ML22153A177

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Attachment 1 - Marked-Up Existing Technical Specifications
ML22153A177
Person / Time
Site: Callaway Ameren icon.png
Issue date: 06/02/2022
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22153A174 List:
References
LDCN 22-0002, ULNRC-06729
Download: ML22153A177 (31)
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Text

Attachment 1 to to ULNRC-06729 Page 1 of 31 ATTACHMENT 1 MARKED-UP EXISTING TECHNICAL SPECIFICATIONS The following pages depict the changes proposed to the existing Technical Specifications.

30 pages follow this cover sheet

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: For Westinghouse fuel, the 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 1.17 for the WRB-2 DNB correlation.

For Westinghouse fuel, the 2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080ºF, decreasing by 58ºF per 10,000 MWd/MTU of burnup.

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

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

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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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

CALLAWAY PLANT 2.0-1 Amendment 216

INSERT A 2.1.1.3 For Framatome GAIA fuel, the DNBR shall be maintained 1.12 for the ORFEO-GAIA DNB correlation.

2.1.1.4 For Framatome GAIA fuel, the peak fuel centerline temperature shall be maintained

< 4901°F, decreasing linearly by 13.7°F per 10,000 MWd/MTU of burnup.

CHAPTER TABLE OF CONTENTS CHAPTER 3.2 POWER DISTRIBUTION LIMITS Westinghouse COLR Methods Section Page 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

(FQ Methodology) ................................................................................................ 3.2-1 FNH A

ACTIONS ........................................................................................................ 3.2-1 SURVEILLANCE REQUIREMENTS ............................................................... 3.2-3 INSERT B Westinghouse COLR Methods 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( ) .................................................... 3.2-6 ACTIONS ........................................................................................................ 3.2-6 A SURVEILLANCE REQUIREMENTS ............................................................... 3.2-8 INSERT C Westinghouse COLR Methods 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ........................................................................... 3.2-9 A

ACTIONS ...................................................................................................... 3.2-9 SURVEILLANCE REQUIREMENTS ............................................................... 3.2-9 INSERT D 3.2.4 QUADRANT POWER TILT RATIO (QPTR) ..................................................... 3.2-10 ACTIONS .................................................................................................... 3.2-10 SURVEILLANCE REQUIREMENTS ............................................................. 3.2-13 CALLAWAY PLANT 3.2-i

INSERT B 3.2.1B Heat Flux Hot Channel Factor (FQ(Z))

Framatome COLR Methods....................................................................................... 3.2-x ACTIONS ............................................................................................................. 3.2-x SURVEILLANCE REQUIREMENTS............................................................... 3.2-x INSERT C 3.2.2B Nuclear Enthalpy Rise Hot Channel Factor (FNH)

Framatome COLR Methods............................................................................................ 3.2-x ACTIONS ................................................................................................................. 3.2-x SURVEILLANCE REQUIREMENTS.................................................................... 3.2-x INSERT D 3.2.3B AXIAL FLUX DIFFERENCE (AFD) Framatome COLR Methods.............................. 3.2-x ACTIONS .................................................................................................................... 3.2-x SURVEILLANCE REQUIREMENTS....................................................................... 3.2-x

Westinghouse COLR Methods FQ(Z) (FQ Methodology) 3.2.1 Westinghouse COLR Methods A

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

A LCO 3.2.1 FQ Z , as approximated by F QC Z and F W Q Z , shall be within the limits specified in the COLR.

A APPLICABILITY: MODE 1. -------------------------------------- NOTE ------------------------------------

This LCO is not applicable when Framatome COLR methods ACTIONS govern COLR development COMPLETION CONDITION REQUIRED ACTION TIME A. F QC Z not within limit. A.1 Reduce THERMAL 15 minutes after POWER 1% RTP for each F QC Z each 1% F QC Z exceeds determination limit.

AND A.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each Neutron Flux High trip F QC Z setpoints 1% for each determination 1% F QC Z exceeds limit.

AND A.3 Reduce Overpower T 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each trip setpoints 1% for F QC Z C

each 1% F Q Z exceeds determination limit.

AND A.4 Perform SR 3.2.1.1. Prior to increasing THERMAL A POWER above the limit of Required Action A.1 (continued)

CALLAWAY PLANT 3.2-1 Amendment No. 133

Westinghouse COLR Methods FQ(Z) (FQ Methodology) 3.2.1 A

ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. FW Q Z not within limits. B.1 Reduce AFD limits 1% 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for each 1% F WQ Z exceeds limit.

