 4, 5, 6, 1 SR 3.3.7.1 Monitor (a) SR 3.3.7.2 SR 3.3.7.4

3. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

(a) During movement of irradiated fuel assemblies.

Kewaunee Power Station 3.3.7-4 Amendment 207

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

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

a. Pressurizer pressure is greater than or equal to the limit specified in the COLR;

b. RCS average temperature is less than or equal to the limit specified in the COLR; and

c. RCS total flow rate 178,000 gpm and greater than or equal to the limit specified in the COLR.

APPLICABILITY: MODE 1.

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

Pressurizer pressure limit does not apply during:

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

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours0.0833 days 0.0119 weeks 0.00274 months parameters not within parameter(s) to within limit.

limits.

B. Required Action and B.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Kewaunee Power Station 3.4.1-1 Amendment 207

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal 12 hours0.5 days 0.0714 weeks 0.0164 months to the limit specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature is less than or 12 hours0.5 days 0.0714 weeks 0.0164 months equal to the limit specified in the COLR.

SR 3.4.1.3 Verify RCS total flow rate is 178,000 gpm and 12 hours0.5 days 0.0714 weeks 0.0164 months greater than or equal to the limit specified in the COLR.

SR 3.4.1.4 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after 90% RTP.

Verify by precision heat balance that RCS total flow 18 months rate is 178,000 gpm and greater than or equal to the limit specified in the COLR.

Kewaunee Power Station 3.4.1-2 Amendment 207

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be 540°F.

APPLICABILITY: MODE 1, MODE 2 with keff 1.0.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 540°F. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.4.2-1 Amendment 207

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in Figure 3.4.3-1 and Figure 3.4.3-2.

APPLICABILITY: At all times.

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

shall be completed whenever this Condition AND is entered.

A.2 Determine RCS is 72 hours3 days 0.429 weeks 0.0986 months acceptable for continued Requirements of operation.

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

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 with RCS 36 hours1.5 days 0.214 weeks 0.0493 months pressure < 500 psig.

C. ------------NOTE------------ C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within shall be completed limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to entering Requirements of acceptable for continued MODE 4 LCO not met any time in operation.

other than MODE 1, 2, 3, or 4.

Kewaunee Power Station 3.4.3-1 Amendment 207

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

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

Verify RCS pressure, RCS temperature, and RCS 30 minutes heatup and cooldown rates are within the limits specified in Figure 3.4.3-1 and Figure 3.4.3-2.

Kewaunee Power Station 3.4.3-2 Amendment 207

RCS P/T Limits 3.4.3 Figure 3.4.3-1 (page 1 of 1)

KPS Heatup, Criticality, and In-Service Leak Test Limitation Curves Applicable for Periods up to 33(1) Effective Full Power Years (EFPY)

(1) Curves limited to 31.1 EFPY due to changes in vessel fluence associated with operation at power uprate Kewaunee Power Station 3.4.3-3 Amendment 207

RCS P/T Limits 3.4.3 Figure 3.4.3-2 (page 1 of 1)

KPS Cooldown and LTOP Event Limitation Curves Applicable for Periods up to 33(1) EFPY (1) Curves limited to 31.1 EFPY due to changes in vessel fluence associated with operation at power uprate Kewaunee Power Station 3.4.3-4 Amendment 207

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES 1 and 2 LCO 3.4.4 Two RCS loops shall be OPERABLE and in operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months LCO not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.4.4-1 Amendment 207

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

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

All reactor coolant pumps may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

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

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

APPLICABILITY: MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Restore RCS loop to 72 hours3 days 0.429 weeks 0.0986 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not met.

Kewaunee Power Station 3.4.5-1 Amendment 207

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two RCS loops C.1 Place the Rod Control Immediately inoperable. System in a condition incapable of rod withdrawal.

OR AND Required RCS loop not in operation. C.2 Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1.

AND C.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify one RCS loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.5.2 Verify steam generator secondary side water levels 12 hours0.5 days 0.0714 weeks 0.0164 months are 5% for both RCS loops.

SR 3.4.5.3 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a pump is not in operation.

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

Kewaunee Power Station 3.4.5-2 Amendment 207

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

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

All reactor coolant pumps (RCPs) and RHR pumps may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

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

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

APPLICABILITY: MODE 4.

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

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

Only required if RHR loop is OPERABLE.

Be in MODE 5. 24 hours1 days 0.143 weeks 0.0329 months Kewaunee Power Station 3.4.6-1 Amendment 207

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

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

operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.6.2 Verify SG secondary side water levels are 5% for 12 hours0.5 days 0.0714 weeks 0.0164 months required RCS loops.

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

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

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

Kewaunee Power Station 3.4.6-2 Amendment 207

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

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side water level of at least one steam generator (SG) shall be 5%.

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

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

a. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, "SHUTDOWN MARGIN (SDM)"; and

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

2. One required RHR loop may be inoperable for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months for Surveillance testing provided that the other RHR loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started unless the secondary side water temperature of each SG is < 100°F above each of the RCS cold leg temperatures.

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY: MODE 5 with RCS Loops Filled.

Kewaunee Power Station 3.4.7-1 Amendment 207

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

AND OR One RHR loop OPERABLE. A.2 Initiate action to restore Immediately required SG secondary side water level to within limit.

B. One required SG with B.1 Initiate action to restore a Immediately secondary side water second RHR loop to level not within limit. OPERABLE status.

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

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

in operation.

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

Kewaunee Power Station 3.4.7-2 Amendment 207

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.7.2 Verify SG secondary side water level is 5% in 12 hours0.5 days 0.0714 weeks 0.0164 months required SG.

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

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

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

Kewaunee Power Station 3.4.7-3 Amendment 207

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

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

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

a. The core outlet temperature is maintained at least 10°F below saturation temperature;

b. No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, "SHUTDOWN MARGIN (SDM)"; and

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

2. One RHR loop may be inoperable for 2 hours0.0833 days 0.0119 weeks 0.00274 months for Surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

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

Kewaunee Power Station 3.4.8-1 Amendment 207

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

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

in operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.8.2 -------------------------------NOTE------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

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

Kewaunee Power Station 3.4.8-2 Amendment 207

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

a. Pressurizer water level 90%; and

b. One group of pressurizer heaters OPERABLE with the capacity of the group 158.4 kW and capable of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months not within limit.

AND A.2 Fully insert all rods. 6 hours0.25 days 0.0357 weeks 0.00822 months AND A.3 Place Rod Control System 6 hours0.25 days 0.0357 weeks 0.00822 months in a condition incapable of rod withdrawal.

AND A.4 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months B. Required group of B.1 Restore required group of 72 hours3 days 0.429 weeks 0.0986 months pressurizer heaters pressurizer heaters to inoperable. OPERABLE status.

Kewaunee Power Station 3.4.9-1 Amendment 207

Pressurizer 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition B not AND met.

C.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 90%. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.9.2 Verify capacity of each required group of pressurizer 18 months heaters is 158.4 kW.

SR 3.4.9.3 Verify required pressurizer heaters are capable of 18 months being powered from an emergency power supply.

Kewaunee Power Station 3.4.9-2 Amendment 207

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings 2410.45 psig and 2559.55 psig.

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

The pressurizer safety valves may be inoperable during a hydro test of the RCS provided the pressurizer power operated relief valves and the safety valves on the discharge pump are set at > the test pressure

+35 psi.

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

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

The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 36 hours1.5 days 0.214 weeks 0.0493 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

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

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND OR B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Two pressurizer safety valves inoperable.

Kewaunee Power Station 3.4.10-1 Amendment 207

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE In accordance in accordance with the Inservice Testing Program. with the Inservice Following testing, lift settings shall be within +/- 1%. Testing Program Kewaunee Power Station 3.4.10-2 Amendment 207

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each PORV and each block valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable to associated block valve.

of being manually cycled.

B. One PORV inoperable B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valve.

manually cycled.

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

AND B.3 Restore PORV to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

Kewaunee Power Station 3.4.11-1 Amendment 207

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve --------------------NOTE-------------------

inoperable. Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or E.2.

C.1 Place associated PORV in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months manual control.

AND C.2 Restore block valve to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months E. Two PORVs inoperable E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valves.

manually cycled.

AND E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

AND E.3 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months AND E.4 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.4.11-2 Amendment 207

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two block valves --------------------NOTE-------------------

inoperable. Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or E.2.

F.1 Restore one block valve to 2 hours0.0833 days 0.0119 weeks 0.00274 months OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition F not AND met.

G.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 ------------------------------NOTES-----------------------------

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

2. Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each block valve. 92 days SR 3.4.11.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV. 18 months Kewaunee Power Station 3.4.11-3 Amendment 207

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with one of the following pressure relief capabilities:

a. The Residual Heat Removal (RHR) System LTOP overpressure relief valve with a lift setting 500 psig and two RHR suction flow paths OPERABLE; or

b. An RCS vent of 6.4 square inches.

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

A reactor coolant pump shall not be started with one or more RCS cold leg temperatures 200ºF unless the secondary water temperature of each steam generator is < 100ºF above each of the RCS cold leg temperatures.

APPLICABILITY: MODE 5, MODE 6 when the reactor vessel head is on.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suction flow A.1 Verify suction valves in the Immediately path inoperable. other RHR suction flow path are locked open with the motive power removed.

AND A.2 Restore RHR suction flow 5 days path to OPERABLE status.

Kewaunee Power Station 3.4.12-1 Amendment 207

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two RHR suction flow B.1 Depressurize RCS and 8 hours0.333 days 0.0476 weeks 0.011 months paths inoperable. establish RCS vent of 6.4 square inches.

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

OR RHR System LTOP overpressure relief valve inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify RHR suction valves are open for each RHR 12 hours0.5 days 0.0714 weeks 0.0164 months suction flow path.

SR 3.4.12.2 Verify required RCS vent 6.4 square inches is 12 hours0.5 days 0.0714 weeks 0.0164 months for open. unlocked open vent valve(s)

AND 31 days for other vent path(s)

Kewaunee Power Station 3.4.12-2 Amendment 207

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to within 4 hours0.167 days 0.0238 weeks 0.00548 months LEAKAGE not within limits.

limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months OR Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limit.

Kewaunee Power Station 3.4.13-1 Amendment 207

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ------------------------------NOTES-----------------------------

1. Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by 72 hours3 days 0.429 weeks 0.0986 months performance of RCS water inventory balance.

SR 3.4.13.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is 72 hours3 days 0.429 weeks 0.0986 months 150 gallons per day through any one SG.

Kewaunee Power Station 3.4.13-2 Amendment 207

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.

AND The Residual Heat Removal (RHR) System interlock function shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

Kewaunee Power Station 3.4.14-1 Amendment 207

RCS PIV Leakage 3.4.14 ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable RCS PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths --------------------NOTE-------------------

with leakage from one or Each valve used to satisfy Required more RCS PIVs not Action A.1 and Required Action A.2 within limit. must have been verified to meet SR 3.4.14.1.a and be in the reactor coolant pressure boundary or the high pressure portion of the system.

A.1 Isolate the high pressure 4 hours0.167 days 0.0238 weeks 0.00548 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND A.2 Isolate the high pressure 72 hours3 days 0.429 weeks 0.0986 months portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months C. RHR System interlock C.1 Isolate each of the affected 4 hours0.167 days 0.0238 weeks 0.00548 months function inoperable. lines by use of one closed manual or deactivated automatic valve.

Kewaunee Power Station 3.4.14-2 Amendment 207

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 ------------------------------NOTE-------------------------------

Only required to be performed in MODES 1 and 2.

Verify: 18 months

a. Leakage from each RCS PIV is equivalent to AND 5.0 gpm at an RCS pressure of 2235 psig; and Prior to entering MODE 2

b. When current measured rate is > 1 gpm, whenever the unit the current measured rate has not has been in exceeded the rate determined by the MODE 5 for previous test by an amount that reduces 72 hours3 days 0.429 weeks 0.0986 months or more, the margin between measured leakage if leakage testing rate and 5.0 gpm by 50%. has not been performed in the previous 9 months SR 3.4.14.2 Verify RHR System interlock prevents the valves 18 months from being opened with a simulated or actual RCS pressure signal 450 psig.

Kewaunee Power Station 3.4.14-3 Amendment 207

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump (hi or hi-hi level) monitor; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 --------------NOTE--------------

sump monitor Not required until 12 hours0.5 days 0.0714 weeks 0.0164 months inoperable. after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours1 days 0.143 weeks 0.0329 months AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

Kewaunee Power Station 3.4.15-1 Amendment 207

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1.1 Analyze grab samples of Once per 24 hours1 days 0.143 weeks 0.0329 months atmosphere radioactivity the containment monitor inoperable. atmosphere.

OR B.1.2 --------------NOTE--------------

Not required until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours1 days 0.143 weeks 0.0329 months AND B.2 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5 36 hours1.5 days 0.214 weeks 0.0493 months D. All required monitors D.1 Enter LCO 3.0.3. Immediately inoperable.

Kewaunee Power Station 3.4.15-2 Amendment 207

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours0.5 days 0.0714 weeks 0.0164 months containment atmosphere radioactivity monitor.

SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months containment sump monitor.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 18 months containment atmosphere radioactivity monitor.

Kewaunee Power Station 3.4.15-3 Amendment 207

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT --------------------NOTE-------------------

I-131 not within limit. LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT Once per 4 hours0.167 days 0.0238 weeks 0.00548 months I-131 20 µCi/gm.

AND A.2 Restore DOSE 48 hours2 days 0.286 weeks 0.0658 months EQUIVALENT I-131 to within limit.

B. DOSE EQUIVALENT --------------------NOTE-------------------

XE-133 not within limit. LCO 3.0.4.c is applicable.

B.1 Restore DOSE 48 hours2 days 0.286 weeks 0.0658 months EQUIVALENT XE-133 to within limit.

Kewaunee Power Station 3.4.16-1 Amendment 207

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months OR DOSE EQUIVALENT I-131 > 20 µCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 7 days specific activity 595 µCi/gm.

SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT I-131 14 days specific activity 1.0 µCi/gm.

AND Between 2 and 6 hours0.25 days 0.0357 weeks 0.00822 months after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Kewaunee Power Station 3.4.16-2 Amendment 207

SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube repair criteria shall be plugged in accordance with the Steam Generator Program.

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

ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube repair affected tube(s) is criteria and not plugged maintained until the next in accordance with the refueling outage or SG tube Steam Generator inspection.

Program.

AND A.2 Plug the affected tube(s) in Prior to entering accordance with the Steam MODE 4 following the Generator Program. next refueling outage or SG tube inspection B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months OR SG tube integrity not maintained.

Kewaunee Power Station 3.4.17-1 Amendment 207

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the In accordance Steam Generator Program. with the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube repair criteria is plugged in accordance with the MODE 4 following Steam Generator Program. a SG tube inspection Kewaunee Power Station 3.4.17-2 Amendment 207

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Two SI accumulators shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS pressure > 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours3 days 0.429 weeks 0.0986 months inoperable due to boron concentration to within concentration not within limits.

limits.

B. One accumulator B.1 Restore accumulator to 24 hours1 days 0.143 weeks 0.0329 months inoperable for reasons OPERABLE status.

other than Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A or B AND not met.

C.2 Reduce RCS pressure to 12 hours0.5 days 0.0714 weeks 0.0164 months 1000 psig.

D. Two accumulators D.1 Enter LCO 3.0.3. Immediately inoperable.

Kewaunee Power Station 3.5.1-1 Amendment 207

Accumulators 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.5.1.2 Verify borated water volume in each accumulator is 12 hours0.5 days 0.0714 weeks 0.0164 months 1225 ft3 and 1275 ft3.

SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator 12 hours0.5 days 0.0714 weeks 0.0164 months is 700 psig and 775 psig.

SR 3.5.1.4 Verify boron concentration in each accumulator is 31 days 2400 ppm and 2625 ppm.

AND

NOTE--------

Only required to be performed for affected accumulators Once within 6 hours0.25 days 0.0357 weeks 0.00822 months after each solution volume increase of 15%

of indicated level that is not the result of addition from the refueling water storage tank SR 3.5.1.5 Verify motive power is removed from each 31 days accumulator isolation valve operator.

Kewaunee Power Station 3.5.1-2 Amendment 207

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

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

A safety injection (SI) train may be considered OPERABLE for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when being used to fill an SI accumulator, provided the other SI train is OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours3 days 0.429 weeks 0.0986 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately ECCS flow equivalent to a single OPERABLE ECCS train available.

Kewaunee Power Station 3.5.2-1 Amendment 207

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position 12 hours0.5 days 0.0714 weeks 0.0164 months with motive power to the valve operator removed.

Number Position Function SI-9A Open Safety Injection to RCS Cold Legs SI-11A Open Safety Injection to Loop A Cold Leg SI-11B Open Safety Injection to Loop B Cold Leg SI-4A OR SI-4B Open RWST Supply to Safety Injection Pumps SR 3.5.2.2 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.3 Not used.

SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the Inservice required developed head. Testing Program SR 3.5.2.5 Verify each ECCS automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5.2.6 Verify each ECCS pump starts automatically on an 18 months actual or simulated actuation signal.

SR 3.5.2.7 Verify, for each ECCS throttle valve listed below, 18 months each position stop is in the correct position.

Valve Number SI-10A SI-10B Kewaunee Power Station 3.5.2-2 Amendment 207

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.8 Verify, by visual inspection, the containment sump 18 months strainer inlet is not restricted by debris and the debris interceptors and strainer show no evidence of structural distress or abnormal corrosion.

Kewaunee Power Station 3.5.2-3 Amendment 207

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

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

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned to the ECCS mode of operation.

APPLICABILITY: MODE 4.

ACTIONS

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

LCO 3.0.4.b is not applicable to ECCS safety injection subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS safety B.1 Restore required ECCS SI 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months injection (SI) subsystem subsystem to OPERABLE inoperable. status.

C. Required Action and C.1 Be in MODE 5. 24 hours1 days 0.143 weeks 0.0329 months associated Completion Time of Condition B not met.

Kewaunee Power Station 3.5.3-1 Amendment 207

ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance required to be OPERABLE: with applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.4 SR 3.5.2.8 Kewaunee Power Station 3.5.3-2 Amendment 207

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours0.333 days 0.0476 weeks 0.011 months concentration not within OPERABLE status.

limits.

B. RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify RWST borated water volume is 272,500 7 days gallons.

SR 3.5.4.2 Verify RWST boron concentration is 2500 ppm 7 days and 2625 ppm.

Kewaunee Power Station 3.5.4-1 Amendment 207

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

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

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

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and leakage In accordance rate testing except for containment air lock testing, with the in accordance with the Containment Leakage Rate Containment Testing Program. Leakage Rate Testing Program Kewaunee Power Station 3.6.1-1 Amendment 207

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 Two containment air locks shall be OPERABLE.

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

ACTIONS

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

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more --------------------NOTES-----------------

containment air locks 1. Required Actions A.1, A.2, with one containment air and A.3 are not applicable if lock door inoperable. both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

A.1 Verify the OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Kewaunee Power Station 3.6.2-1 Amendment 207

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE door 24 hours1 days 0.143 weeks 0.0329 months closed in the affected air lock.

AND A.3 --------------NOTE--------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE door Once per 31 days is locked closed in the affected air lock.