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

CALLAWAY PLANT 3.2-2 Amendment No. 133

Westinghouse COLR Methods FQ(Z) (FQ Methodology) 3.2.1 A

SURVEILLANCE REQUIREMENTS

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

During power escalation following shutdown, 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 F QC Z is within limit. Once after each refueling prior to A THERMAL POWER exceeding 75% RTP AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which F QC Z was last verified AND In accordance with the Surveillance Frequency Control Program (continued)

CALLAWAY PLANT 3.2-3 Amendment No. 202

Westinghouse COLR Methods FQ(Z) (FQ Methodology) 3.2.1 A

SURVEILLANCE REQUIREMENTS (continued)

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

If F QC Z measurements indicate A

F QC Z maximum over z -------------------

KZ has increased since the previous evaluation of F QC Z

a. Increase F W Q Z by the appropriate factor specified in the COLR and reverify F W Q Z is within limits; or A
b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive power distribution measurements indicate.

F QC Z maximum over z -------------------

KZ has not increased.

Verify F W Once after each Q Z is within limit refueling prior to THERMAL POWER exceeding 75%

RTP AND (continued)

CALLAWAY PLANT 3.2-4 Amendment No. 182

Westinghouse COLR Methods FQ(Z) (FQ Methodology) 3.2.1 A

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued) Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after A achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which was last verified AND In accordance with the Surveillance Frequency Control Program INSERT E follows this page CALLAWAY PLANT 3.2-5 Amendment 202

FQ(Z) Framatome COLR Methods INSERT E 3.2.1B 3.2 POWER DISTRIBUTION LIMITS 3.2.1B Heat Flux Hot Channel Factor [FQ(Z)] Framatome COLR Methods LCO 3.2.1B The FQ(Z) as approximated by (Z) and (Z) shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

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

This LCO is not applicable when Westinghouse COLR Methods govern COLR development ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (Z) not within A.1 Reduce THERMAL POWER 1% RTP for 15 minutes after each (Z) the limit. each 1% (Z) exceeds limit. determination AND A.2 Reduce Power Range Neutron Flux - High 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each (Z) trip setpoints 1% for each 1% (Z) determination exceeds limit.

AND A.3 Reduce Overpower T trip setpoints 1% 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each (Z)

RTP for each 1% (Z) exceeds limit. determination AND A.4 Perform SR 3.2.1B.1 and SR 3.2.1B.2. Prior to increasing THERMAL POWER above the limit of Required Action A.1 1

FQ(Z) Framatome COLR Methods 3.2.1B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (Z) not within B.1.1 Reduce the AFD limits based on the current 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit. target AFD band and V(Z) function by the appropriate amount (%AFD/%FQ) specified in the COLR for each 1% the current (Z) exceeds limit.

AND B.1.2 Perform SR 3.2.1B.1 and SR 3.2.1B.2. Prior to restoration of AFD limits less restrictive than the limits of Required Action B.1.1 OR B.2.1 Reduce THERMAL POWER 1% RTP 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for each 1% (Z) exceeds limit.

AND B.2.2 Reduce Power Range Neutron Flux - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> High trip setpoints 1% for each 1%

(Z) exceeds limit.

AND B.2.3 Reduce Overpower T trip 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> setpoints 1% RTP for each 1%

(Z) exceeds limit.

AND Prior to increasing THERMAL B.2.4 Perform SR 3.2.1B.1 and SR 3.2.1B.2.

POWER above the limit of Required Action B.2.3.

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

2

FQ(Z) Framatome COLR Methods 3.2.1B 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 3.2.1B.1 Verify (Z) is within limit Once after each refueling prior to THERMAL specified in the COLR. POWER exceeding 75% RTP AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which (Z) was last verified AND In accordance with Surveillance Frequency Control Program SR 3.2.1B.2 Verify (Z) is within limit Once after each refueling prior to THERMAL specified in the COLR. POWER exceeding 75% RTP AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which V (Z) was last verified AND In accordance with Surveillance Frequency Control Program 3

Westinghouse COLR Methods F NH 3.2.2 Westinghouse COLR Methods A

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

A LCO 3.2.2 F NH shall be within the limits specified in the COLR.

A APPLICABILITY: MODE 1. -------------------------------------- NOTE ------------------------------------

This LCO is not applicable when Framatome COLR Methods ACTIONS govern COLR development COMPLETION CONDITION REQUIRED ACTION TIME A. ------------- NOTE ------------- A.1.1 Restore F NH to within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Actions A.2 and A.3 must be completed limit.

whenever Condition A is entered. OR A.1.2.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> F NH not within limit. POWER to < 50% RTP.

AND A.1.2.2 Reduce Power Range 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Neutron Flux - High trip setpoints to 55% RTP.

AND A.2 Perform SR 3.2.2.1. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A

AND (continued)

CALLAWAY PLANT 3.2-6 Amendment No. 133

Westinghouse COLR Methods F NH 3.2.2 A

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. (continued) A.3 ------------ 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 A 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER reaching 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

CALLAWAY PLANT 3.2-7 Amendment 133

Westinghouse COLR Methods F NH 3.2.2 A

SURVEILLANCE REQUIREMENTS

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

During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FNH is within limits specified in the COLR. Once after each refueling prior to A THERMAL POWER exceeding 75% RTP AND In accordance with the Surveillance Frequency Control Program INSERT F follows this page CALLAWAY PLANT 3.2-8 Amendment No. 202

FN H Framatome COLR Methods INSERT F 3.2.2B 3.2 POWER DISTRIBUTION LIMITS 3.2.2B Nuclear Enthalpy Rise Hot Channel Factor (FNH) Framatome COLR Methods LCO 3.2.2B FNH shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

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

This LCO is not applicable when Westinghouse COLR Methods govern COLR development ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1.1 Restore to within limit. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Actions A.2 and A.3 must be completed OR whenever Condition A is entered. A.1.2.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

< 50% RTP.

AND not within the limit.

A.1.2.2 Reduce Power Range Neutron Flux - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> High trip setpoints to 55% RTP AND A.2 Perform SR 3.2.2B.1. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND (continued) 1

FN H Framatome COLR Methods 3.2.2B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 ----------------------NOTE-----------------------

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

Perform SR 3.2.2B.1. Prior to THERMAL POWER exceeding 50%

RTP AND Prior to THERMAL POWER exceeding 75%

RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER reaching 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

2

FN H Framatome COLR Methods 3.2.2B SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2B.1 ----------------------------NOTE----------------------------

If is within limits but two consecutive measurements indicate that is increasing with exposure, then:

a. Increase FVQ(z) by value specified in the COLR and re-verify that FVQ(z) is within limits; or
b. Perform SR 3.2.1B.2 and SR 3.2.3B.2 once per 7 EFPD until two successive measurements indicate FNH is not increasing.

Once after each refueling prior to Verify FN H is within the limit specified in the COLR. THERMAL POWER exceeding 75% RTP AND In accordance with Surveillance Frequency Control Program 3

Westinghouse COLR Methods AFD (RAOC Methodology) 3.2.3 A

Westinghouse COLR Methods 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)

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

A

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.

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

This LCO is not applicable when Framatome COLR Methods ACTIONS govern COLR development COMPLETION CONDITION REQUIRED ACTION 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 In accordance channel. with the A Surveillance Frequency Control Program INSERT G follows this page CALLAWAY PLANT 3.2-9 Amendment No. 202

INSERT G AFD Framatome COLR Methods 3.2.3B 3.2 POWER DISTRIBUTION LIMITS 3.2.3B AXIAL FLUX DIFFERENCE (AFD) Framatome COLR Methods LCO 3.2.3B AFD shall be maintained within the AFD limits defined by the sum of the target AFD and the target AFD band specified in the COLR.

APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP.

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

This LCO is not applicable when Westinghouse COLR Methods govern COLR development ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------ NOTE ------------ A.1 Reduce THERMAL POWER to < 50% RTP. 30 minutes AFD shall be considered not within its limits when two or more OPERABLE excore channels indicate AFD not within the limits.

AFD not within the limits.

1

AFD Framatome COLR Methods 3.2.3B SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3B.1 Verify AFD is within limits for each OPERABLE In accordance with Surveillance excore channel. Frequency Control Program SR 3.2.3B.2 ------------------------------NOTE----------------------------

a. The initial target AFD after each refueling may be determined from design predictions.
b. Between measurements, the target AFD may be updated by adding the most recently measured AFD value and the change in the predicted AFD values since that measurement.
c. Update, with the new 'target AFD' value, the

'AFD limits' based on the current 'target AFD band', which was expressed in deviation from the target AFD.