B. One or more -------------------NOTES------------------

containment air locks 1. Required Actions B.1, B.2, with containment air lock and B.3 are not applicable if interlock mechanism both doors in the same air lock inoperable. are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock.

AND Kewaunee Power Station 3.6.2-2 Amendment 207

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours1 days 0.143 weeks 0.0329 months closed in the affected air lock.

AND B.3 --------------NOTE--------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is locked closed in the affected air lock.

C. One or more C.1 Initiate action to evaluate Immediately containment air locks overall containment inoperable for reasons leakage rate per LCO 3.6.1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 3.6.2-3 Amendment 207

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1 ------------------------------NOTES-----------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in In accordance accordance with the Containment Leakage Rate with the Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be opened at 18 months a time.

Kewaunee Power Station 3.6.2-4 Amendment 207

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

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

ACTIONS

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

1. Penetration flow path(s) except for 36 inch purge and vent valve flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Isolate the affected 24 hours1 days 0.143 weeks 0.0329 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two containment and de-activated automatic isolation valves. valve, closed manual valve,

blind flange, or check valve with flow through the valve One or more penetration secured.

flow paths with one containment isolation AND valve inoperable for reasons other than Condition D.

Kewaunee Power Station 3.6.3-1 Amendment 207

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -------------NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. ------------NOTE------------ B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two containment and de-activated automatic isolation valves. valve, closed manual valve,

or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable for reasons other than Condition D.

Kewaunee Power Station 3.6.3-2 Amendment 207

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE------------ C.1 Isolate the affected 72 hours3 days 0.429 weeks 0.0986 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with only one and de-activated automatic containment isolation valve, closed manual valve, valve and a closed or blind flange.

system.

AND One or more penetration C.2 -------------NOTES-------------

flow paths with one 1. Isolation devices in high containment isolation radiation areas may be valve inoperable. verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Kewaunee Power Station 3.6.3-3 Amendment 207

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Combined bypass D.1 Restore leakage within 4 hours0.167 days 0.0238 weeks 0.00548 months leakage not within limits. limit.

E. Required Action and E.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 36 inch purge and vent isolation valve is 31 days sealed closed.

SR 3.6.3.2 Verify each 2 inch containment vent isolation valve 31 days is closed, except when the 2 inch containment vent isolation valves are open for pressure control, ALARA or air quality considerations for personnel entry, or for Surveillances that require the valves to be open.

Kewaunee Power Station 3.6.3-4 Amendment 207

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.3 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and 31 days blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.4 -------------------------------NOTE------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed, except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.5 Verify the isolation time of each automatic power In accordance operated containment isolation valve is within limits. with the Inservice Testing Program SR 3.6.3.6 Verify each automatic containment isolation valve 18 months that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

Kewaunee Power Station 3.6.3-5 Amendment 207

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.7 Verify the combined bypass leakage rate for all In accordance penetrations: with the Containment

a. Which extend into the auxiliary building special Leakage Rate ventilation zone is 0.10 La; and Testing Program

b. Which are exterior to both the shield building and the auxiliary building special ventilation zone is 0.01 La.

Kewaunee Power Station 3.6.3-6 Amendment 207

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be 0.0 psig and 2.0 psig.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.6.4-1 Amendment 207

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be 120°F.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air A.1 Restore containment 8 hours0.333 days 0.0476 weeks 0.011 months temperature not within average air temperature to limit. within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is within 24 hours1 days 0.143 weeks 0.0329 months limit.

Kewaunee Power Station 3.6.5-1 Amendment 207

Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray 72 hours3 days 0.429 weeks 0.0986 months train inoperable. train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months C. One containment cooling C.1 Restore containment 7 days train inoperable. cooling train to OPERABLE status.

D. One fan coil unit in both D.1 Restore one containment 72 hours3 days 0.429 weeks 0.0986 months containment cooling cooling train to OPERABLE trains inoperable. status.

E. Required Action and E.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition C or D AND not met.

E.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 3.6.6-1 Amendment 207

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two containment spray F.1 Enter LCO 3.0.3. Immediately trains inoperable.

OR Two containment cooling trains inoperable for reasons other than Condition D.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Operate each containment cooling train fan unit for 31 days 15 minutes.

SR 3.6.6.3 Verify each containment cooling train cooling water 92 days flow rate is sufficient to remove the assumed heat load.

SR 3.6.6.4 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the Inservice the required developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray valve in 18 months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

Kewaunee Power Station 3.6.6-2 Amendment 207

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.6 Verify each containment spray pump starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.7 Verify each containment cooling train starts 18 months automatically on an actual or simulated actuation signal.

SR 3.6.6.8 Verify each required spray nozzle is unobstructed. 10 years Kewaunee Power Station 3.6.6-3 Amendment 207

Spray Additive System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Spray Additive System LCO 3.6.7 The Spray Additive System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A.1 Restore Spray Additive 72 hours3 days 0.429 weeks 0.0986 months inoperable. System to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify each spray additive manual, power operated, 31 days and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.7.2 Verify caustic additive standpipe solution volume is 184 days 300 gal.

SR 3.6.7.3 Verify caustic additive standpipe NaOH solution 184 days concentration is 30% and 38% by weight.

Kewaunee Power Station 3.6.7-1 Amendment 207

Spray Additive System 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.4 Verify each spray additive automatic valve in the 18 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

Kewaunee Power Station 3.6.7-2 Amendment 207

Shield Building 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Shield Building LCO 3.6.8 The shield building shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shield building A.1 Restore shield building to 24 hours1 days 0.143 weeks 0.0329 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify one shield building access door in each 31 days access opening is closed.

SR 3.6.8.2 Verify the shield building can be maintained at a 18 months on a pressure 0.25 inch vacuum water gauge in the STAGGERED annulus by one Shield Building Ventilation System TEST BASIS for train with final flow with the limits of Figure 3.6.8-1 each Shield within 120 seconds after a start signal. Building Air Cleanup System train Kewaunee Power Station 3.6.8-1 Amendment 207

Shield Building 3.6.8 Unacceptable Operation Acceptable Operation Figure 3.6.8-1 Shield Building Ventilation Performance Requirement Kewaunee Power Station 3.6.8-2 Amendment 207

Vacuum Relief Valves 3.6.9 3.6 CONTAINMENT SYSTEMS 3.6.9 Vacuum Relief Valves LCO 3.6.9 Two vacuum relief lines shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One vacuum relief line A.1 Restore vacuum relief line 72 hours3 days 0.429 weeks 0.0986 months inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.1 Perform a functional test of each vacuum relief valve 18 months and verify the valve opens at a simulated containment vacuum of 0.5 psig vacuum.

SR 3.6.9.2 Perform a CHANNEL CALIBRATION on the 18 months containment vacuum breaker differential pressure channels.

Kewaunee Power Station 3.6.9-1 Amendment 207

SBVS 3.6.10 3.6 CONTAINMENT SYSTEMS 3.6.10 Shield Building Ventilation System (SBVS)

LCO 3.6.10 Two SBVS trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SBVS train A.1 Restore SBVS train to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.10.1 Operate each SBVS train for 15 minutes. 31 days SR 3.6.10.2 Perform required SBVS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.10.3 Verify each SBVS train actuates on an actual or 18 months simulated actuation signal.

Kewaunee Power Station 3.6.10-1 Amendment 207

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 Five MSSVs per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months generators with one POWER to 55% RTP.

MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.

B. One or more steam B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months generators with two or POWER to less than or more MSSVs equal to the Maximum inoperable. Allowable % RTP specified in Table 3.7.1-1 for the OR number of OPERABLE MSSVs.

One or more steam generators with one AND MSSV inoperable and the MTC positive at any power level.

Kewaunee Power Station 3.7.1-1 Amendment 207

MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 --------------NOTE--------------

Only required in MODE 1.

Reduce the Power Range 36 hours1.5 days 0.214 weeks 0.0493 months Neutron Flux - High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND OR C.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months One or more steam generators with 4 MSSVs inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance Table 3.7.1-2 in accordance with the Inservice with the Inservice Testing Program. Following testing, lift setting shall Testing Program be within +1%.

Kewaunee Power Station 3.7.1-2 Amendment 207

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MAXIMUM ALLOWABLE MSSVs PER STEAM POWER (% RTP)

GENERATOR 4 48 3 33 2 19 Kewaunee Power Station 3.7.1-3 Amendment 207

MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER STEAM GENERATOR LIFT SETTING (psig +/- 3%)

1 #2 SD1A3 SD1B3 1074 SD1A2 SD1B4 1090 SD1A4 SD1B2 1105 SD1A1 SD1B5 1120 SD1A5 SD1B1 1127 Kewaunee Power Station 3.7.1-4 Amendment 207

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed and de-activated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 24 hours1 days 0.143 weeks 0.0329 months MODE 1. OPERABLE status.

B. Required Action and B.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not met.

C. ------------NOTE------------ C.1 Close MSIV. 24 hours1 days 0.143 weeks 0.0329 months Separate Condition entry is allowed for each AND MSIV.

C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.7.2-1 Amendment 207

MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 -------------------------------NOTE------------------------------

Not required to be performed in MODES 2 and 3 until 12 hours0.5 days 0.0714 weeks 0.0164 months after the MSIVs are open.

Verify the isolation time of each MSIV is within In accordance limits. with the Inservice Testing Program SR 3.7.2.2 -------------------------------NOTE------------------------------

Only required to be performed in MODES 1 and 2.

Verify each MSIV actuates to the isolation position 18 months on an actual or simulated actuation signal.

Kewaunee Power Station 3.7.2-2 Amendment 207

MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and MFRV Bypass Valves LCO 3.7.3 Two MFIVs, two MFRVs, and MFRV bypass valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 except when all MFIVs, MFRVs, and MFRV bypass valves are closed and de-activated or isolated by a closed manual valve.

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate MFIV. 72 hours3 days 0.429 weeks 0.0986 months inoperable.

AND A.2 Verify MFIV is closed or Once per 7 days isolated.

B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours3 days 0.429 weeks 0.0986 months inoperable.

AND B.2 Verify MFRV is closed or Once per 7 days isolated.

C. One or more MFRV C.1 Close or isolate MFRV 72 hours3 days 0.429 weeks 0.0986 months bypass valves bypass valve.

inoperable.

AND C.2 Verify MFRV bypass valve Once per 7 days is closed or isolated.

Kewaunee Power Station 3.7.3-1 Amendment 207

MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same D.1 Isolate affected flow path. 8 hours0.333 days 0.0476 weeks 0.011 months flow path inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the isolation time of each MFIV, MFRV, and In accordance MFRV bypass valve is within limits. with the Inservice Testing Program SR 3.7.3.2 Verify each MFIV, MFRV, and MFRV bypass valves 18 months actuates to the isolation position on an actual or simulated actuation signal.

Kewaunee Power Station 3.7.3-2 Amendment 207

SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs)

LCO 3.7.4 Two SG PORV lines shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 Restore SG PORV line to 7 days inoperable. OPERABLE status.

B. Two SG PORV lines B.1 Restore one SG PORV line 24 hours1 days 0.143 weeks 0.0329 months inoperable. to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 4 without 24 hours1 days 0.143 weeks 0.0329 months reliance upon steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Inservice Testing Program Kewaunee Power Station 3.7.4-1 Amendment 207

SG PORVs 3.7.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.4.2 Verify one complete cycle of each SG PORV 18 months manual isolation valve.

Kewaunee Power Station 3.7.4-2 Amendment 207

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

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

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

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

LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Turbine driven AFW A.1 Restore affected equipment 7 days train inoperable due to to OPERABLE status.

one inoperable steam supply.

OR

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

Only applicable if MODE 2 has not been entered following refueling.

Turbine driven AFW train inoperable in MODE 3 following refueling.

Kewaunee Power Station 3.7.5-1 Amendment 207

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One AFW train B.1 Restore AFW train to 72 hours3 days 0.429 weeks 0.0986 months inoperable in MODE 1, OPERABLE status.

2, or 3 for reasons other than Condition A.

C. Turbine driven AFW train C.1 Restore the steam supply to 48 hours2 days 0.286 weeks 0.0658 months inoperable due to one the turbine driven train to inoperable steam supply. OPERABLE status.

AND OR One motor driven AFW C.2 Restore the motor driven 48 hours2 days 0.286 weeks 0.0658 months train inoperable. AFW train to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 18 hours0.75 days 0.107 weeks 0.0247 months OR Two AFW trains inoperable in MODE 1, 2, or 3 for reasons other than Condition C.

E. Three AFW trains E.1 --------------NOTE--------------

inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

Kewaunee Power Station 3.7.5-2 Amendment 207

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required AFW train F.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 ------------------------------NOTES-----------------------------

1. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control when THERMAL POWER is < 15% RTP, if it is capable of being manually realigned to the AFW mode of operation.

2. One AFW header cross-tie valve is allowed to be closed during testing of the motor driven AFW pump for up to 4 hours0.167 days 0.0238 weeks 0.00548 months and the turbine driven AFW train may be considered OPERABLE, provided the cross-tie valve is capable of being remotely realigned.

Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 -------------------------------NOTE------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours1 days 0.143 weeks 0.0329 months after 500 psig in the steam generator.

Verify the developed head of each AFW pump at the In accordance flow test point is greater than or equal to the with the Inservice required developed head. Testing Program Kewaunee Power Station 3.7.5-3 Amendment 207

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.3 -------------------------------NOTE------------------------------

AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control when THERMAL POWER is < 15% RTP, if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW automatic valve that is not locked, 18 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4 ------------------------------NOTES-----------------------------

1. Not required to be performed for the turbine driven AFW pump until 24 hours1 days 0.143 weeks 0.0329 months after 500 psig in the steam generator.

2. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control when THERMAL POWER is < 15% RTP, if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW pump starts automatically on an 18 months actual or simulated actuation signal.

Kewaunee Power Station 3.7.5-4 Amendment 207

CSTs 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tanks (CSTs)

LCO 3.7.6 The CSTs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CSTs inoperable. A.1 Verify by administrative 4 hours0.167 days 0.0238 weeks 0.00548 months means OPERABILITY of backup water supply. AND Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND A.2 Restore CSTs to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4, without 24 hours1 days 0.143 weeks 0.0329 months reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify usable volume in the CSTs is 41,500 gal. 12 hours0.5 days 0.0714 weeks 0.0164 months Kewaunee Power Station 3.7.6-1 Amendment 207

CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling (CC) System LCO 3.7.7 Two CC trains shall be OPERABLE.

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

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

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat removal loops made inoperable by CC System.

Restore CC train to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 3.7.7-1 Amendment 207

CC System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 -------------------------------NOTE------------------------------

Isolation of CC water flow to individual components does not render the CC System inoperable.

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

SR 3.7.7.2 Verify each CC automatic valve in the flow path that 18 months is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.3 Verify each CC pump starts automatically on an 18 months actual or simulated actuation signal.

Kewaunee Power Station 3.7.7-2 Amendment 207

SW System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water (SW) System LCO 3.7.8 Two SW trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SW train A.1 --------------NOTES-------------

inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"

for emergency diesel generator made inoperable by SW System.

2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops

- MODE 4," for residual heat removal loops made inoperable by SW System.

Restore SW train to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 3.7.8-1 Amendment 207

SW System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 -------------------------------NOTE------------------------------

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

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

SR 3.7.8.2 -------------------------------NOTE------------------------------

The turbine building header isolation valve actuation is not required provided the valve is closed and de-activated.

Verify each SW System automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.3 Verify each SW System pump starts automatically 18 months on an actual or simulated actuation signal.

SR 3.7.8.4 Perform CHANNEL CALIBRATION. 18 months SR 3.7.8.5 Verify each Circulating Water pump breaker trips on 18 months an actual or simulated Forebay Water Level - Low Low signal.

Kewaunee Power Station 3.7.8-2 Amendment 207

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO 3.7.9 The UHS shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable. A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months AND A.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify Circulating Water Forebay water level of UHS 24 hours1 days 0.143 weeks 0.0329 months is 565 ft 3 inches mean sea level.

SR 3.7.9.2 Verify average water temperature of UHS is 80°F. 24 hours1 days 0.143 weeks 0.0329 months Kewaunee Power Station 3.7.9-1 Amendment 207

CRPAR System 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Post Accident Recirculation (CRPAR) System LCO 3.7.10 Two CRPAR trains shall be OPERABLE.

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

The control room boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRPAR train A.1 Restore CRPAR train to 7 days inoperable. OPERABLE status.

B. Two CRPAR trains B.1 Restore control room 24 hours1 days 0.143 weeks 0.0329 months inoperable due to boundary to OPERABLE inoperable control room status.

boundary in MODE 1, 2, 3, or 4.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Kewaunee Power Station 3.7.10-1 Amendment 207

CRPAR System 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE CRPAR Immediately associated Completion train in emergency mode.

Time of Condition A not met in MODE 5 or 6, or OR during movement of irradiated fuel D.2 Suspend movement of Immediately assemblies. irradiated fuel assemblies.

E. Two CRPAR trains E.1 Suspend movement of Immediately inoperable in MODE 5 or irradiated fuel assemblies.

6, or during movement of irradiated fuel assemblies.

F. Two CRPAR trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRPAR train for 15 minutes. 31 days SR 3.7.10.2 Perform required CRPAR filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with VFTP SR 3.7.10.3 Verify each CRPAR train actuates on an actual or 18 months simulated actuation signal.

Kewaunee Power Station 3.7.10-2 Amendment 207

CRAC Alternate Cooling System 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning (CRAC) Alternate Cooling System LCO 3.7.11 Two CRAC Alternate Cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAC Alternate A.1 Restore CRAC Alternate 30 days Cooling train inoperable. Cooling train to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months C. Required Action and C.1 Place OPERABLE CRAC Immediately associated Completion Alternate Cooling train in Time of Condition A not operation.

met during movement of irradiated fuel OR assemblies.

C.2 Suspend movement of Immediately irradiated fuel assemblies.

D. Two CRAC Alternate D.1 Suspend movement of Immediately Cooling trains inoperable irradiated fuel assemblies.

during movement of irradiated fuel assemblies.

Kewaunee Power Station 3.7.11-1 Amendment 207

CRAC Alternate Cooling System 3.7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two CRAC Alternate E.1 Enter LCO 3.0.3. Immediately Cooling trains inoperable in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CRAC Alternate Cooling train has the 18 months capability to remove the assumed heat load.

Kewaunee Power Station 3.7.11-2 Amendment 207

ASV System 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Auxiliary Building Special Ventilation (ASV) System LCO 3.7.12 Two ASV trains shall be OPERABLE.

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

The ASV boundary may be opened intermittently under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ASV train A.1 Restore ASV train to 7 days inoperable. OPERABLE status.

B. Two ASV trains B.1 Restore ASV boundary to 24 hours1 days 0.143 weeks 0.0329 months inoperable due to OPERABLE status.

inoperable ASV boundary.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ASV train for 15 minutes. 31 days Kewaunee Power Station 3.7.12-1 Amendment 207

ASV System 3.7.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.12.2 Perform required ASV System filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

SR 3.7.12.3 Verify each ASV train actuates on an actual or 18 months simulated actuation signal.