Determine, at steady state and high power (as Once within 31 EFPD after each refueling near RTP as practical, equilibrium xenon, and AND normal bank positions), the target AFD when FQ(Z) is measured in accordance with In accordance with Surveillance SR 3.2.1B.2. Frequency Control Program 2

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 COMPLETION CONDITION REQUIRED ACTION TIME A. QPTR not within limit. A.1 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each POWER 3% from RTP QPTR for each 1% of QPTR determination

> 1.00.

AND A.2 Determine QPTR. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND A.3 ----------- NOTE --------- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after Perform applicable SR achieving based on governing equilibrium COLR development conditions from a method. THERMAL

POWER reduction Perform SR 3.2.1A.1, per Required SR 3.2.1A.2 and SR Action A.1 3.2.2A.1.

AND OR Once per 7 days Perform SR 3.2.1B.1, thereafter SR 3.2.1B.2 and SR 3.2.2B.1.

AND (continued)

CALLAWAY PLANT 3.2-10 Amendment No. 133

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

CALLAWAY PLANT 3.2-11 Amendment 133

QPTR 3.2.4 ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. (continued) A.6 ------------ NOTES -------

1. Perform Required Action A.6 only after Required Action A.5 is completed.
2. Perform applicable SR based on governing COLR development method.

Perform SR 3.2.1A.1, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after SR 3.2.1A.2 and achieving SR 3.2.2A.1. equilibrium conditions not to OR exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing Perform SR 3.2.1B.1, THERMAL SR 3.2.1B.2 and POWER above the SR 3.2.2B.1. limit of Required Action A.1 B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to 50% RTP Time not met.

CALLAWAY PLANT 3.2-12 Amendment 133

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 --------------------------------- NOTE ------------------------------

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. In accordance with the Surveillance Frequency Control Program SR 3.2.4.2 --------------------------------- NOTE ------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER

> 75% RTP.

Verify QPTR is within limit using power distribution In accordance measurement information. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.2-13 Amendment No. 202

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Callaway Plant site consists of approximately 2,767 acres of rural land 10 miles southeast of the city of Fulton in Callaway County, Missouri, and 80 miles west of the St. Louis metropolitan area.

4.2 Reactor Core 4.2.1 Fuel Assemblies zircaloy, ZIRLOTM or M5 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitution of fuel rods by zirconium alloy or stainless steel filler rods may be used in accordance with approved applications of fuel rod configurations. 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 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 53 control rod assemblies. The control rod material shall be silver indium cadmium, hafnium metal, or a mixture of both types, 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 nominal U-235 enrichment of 5.0 weight percent; For fuel with enrichments greater than 4.6 nominal weight percent of U-235, the combination of enrichment and integral fuel burnable absorbers shall be sufficient so that the requirements of 4.3.1.1.b are met.

(continued)

CALLAWAY PLANT 4.0-1 Amendment 133

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 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. Moderator Temperature Coefficient limits in Specification 3.1.3,
2. Shutdown Bank Insertion Limit for Specification 3.1.5, 3.2.1A, and FCQ(z),

FVQ(z), Measurement 3. Control Bank Insertion Limits for Specification 3.1.6, 3.2.3A and 3.2.3B, Uncertainty, s Manufacturing 4. Axial Flux Difference Limits for Specification 3.2.3, Tolerance, and V(z) for Specification 3.2.1B

5. Heat Flux Hot Channel Factor, FQ(Z), FQRTP, K(Z), W(Z) and FQ Penalty Factors for Specification 3.2.1,
6. Nuclear Enthalpy Rise Hot Channel Factor F H N

, FH RTP, and Power Factor Multiplier, PFH, limits for Specification 3.2.2,

7. Shutdown Margin Limits for Specifications 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.2.2A, and measured FN H, and 3.1.8, F H uncertainty, UH for N
8. Reactor Core Safety Limits Figure for Specification 2.1.1, Specification 3.2.2B
9. Overtemperature T and Overpower T Setpoint Parameters for Specification 3.3.1, and
10. Reactor Coolant System Pressure and Temperature DNB Limits for Specification 3.4.1.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. WCAP-9272-P-A, WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY.
2. WCAP-10216-P-A, RELAXATION OF CONSTANT AXIAL OFFSET CONTROL AND FQ SURVEILLANCE TECHNICAL SPECIFICATION.
3. WCAP-10266-P-A, THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE.