SR 3.7.12.4 Verify one ASV train can maintain a measurable 18 months on a vacuum with coincident isolation of the normal vent STAGGERED ducts. TEST BASIS Kewaunee Power Station 3.7.12-2 Amendment 207

Spent Fuel Pool Water Level 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Spent Fuel Pool Water Level LCO 3.7.13 The spent fuel pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water A.1 --------------NOTE--------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify the spent fuel pool water level is 23 ft above 7 days the top of the irradiated fuel assemblies seated in the storage racks.

Kewaunee Power Station 3.7.13-1 Amendment 207

Spent Fuel Pool Boron Concentration 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Boron Concentration LCO 3.7.14 The spent fuel pool boron concentration shall be 240 ppm.

APPLICABILITY: When fuel assemblies are stored in the spent fuel pool and a spent fuel pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron --------------------NOTE-------------------

concentration not within LCO 3.0.3 is not applicable.

limit. ------------------------------------------------

A.1 Suspend movement of fuel Immediately assemblies in the spent fuel pool.

AND A.2.1 Initiate action to restore Immediately spent fuel pool boron concentration to within limit.

OR A.2.2 Initiate action to perform a Immediately spent fuel pool verification.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool boron concentration is 7 days within limit.

Kewaunee Power Station 3.7.14-1 Amendment 207

Spent Fuel Pool Storage 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Storage LCO 3.7.15 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel pool shall be in accordance with the following:

a. Irradiated fuel assemblies discharged prior to or during the 1984 refueling outage with a combination of burnup and initial nominal enrichment in the "Acceptable Domain" of Figure 3.7.15-1 shall be stored in the transfer canal spent fuel pool or the north and south combined spent fuel pools; and

b. New fuel assemblies, irradiated fuel assemblies discharged after the 1984 refueling outage, and irradiated fuel assemblies discharged prior to or during the 1984 refueling outage with a combination of burnup and initial nominal enrichment in the "Unacceptable Domain" of Figure 3.7.15-1, shall be stored in the north and south combined spent fuel pools.

APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 --------------NOTE--------------

LCO not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly to an acceptable location.

Kewaunee Power Station 3.7.15-1 Amendment 207

Spent Fuel Pool Storage 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial enrichment Prior to storing the and burnup of the fuel assembly is in accordance fuel assembly in with Figure 3.7.15-1. the spent fuel pool Kewaunee Power Station 3.7.15-2 Amendment 207

Spent Fuel Pool Storage 3.7.15 35.0 Acceptable Domain (3.411, 30) 30.0 Bounding Curve :

3 2 B = 1.29731 x E - 11.66621 x E + 48.63306 x E - 51.7244 25.0 Assembly Burnup (GWD/MTU)

(3.0, 24.17) 20.0 (2.5, 17.21) 15.0 Unacceptable Domain (2.25, 13.37) 10.0 (2.0, 9.24) 5.0 0.0 2 2.2 2.4 2.6 2.8 3 3.2 3.4 Initial Enrichment (wt% U-235)

Figure 3.7.15-1 (page 1 of 1)

Fuel Assembly Burnup Limits in the Spent Fuel Pools Kewaunee Power Station 3.7.15-3 Amendment 207

Secondary Specific Activity 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Secondary Specific Activity LCO 3.7.16 The specific activity of the secondary coolant shall be 0.10 µCi/gm DOSE EQUIVALENT I-131.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months within limit.

AND A.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the specific activity of the secondary coolant 31 days is 0.10 µCi/gm DOSE EQUIVALENT I-131.

Kewaunee Power Station 3.7.16-1 Amendment 207

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E power distribution subsystem(s).

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

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND A.2 Declare required feature(s) 24 hours1 days 0.143 weeks 0.0329 months from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND A.3 Restore offsite circuit to 7 days OPERABLE status.

Kewaunee Power Station 3.8.1-1 Amendment 207

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One DG inoperable. B.1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months offsite circuit(s).

AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND B.2 Declare required feature(s) 4 hours0.167 days 0.0238 weeks 0.00548 months from supported by the inoperable discovery of DG inoperable when its Condition B required redundant concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE DG 24 hours1 days 0.143 weeks 0.0329 months is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours1 days 0.143 weeks 0.0329 months OPERABLE DG.

AND B.4 Restore DG to OPERABLE 7 days status.

C. Two offsite circuits C.1 Declare required feature(s) 12 hours0.5 days 0.0714 weeks 0.0164 months from inoperable. inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required features AND Kewaunee Power Station 3.8.1-2 Amendment 207

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Restore one offsite circuit to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

D. One offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems - Operating,"

when Condition D is entered with no One DG inoperable. AC power source to any train.

D.1 Restore offsite circuit to 12 hours0.5 days 0.0714 weeks 0.0164 months OPERABLE status.

OR D.2 Restore DG to OPERABLE 12 hours0.5 days 0.0714 weeks 0.0164 months status.

E. Two DGs inoperable. E.1 Restore one DG to 2 hours0.0833 days 0.0119 weeks 0.00274 months OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND C, D, or E not met.

F.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months G. Three or more AC G.1 Enter LCO 3.0.3. Immediately sources inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 days power availability for each offsite circuit.

Kewaunee Power Station 3.8.1-3 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.8 must be met.

Verify each DG starts from standby conditions and 31 days achieves steady state voltage 4000 V and 4400 V, and frequency 60.0 Hz and 60.7 Hz.

SR 3.8.1.3 ------------------------------NOTES-----------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.8.

Verify each DG is synchronized and loaded and 31 days operates for 60 minutes at a load 2600 kW.

SR 3.8.1.4 Verify day tanks for each DG contain 1000 gal of 31 days fuel oil.

Kewaunee Power Station 3.8.1-4 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.5 Check for and remove accumulated water from each 31 days day tank.

SR 3.8.1.6 Verify each fuel oil transfer system operates to 31 days automatically transfer fuel oil from the storage tank to the associated day tanks.

SR 3.8.1.7 Verify interval between each sequenced load block 31 days is greater than or equal to minimum design load interval.

SR 3.8.1.8 ------------------------------NOTE-------------------------------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and 184 days achieves:

a. In 10 seconds, voltage 3952 V and frequency 59.0 Hz; and

b. Steady state voltage 4000 V and 4400 V, and frequency 60.0 Hz and 60.7 Hz.

SR 3.8.1.9 ------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify manual transfer of AC power sources from 18 months the normal offsite circuit to the alternate offsite circuit.

Kewaunee Power Station 3.8.1-5 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 ------------------------------NOTES-----------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with the DG synchronized with offsite power, it shall be performed at a power factor 0.89. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each DG rejects a load greater than or equal 18 months to its associated single largest post-accident load, and following load rejection, the frequency is 66.75 Hz.

SR 3.8.1.11 ------------------------------NOTES-----------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with DG synchronized with offsite power, it shall be performed at a power factor 0.89. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each DG can reject a load of 2860 kW 18 months without exceeding speeds or voltages that will cause tripping, mechanical damage, or harmful overstresses.

Kewaunee Power Station 3.8.1-6 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 18 months signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses,

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in 10 seconds;

2. Energizes auto-connected shutdown loads through time delay relays;

3. Maintains steady state voltage 4000 V and 4400 V;

4. Maintains steady state frequency 60.0 Hz and 60.7 Hz; and

5. Supplies permanently connected and auto-connected shutdown loads for 5 minutes.

Kewaunee Power Station 3.8.1-7 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

3. If performed with DG synchronized with offsite power, it shall be performed at a power factor 0.89. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each DG operates for 24 hours1 days 0.143 weeks 0.0329 months : 18 months

a. For 2 hours0.0833 days 0.0119 weeks 0.00274 months loaded 2860 kW; and

b. For the remaining hours of the test loaded 2700 kW.

Kewaunee Power Station 3.8.1-8 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours0.0833 days 0.0119 weeks 0.00274 months loaded 2600 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves: 18 months

a. In 10 seconds, voltage 3952 V and frequency 59.0 Hz; and

b. Steady state voltage 4000 V, and 4400 V and frequency 60.0 Hz and 60.7 Hz.

SR 3.8.1.15 ------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG: 18 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

Kewaunee Power Station 3.8.1-9 Amendment 207

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.16 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 18 months signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses,

b. Load shedding from emergency buses, and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in 10 seconds;

2. Energizes auto-connected emergency loads through time delay relays;

3. Achieves steady state voltage 4000 V and 4400 V;

4. Achieves steady state frequency 60.0 Hz and 60.7 Hz; and

5. Supplies permanently connected and auto-connected emergency loads for 5 minutes.

Kewaunee Power Station 3.8.1-10 Amendment 207

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b. One diesel generator (DG) capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite -------------------NOTE--------------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.

AND Kewaunee Power Station 3.8.2-1 Amendment 207

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One required DG B.1 Suspend movement of Immediately inoperable. irradiated fuel assemblies.

AND B.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.3 Initiate action to restore Immediately required DG to OPERABLE status.

Kewaunee Power Station 3.8.2-2 Amendment 207

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ------------------------------NOTE------------------------------

The following SRs are not required to be performed:

SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.10 through SR 3.8.1.15.

For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.1, "AC Sources - Operating," with applicable except SR 3.8.1.9 and SR 3.8.1.16, are applicable. SRs Kewaunee Power Station 3.8.2-3 Amendment 207

Diesel Fuel Oil and Lube Oil 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil and Lube Oil LCO 3.8.3 The stored diesel fuel oil and lube oil shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore fuel oil level to 48 hours2 days 0.286 weeks 0.0658 months usable combined within limits.

storage and day tanks fuel level < 32,888 gal and > 27,961 gal.

B. One or more DGs with B.1 Restore lube oil inventory to 48 hours2 days 0.286 weeks 0.0658 months lube oil inventory within limits.

< 504 gal and > 432 gal.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limits.

particulates not within limit.

D. One or more DGs with D.1 Restore stored fuel oil 30 days new fuel oil properties properties to within limits.

not within limits.

Kewaunee Power Station 3.8.3-1 Amendment 207

Diesel Fuel Oil and Lube Oil 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Declare associated DG Immediately associated Completion inoperable.

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

OR One or more DGs with diesel fuel oil or lube oil not within limits for reasons other than Condition A, B, C, or D.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank and associated day 31 days tanks contains 32,888 gal of usable fuel.

SR 3.8.3.2 Verify lubricating oil inventory is 504 gal for each 31 days DG.

SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Check for and remove accumulated water from each 92 days fuel oil storage tank.

Kewaunee Power Station 3.8.3-2 Amendment 207

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be OPERABLE.

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

ACTIONS

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

When a DC electrical power subsystem is inoperable solely due to the room cooler being non-functional, entry into associated ACTIONS may be delayed for up to 24 hours1 days 0.143 weeks 0.0329 months provided the associated room temperature is monitored and maintained within the design environmental requirements and the other DC electrical power subsystem is OPERABLE.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required battery A.1 Restore battery terminal 2 hours0.0833 days 0.0119 weeks 0.00274 months charger inoperable. voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify battery float current Once per 12 hours0.5 days 0.0714 weeks 0.0164 months 2 amps.

AND A.3 Restore battery charger to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

B. One DC electrical power B.1 Restore DC electrical 2 hours0.0833 days 0.0119 weeks 0.00274 months subsystem inoperable power subsystem to for reasons other than OPERABLE status.

Condition A.

Kewaunee Power Station 3.8.4-1 Amendment 207

DC Sources - Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify each required battery charger supplies 18 months 150 amps at greater than or equal to the minimum established float voltage for 8 hours0.333 days 0.0476 weeks 0.011 months .

OR Verify each required battery charger can recharge the battery to the fully charged state within 24 hours1 days 0.143 weeks 0.0329 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

Kewaunee Power Station 3.8.4-2 Amendment 207

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENT (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.3 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and 18 months maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

Kewaunee Power Station 3.8.4-3 Amendment 207

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE to support one subsystem of the DC Electrical Power Distribution System required by LCO 3.8.10, "Distribution System - Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC A.1 Suspend movement of Immediately electrical power irradiated fuel assemblies.

subsystem inoperable.

AND A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore Immediately required DC electrical power subsystem to OPERABLE status.

Kewaunee Power Station 3.8.5-1 Amendment 207

DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------------------NOTE------------------------------

The following SR is not required to be performed:

SR 3.8.4.3.

For the DC source required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 Kewaunee Power Station 3.8.5-2 Amendment 207

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for Train A and Train B electrical power subsystem batteries shall be within limits.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One battery with one or A.1 Perform SR 3.8.4.1. 2 hours0.0833 days 0.0119 weeks 0.00274 months more battery cells float voltage < 2.07 V. AND A.2 Perform SR 3.8.6.1. 2 hours0.0833 days 0.0119 weeks 0.00274 months AND A.3 Restore affected cell 24 hours1 days 0.143 weeks 0.0329 months voltage 2.07 V.

B. One battery with float B.1 Perform SR 3.8.4.1. 2 hours0.0833 days 0.0119 weeks 0.00274 months current > 2 amps.

AND B.2 Restore battery float current 12 hours0.5 days 0.0714 weeks 0.0164 months to 2 amps.

Kewaunee Power Station 3.8.6-1 Amendment 207

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action C.2 shall be Required Actions C.1 and C.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

C. One battery with one or C.1 Restore electrolyte level to 8 hours0.333 days 0.0476 weeks 0.011 months more cells electrolyte above top of plates.

level less than minimum established design AND limits.

C.2 Verify no evidence of 12 hours0.5 days 0.0714 weeks 0.0164 months leakage.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

D. One battery with pilot D.1 Restore battery pilot cell 12 hours0.5 days 0.0714 weeks 0.0164 months cell electrolyte temperature to greater than temperature less than or equal to minimum minimum established established design limits.

design limits.

E. Two batteries with E.1 Restore battery parameters 2 hours0.0833 days 0.0119 weeks 0.00274 months battery parameters not for one battery to within within limits. limits.

Kewaunee Power Station 3.8.6-2 Amendment 207

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

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

OR One battery with one or more battery cells float voltage < 2.07 V and float current > 2 amps.

OR SR 3.8.6.6 not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 -------------------------------NOTE------------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is 2 amps. 7 days SR 3.8.6.2 Verify each battery pilot cell float voltage is 2.07 V. 31 days SR 3.8.6.3 Verify each battery connected cell electrolyte level is 31 days greater than or equal to minimum established design limits.

SR 3.8.6.4 Verify each battery pilot cell temperature is greater 31 days than or equal to minimum established design limits.

Kewaunee Power Station 3.8.6-3 Amendment 207

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell float voltage is 92 days 2.07 V.

SR 3.8.6.6 -------------------------------NOTE------------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is 80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation, or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 100% of manufacturer's rating Kewaunee Power Station 3.8.6-4 Amendment 207

Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 The Train A and Train B inverters shall be OPERABLE.

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

Two inverters may be disconnected from their associated DC bus for 24 hours1 days 0.143 weeks 0.0329 months to perform an equalizing charge on their associated common battery, provided:

a. The associated AC instrument bus(es) are energized from their inverter using internal AC source/rectifier; and

b. All other AC instrument buses are energized from their associated OPERABLE inverters.

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

ACTIONS

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

When one or both inverters in one train are inoperable solely due to the room cooler being non-functional, entry into associated ACTIONS may be delayed for up to 24 hours1 days 0.143 weeks 0.0329 months provided the associated room temperature is monitored and maintained within the design environmental requirements and both inverters in the other train are OPERABLE.

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

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems - Operating" with any AC instrument bus de-energized.

Restore inverter to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

Kewaunee Power Station 3.8.7-1 Amendment 207

Inverters - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two inverters in one B.1 Restore one inverter to 2 hours0.0833 days 0.0119 weeks 0.00274 months train inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to its associated AC instrument buses.

Kewaunee Power Station 3.8.7-2 Amendment 207

Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 One inverter shall be OPERABLE to support the 120 VAC electrical distribution subsystem required by LCO 3.8.10, "Distribution Systems -

Shutdown."

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 Suspend movement of Immediately inoperable. irradiated fuel assemblies.

AND A.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore Immediately required inverter to OPERABLE status.

Kewaunee Power Station 3.8.8-1 Amendment 207

Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignments to its associated AC instrument buses.

Kewaunee Power Station 3.8.8-2 Amendment 207

Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Train A and Train B AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE.

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

ACTIONS

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

When one or more electrical power distribution subsystems are inoperable solely due to the room cooler being non-functional, entry into associated ACTIONS may be delayed for up to 24 hours1 days 0.143 weeks 0.0329 months provided the associated room temperature is monitored and maintained within the design environmental requirements and the electrical power distribution subsystems in the other train are OPERABLE.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC --------------------NOTE-------------------

electrical power Enter applicable Conditions and distribution subsystems Required Actions of LCO 3.8.4, "DC inoperable. Sources - Operating," for DC sources made inoperable by inoperable power distribution subsystems.

A.1 Restore AC electrical power 8 hours0.333 days 0.0476 weeks 0.011 months distribution subsystem(s) to OPERABLE status.

B. One or more AC B.1 Restore AC instrument 2 hours0.0833 days 0.0119 weeks 0.00274 months instrument buses bus(es) to OPERABLE inoperable. status.

C. One DC electrical power C.1 Restore DC electrical 2 hours0.0833 days 0.0119 weeks 0.00274 months distribution subsystem power distribution inoperable. subsystem to OPERABLE status.

Kewaunee Power Station 3.8.9-1 Amendment 207

Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months E. Two or more electrical E.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and AC instrument bus electrical power distribution subsystems.

Kewaunee Power Station 3.8.9-2 Amendment 207

Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC supported required instrument bus electrical feature(s) inoperable.

power distribution subsystems inoperable. OR A.2.1 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.2 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND Kewaunee Power Station 3.8.10-1 Amendment 207

Distribution Systems - Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate actions to restore Immediately required AC, DC, and AC instrument bus electrical power distribution subsystems to OPERABLE status.

AND A.2.4 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and AC instrument bus electrical power distribution subsystems.

Kewaunee Power Station 3.8.10-2 Amendment 207

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System (RCS), the fuel transfer canal, the refueling cavity, and the spent fuel pool shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

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

Only applicable to the fuel transfer canal, refueling cavity, and the spent fuel pool when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend positive reactivity Immediately within limit. additions.

AND A.2 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit 72 hours3 days 0.429 weeks 0.0986 months specified in the COLR.

Kewaunee Power Station 3.9.1-1 Amendment 207

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.

AND One source range audible count rate circuit shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One source range A.1 Suspend positive reactivity Immediately neutron flux monitor additions.

inoperable.

AND A.2 Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B. Two source range B.1 Initiate action to restore one Immediately neutron flux monitors source range neutron flux inoperable. monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months C. Required source range C.1 Initiate action to isolate Immediately audible count rate circuit unborated water sources.

inoperable.

Kewaunee Power Station 3.9.2-1 Amendment 207

Nuclear Instrumentation 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.9.2.2 -------------------------------NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months Kewaunee Power Station 3.9.2-2 Amendment 207

RHR and Coolant Circulation - High Water Level 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level LCO 3.9.3 One RHR loop shall be OPERABLE and in operation.

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

The required RHR loop may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, "Boron Concentration."

APPLICABILITY: MODE 6 with the water level 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspend operations that Immediately not met. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately RHR loop requirements.

AND Kewaunee Power Station 3.9.3-1 Amendment 207

RHR and Coolant Circulation - High Water Level 3.9.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Close equipment hatch and 4 hours0.167 days 0.0238 weeks 0.00548 months secure with four bolts.