(continued)

CALLAWAY PLANT 5.0-24 Amendment No. 215 l

Reporting Requirements 5.6 5.6 Reporting Requirements

4. WCAP-12610-P-A, VANTAGE + FUEL ASSEMBLY REFERENCE CORE REPORT.
5. WCAP-11397-P-A, REVISED THERMAL DESIGN PROCEDURE.
6. WCAP-14565-P-A, VIPRE-01 MODELING AND QUALIFICATION FOR PRESSURIZED WATER REACTOR NON-LOCA THERMAL-HYDRAULIC SAFETY ANALYSIS.
7. WCAP-10851-P-A, IMPROVED FUEL PERFORMANCE MODELS FOR WESTINGHOUSE FUEL ROD DESIGN AND SAFETY EVALUATIONS.
8. WCAP-15063-P-A, WESTINGHOUSE IMPROVED PERFORMANCE ANALYSIS AND DESIGN MODEL (PAD 4.0).
9. WCAP-8745-P-A, DESIGN BASES FOR THE THERMAL OVERPOWER DT AND THERMAL OVERTEMPERATURE DT TRIP FUNCTIONS.
10. WCAP-10965-P-A, ANC: A WESTINGHOUSE ADVANCED NODAL COMPUTER CODE.
11. WCAP-10965-P-A Addendum 2-A, Qualification of the New Pin Power Recovery Methodolgy.
12. WCAP-13524-P-A, APOLLO: A ONE DIMENSIONAL NEUTRON DIFFUSION THEORY PROGRAM.
13. WCAP-14565-P-A Addendum 2-P-A, Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications.
14. WCAP-16045-P-A, Qualification of the Two-Dimensional Transport Code PARAGON.
15. WCAP-16045-P-A Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology.

INSERT H

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.

(continued)

CALLAWAY PLANT 5.0-25 Amendment No. 217

Reporting Requirements 5.6 5.6 Reporting Requirements

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing and PORV lift setting as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
1. Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits, and
2. Specification 3.4.12, Cold Overpressure Mitigation System (COMS).
b. The analytical methods used to determine the RCS pressure and temperature and COMS PORV limits shall be those previously reviewed and approved by the NRC, specifically those described in WCAP-14040-NP-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves".
c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.7 Not used.

5.6.8 PAM Report When a report is required by Condition B or F 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.

5.6.9 Not used.

(continued)

CALLAWAY PLANT 5.0-26 Amendment No. 217 l

INSERT H

16. EMF-2103(P)(A), Realistic Large Break LOCA Methodology for Pressurized Water Reactors. [Methodology for Specification 3.2.1, FQ]

17 EMF-2328(P)(A), PWR Small Break LOCA Evaluation Model, S-RELAP5 Based. [Methodology for Specification 3.2.1, FQ]

18. EMF-2310(P)(A), SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors.
19. XN-NF-82-21(P)(A), Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations.
20. EMF-92-081(P)(A), Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors.
21. ANP-10341(P)(A), The ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations.
22. XN-75-21(P)(A), XCOBRA-IIIC: A Computer Code to Determine the Distribution of Coolant During Steady State and Transient Core Operation.
23. ANP-10311P-A, COBRA-FLX: A Core Thermal-Hydraulic Analysis Code.
24. XN-NF-82-06(P)(A) Supplement 2, 4, and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup.
25. XN-75-32(P)(A) Supplements 1, 2, 3, and 4, Computational Procedure for Evaluating Fuel Rod Bowing.
26. Insert Reference to Callaway SER for fuel transition LAR.
27. ANP-10297P-A, The ARCADIA Reactor Analysis System for PWRs Methodology Description and Benchmarking Results.
28. ANP-10297P-A, Supplement 1PA, The ARCADIA Reactor Analysis System for PWRs Methodology Description and Benchmarking Results.
29. ANP-10338P-A, AREA - ARCADIA Rod Ejection Accident.
30. ANP-10323P-A, GALILEO Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactors.
31. BAW-10231P-A, COPERNIC Fuel Rod Design Computer Code.
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