AND A.5 Close one door in each air 4 hours0.167 days 0.0238 weeks 0.00548 months lock.

AND A.6. Verify each penetration 4 hours0.167 days 0.0238 weeks 0.00548 months providing direct access from the containment atmosphere to the outside atmosphere is either closed with a manual or automatic isolation valve, blind flange, or equivalent; or is capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify one RHR loop is in operation and circulating 12 hours0.5 days 0.0714 weeks 0.0164 months reactor coolant.

Kewaunee Power Station 3.9.3-2 Amendment 207

RHR and Coolant Circulation - Low Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.4 Two RHR loops shall be OPERABLE and one RHR loop shall be in operation.

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

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

a. The core outlet temperature is maintained > 10°F below saturation temperature;

b. No operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, "Boron Concentration"; and

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

2. One required RHR loop may be inoperable for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months for Surveillance testing, provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

OR A.2 Initiate action to establish Immediately 23 ft of water above the top of reactor vessel flange.

Kewaunee Power Station 3.9.4-1 Amendment 207

RHR and Coolant Circulation - Low Water Level 3.9.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR loop in B.1 Suspend operations that Immediately operation. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore one Immediately RHR loop to operation.

AND B.3 Close equipment hatch and 4 hours0.167 days 0.0238 weeks 0.00548 months secure with four bolts.

AND B.4 Close one door in each air 4 hours0.167 days 0.0238 weeks 0.00548 months lock.

AND B.5 Verify each penetration 4 hours0.167 days 0.0238 weeks 0.00548 months providing direct access from the containment atmosphere to the outside atmosphere is either closed with a manual or automatic isolation valve, blind flange, or equivalent; or is capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.

Kewaunee Power Station 3.9.4-2 Amendment 207

RHR and Coolant Circulation - Low Water Level 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one RHR loop is in operation and circulating 12 hours0.5 days 0.0714 weeks 0.0164 months reactor coolant.

SR 3.9.4.2 -----------------------------NOTE------------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power available to the required RHR pump that is not in operation.

Kewaunee Power Station 3.9.4-3 Amendment 207

Refueling Cavity Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Refueling Cavity Water Level LCO 3.9.5 Refueling cavity water level shall be maintained 23 ft above the top of reactor vessel flange.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within limit. irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify refueling cavity water level is 23 ft above 24 hours1 days 0.143 weeks 0.0329 months the top of reactor vessel flange.

Kewaunee Power Station 3.9.5-1 Amendment 207

Containment Penetrations 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Containment Penetrations LCO 3.9.6 The containment penetrations shall be in the following status:

a. The equipment hatch is closed and held in place by four bolts;

b. One door in each air lock is capable of being closed; and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere is either:

1. Closed by a manual or automatic isolation valve, blind flange, or equivalent; or

2. Capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.

APPLICABILITY: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Suspend movement of Immediately containment irradiated fuel assemblies penetrations not in within containment.

required status.

Kewaunee Power Station 3.9.6-1 Amendment 207

Containment Penetrations 3.9.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify each required containment penetration is in 7 days the required status.

SR 3.9.6.2 -------------------------------NOTE------------------------------

Not required to be met for containment purge and vent valve(s) in penetrations closed to comply with LCO 3.9.6.c.1.

Verify each required containment purge and vent 18 months valve actuates to the isolation position on an actual or simulated actuation signal.

Kewaunee Power Station 3.9.6-2 Amendment 207

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Kewaunee Power Station is located on property owned by Dominion Energy Kewaunee Inc. at a site on the west shore of Lake Michigan, approximately 30 miles east-southeast of the city of Green Bay, Wisconsin.

The minimum distance from the center line of the reactor containment to the site exclusion radius as defined in 10 CFR 100.3 is 1200 meters.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 121 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 29 control rod assemblies. The control material shall be silver indium cadmium as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.9776 weight percent;

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.5 of the USAR;

c. A nominal 8.3 inch rack cell lattice spacing between fuel assemblies placed in the canal pool; Kewaunee Power Station 4.0-1 Amendment 207

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

d. A minimum 10 inch center to center distance between fuel assemblies placed in the north and south pools; and

e. New and spent fuel assemblies stored in the north and south pools and the canal pool in accordance with LCO 3.7.15, "Spent Fuel Pool Storage."

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.9776 weight percent;

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.5 of the USAR;

c. keff < 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.5 of the USAR; and

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 645 ft 2 inches (mean sea level).

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1205 fuel assemblies.

Kewaunee Power Station 4.0-2 Amendment 207

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The shift manager shall be responsible for the control room command function.

During any absence of the shift manager from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Operator license shall be designated to assume the control room command function. During any absence of the shift manager from the control room while the unit is in MODE 5 or 6, an individual with an active Senior Operator license or Operator license shall be designated to assume the control room command function.

Kewaunee Power Station 5.1-1 Amendment 207

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the quality assurance program. The plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be maintained in appropriate plant documents.

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned if the reactor contains fuel and an additional non-licensed operator shall be assigned if the reactor is operating in MODES 1, 2, 3, or 4.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.e for a period of time not to exceed 2 hours0.0833 days 0.0119 weeks 0.00274 months , except in severe weather conditions, in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

Kewaunee Power Station 5.2-1 Amendment 207

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

c. A radiation technologist shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours0.0833 days 0.0119 weeks 0.00274 months , except in severe weather conditions, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The operations manager or assistant operations manager shall hold a Senior Operator license.

e. When the unit is in MODE 1, 2, 3, or 4 an individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Kewaunee Power Station 5.2-2 Amendment 207

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:

a. The radiation protection manager who shall meet or exceed the recommendation of Regulatory Guide 1.8, Revision 1-R, September 1975, or their equivalent as further clarified in Attachment 1 to the NRC Safety Evaluation Report enclosed with Amendment No. 46, dated July 12, 1982.

b. The education and experience eligibility requirements for operator license applicants, changes thereto, shall be those previously reviewed and approved by the NRC, specifically those referenced in NRC Safety Evaluation letter for Amendment 170, dated October 2, 2003.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Operator and a licensed Operator are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

Kewaunee Power Station 5.3-1 Amendment 207

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

Kewaunee Power Station 5.4-1 Amendment 207

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.1 and Specification 5.6.2.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s); and b) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2. Shall become effective after the approval of the plant manager; and

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

Kewaunee Power Station 5.5-1 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment The System Integrity Program (SIP) provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Safety Injection System, Chemical and Volume Control System, Containment Spray System, Miscellaneous Sumps and Drains System, Reactor Building Ventilation System, Residual Heat Removal System, and Primary Sampling System. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 18 months.

The provisions of SR 3.0.2 are applicable.

5.5.3 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; Kewaunee Power Station 5.5-2 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Radioactive Effluent Controls Program (continued)

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate 500 mrem/yr to the whole body and a dose rate 3000 mrem/yr to the skin; and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate 1500 mrem/yr to any organ;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program Surveillance Frequencies.

Kewaunee Power Station 5.5-3 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.4 Component Cyclic or Transient Limit Program This program provides controls to track the USAR, Section 4, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.5 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.

5.5.6 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities.

c. The provisions of SR 3.0.3 are applicable to inservice testing activities.

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

Kewaunee Power Station 5.5-4 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following provisions:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the as found condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes.

Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse. In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 150 gallons per day per SG.

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE."

Kewaunee Power Station 5.5-5 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Steam Generator (SG) Program (continued)

c. Provisions for SG tube repair criteria. Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube repair criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. An assessment of degradation shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.

2. Inspect 100% of the tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) without being inspected.

3. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

Kewaunee Power Station 5.5-6 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.8 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables;

b. Identification of the procedures used to measure the values of the critical variables;

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage;

d. Procedures for the recording and management of data;

e. Procedures defining corrective actions for all off control point chemistry conditions; and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.9 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of safety related filter ventilation systems in accordance with Regulatory Positions C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, ANSI N510-1975, ATSM D3803-1989, and AG-1.

The test described in Specification 5.5.9.a shall be performed once per 18 months and after each complete or partial replacement of the high efficiency particulate air (HEPA) filter bank and any maintenance on the system that could affect the HEPA bank bypass leakage.

The test described in Specification 5.5.9.b shall be performed after each complete or partial replacement of a charcoal adsorber bank or maintenance on the system that could affect the charcoal adsorber bank bypass leakage.

The test described in Specification 5.5.9.c shall be performed once per 18 months for filters in a standby status or after 720 hours30 days 4.286 weeks 0.986 months of filter operation, and following painting, fire, or chemical release in any ventilation zone communicating with the system.

The test described in Specification 5.5.9.d shall be performed once per 18 months.

Kewaunee Power Station 5.5-7 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Ventilation Filter Testing Program (VFTP) (continued)

The test described in Specification 5.5.9.e shall be performed after any maintenance or testing that could affect the air distribution within the systems.

a. Demonstrate for each of the safety related systems listed below that an inplace test of the HEPA filters shows a penetration and system bypass 1.0% when tested in accordance with Regulatory Position C.5.c of Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 at the system flowrate specified below +/- 10%.

Safety Related System Flow Rate (cfm)

Shield Building Ventilation System (SBVS) 5700 Auxiliary Building Special Ventilation (ASV) System 9000 Control Room Post Accident Recirculation (CRPAR) 2500 System

b. Demonstrate for each of the safety related systems listed below that an inplace test of the charcoal adsorber shows a penetration and system bypass 1.0% when tested in accordance with Regulatory Position C.5.d of Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 at the system flowrate specified below +/- 10%.

Safety Related System Flow Rate (cfm)

SBVS 5700 ASV System 9000 CRPAR System 2500

c. Demonstrate for each of the safety related systems listed below that a laboratory test of a sample of the charcoal adsorber shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 and AG-1 at a temperature of 30°C (86°F) and relative humidity of 95%.

Safety Related System Penetration SBVS 2.5%

ASV System 2.5%

CRPAR System 5%

Kewaunee Power Station 5.5-8 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Ventilation Filter Testing Program (VFTP) (continued)

d. Demonstrate for each of the safety related systems listed below that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with ANSI N510-1975 at the system flowrate specified below

+/- 10%.

Combined Delta P Safety Related System (in. wc) Flow Rate (cfm)

SBVS < 6.3 5700 ASV System < 6.3 9000 CRPAR System < 2.4 2500

e. Demonstrate for each of the safety related systems listed below that when tested at the system flowrate specified below (+/- 10%) the air distribution is uniform within +/- 20%.

Safety Related System Flow Rate (cfm)

SBVS 5700 ASV System 9000 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.10 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Gaseous Radioactive Waste Disposal System, the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure." The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures."

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Gaseous Radioactive Waste Disposal System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

Kewaunee Power Station 5.5-9 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tank's contents; and

c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Waste Disposal System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program Surveillance Frequencies.

5.5.11 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within limits;

2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil; and

3. A clear and bright appearance with proper color or a water and sediment content within limits;

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a.,

above, are within limits for ASTM 2D fuel oil; and

c. Total particulate concentration of the fuel oil is 10 mg/l when tested every 92 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies.

Kewaunee Power Station 5.5-10 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.12 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated USAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.

d. Proposed changes that meet the criteria of Specification 5.5.12.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.13 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

a. The SFDP shall contain the following:

1. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

4. Other appropriate limitations and remedial or compensatory actions.

Kewaunee Power Station 5.5-11 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Safety Function Determination Program (SFDP) (continued)

b. A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable; and

1. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

2. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

3. A required system redundant to the support system(s) for the supported systems described in Specifications 5.5.13.b.1 and 5.5.13.b.2 above is also inoperable.

c. The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.14 Containment Leakage Rate Testing Program

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 44.6 psig. The containment design pressure is 46 psig.

c. The maximum allowable containment leakage rate, La, at 46 psig (Peak Test Pressure), shall be 0.2% of containment air weight per day.

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and 0.75 La for Type A tests.

Kewaunee Power Station 5.5-12 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Containment Leakage Rate Testing Program (continued)

2. Air lock door seal leakage testing acceptance criteria for each door seal is a leakage rate of < 0.005 La when pressurized to 10 psig.

e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing program.

5.5.15 Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (Std) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a. The program allows the following RG 1.129, Revision 2 exceptions:

1. Battery temperature correction may be performed before or after conducting discharge tests.

2. RG 1.129, Regulatory Position 1, Subsection 2, "References," is not applicable to this program.

3. In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery after each performance of SR 3.8.6.5."

4 In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5. In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

b. The program shall include the following provisions:

1. Actions to restore battery cells with float voltage < 2.13 V; Kewaunee Power Station 5.5-13 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Battery Monitoring and Maintenance Program (continued)

2. Actions to determine whether the float voltage of the remaining battery cells is 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

5.5.16 Setpoint Control Program This program shall establish the requirements for ensuring that setpoints for automatic protective devices are initially within and remain within the assumptions of the applicable safety analysis. The program shall ensure that testing of automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A) verify that instrumentation will function as required.

a. The program shall list the Functions in the following specifications to which it applies:

1. LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation";

2. LCO 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Functions";

3. LCO 3.3.5, "Loss of Offsite Power (LOOP) Diesel Generator (DG) Start Instrumentation";

4. LCO 3.3.6, "Containment Purge and Vent Isolation Instrumentation";

and

5. LCO 3.3.7, "Control Room Post Accident Recirculation (CRPAR)

Actuation Instrumentation."

b. The program shall list the value of the Nominal Trip Setpoint (NTSP),

Allowable Value (AV), As-Found Tolerance (AFT), and As-Left Tolerance (ALT) (as applicable) for each Function described in Paragraph a. The NRC staff has not approved processing changes to Kewaunee Power Station instrumentation setpoints under 10 CFR 50.59 using an approved setpoint methodology as described in Option B of TSTF-493. NRC approval using Kewaunee Power Station 5.5-14 Amendment 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Setpoint Control Program (continued) 10 CFR 50.90 is required to change the listed value of the NTSP, AV, AFT, and ALT (as applicable) for each Function described in Paragraph a.

c. The program shall establish methods to ensure that Functions described in Paragraph a. will function as required by verifying the as-left and as-found settings are consistent with the list of values established by Paragraph b. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

d. The program shall identify the Functions described in Paragraph a. that are automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A). The NTSP of these Functions are Limiting Safety System Settings. These Functions shall be demonstrated to be functioning as required by applying the following requirements during CHANNEL CALIBRATIONS, CHANNEL OPERATIONAL TESTS, and TRIP ACTUATING DEVICE OPERATIONAL TESTS that verify the NTSP.

1. The as-found value of the instrument channel trip setting shall be compared with the previous as-left value or the specified NTSP.

2. If the as-found value of the instrument channel trip setting differs from the previous as-left value or the specified NTSP by more than the pre-defined test acceptance criteria band (i.e., the specified AFT), then the instrument channel shall be evaluated before declaring the SR met and returning the instrument channel to service. This condition shall be entered in the plant corrective action program.

3. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

4. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the NTSP at the completion of the surveillance test; otherwise, the channel is inoperable (setpoints may be more conservative than the NTSP provided that the as-found and as-left tolerances apply to the actual setpoint used to confirm channel performance).

e. The program shall be specified in the Technical Requirements Manual.

Kewaunee Power Station 5.5-15 Amendment 207

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted by May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.3 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1, "Reactor Core SLs";

2. LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3. LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

Kewaunee Power Station 5.6-1 Amendment 207

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. LCO 3.1.5, "Shutdown Bank Insertion Limits";

5. LCO 3.1.6, "Control Bank Insertion Limits";

6. LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))";

7. LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor ( FNH )";

8. LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)";

9. LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation,"

Functions 6 and 7 (Overtemperature T and Overpower T, respectively);

10. LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits"; and

11. LCO 3.9.1, "Boron Concentration."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. When an initial assumed power level of 102% of the original RATED THERMAL POWER is specified in a previously approved method, 100.6% of uprated RATED THERMAL POWER may be used only when the main feedwater flow measurement (used as the input for reactor thermal output) is provided by the Crossflow Ultrasonic Flow Measurement System (Crossflow System) as described in the Reference listed in Specification 5.6.3.b.14 below. When main feedwater flow measurements from the Crossflow System are unavailable, a power measurement uncertainty consistent with the instrumentation used shall be applied.

Future revisions of approved analytical methods listed in this Technical Specification that currently reference the original Appendix K uncertainty of 102% of the original rated power should include the condition given above allowing use of 100.6% of uprated power in the safety analysis methodology when the Crossflow System is used for main feedwater flow measurement.

The approved analytical methods are described in the following documents:

1. Topical Report WPSRSEM-NP, "Kewaunee Nuclear Power Plant -

Review For Kewaunee Reload Safety Evaluation Methods."

2. WCAP-12945-P-A (Proprietary), "Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis,"

Volume I and Volume II-V.

Kewaunee Power Station 5.6-2 Amendment 207

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

3. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."

4. WCAP-10054-P-A, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," Addendum 2.

5. XN-NF-82-06 (P)(A) Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup."

6. ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU."

7. EMF-92-116 (P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs."

8. WCAP-10216-P-A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification."

9. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology."

10. WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature T and Thermal Overpower T trip functions."

11. WCAP-14449-P-A, "Application of Best-Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection."

12. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report."

13. WCAP-11397-P-A, "Revised Thermal Design Procedure."

14. CENP-397-P-A, "Improved Flow Measurement Accuracy Using Cross Flow Ultrasonic Flow Measurement Technology."

15. Topical Report DOM-NAF-5-A, "Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS)."

The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

Kewaunee Power Station 5.6-3 Amendment 207

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.4 Post Accident Monitoring Report When a report is required by Condition B of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days.

The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.5 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.7, "Steam Generator (SG) Program." The report shall include:

a. The scope of inspections performed on each SG;

b. Active degradation mechanisms found;

c. Nondestructive examination techniques utilized for each degradation mechanism;

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications;

e. Number of tubes plugged during the inspection outage for each active degradation mechanism;

f. Total number and percentage of tubes plugged to date;

g. The results of condition monitoring, including the results of tube pulls and in-situ testing; and

h. The effective plugging percentage for all plugging in each SG.

Kewaunee Power Station 5.6-4 Amendment 207

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously displays radiation dose rates in the area;

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or Kewaunee Power Station 5.7-1 Amendment 207

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift manager, radiation protection manager, or his or her designees; and

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

Kewaunee Power Station 5.7-2 Amendment 207

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

d. Each individual group entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area; or (ii) Be under surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where Specifications 5.7.2.d.2 and 5.7.2.d.3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

Kewaunee Power Station 5.7-3 Amendment 207

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Kewaunee Power Station 5.7-4 Amendment 207

v t e Letter Sequence Acceptance Review
TAC:ME2139, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed)
Initiation Request, Request, Request, Request, Request Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance Questions 13 January 2010 11 March 2010 Answers Results Approval, Approval, Approval Other: ML093130368, ML102210288, ML102371088, ML102371098, ML102371109, ML102371140, ML102371178, ML102371203, ML102371205, ML102371210, ML102371257, ML102371260, ML102371266, ML102371269, ML102371282, ML102371283, ML102371290, ML102371292, ML102371294, ML102371297, ML102580704, ML102580706, ML102580709, ML102580710, ML102670754, ML102730398, ML102730399, ML103370691, ML110260316
MONTHYEAR2010-07-01 [Table View]

ML102020664

Text

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