ML22153A177
| ML22153A177 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| 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) | |
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
CALLAWAY PLANT 2.0-1 Amendment 216 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-2 DNB correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080ºF, decreasing by 58ºF per 10,000 MWd/MTU of burnup.
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.
For Westinghouse fuel, the For Westinghouse fuel, the INSERT A
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.
CALLAWAY PLANT 3.2-i CHAPTER TABLE OF CONTENTS CHAPTER 3.2 POWER DISTRIBUTION LIMITS Section Page 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
(FQ Methodology)................................................................................................ 3.2-1 ACTIONS........................................................................................................ 3.2-1 SURVEILLANCE REQUIREMENTS............................................................... 3.2-3 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( ).................................................... 3.2-6 ACTIONS........................................................................................................ 3.2-6 SURVEILLANCE REQUIREMENTS............................................................... 3.2-8 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)........................................................................... 3.2-9 ACTIONS...................................................................................................... 3.2-9 SURVEILLANCE REQUIREMENTS............................................................... 3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR)..................................................... 3.2-10 ACTIONS.................................................................................................... 3.2-10 SURVEILLANCE REQUIREMENTS............................................................. 3.2-13 INSERT B INSERT C INSERT D A
A A
Westinghouse COLR Methods Westinghouse COLR Methods Westinghouse COLR Methods FNH
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
CALLAWAY PLANT 3.2-1 Amendment No. 133 FQ(Z) (FQ Methodology) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))(FQ Methodology)
, as approximated by and
, shall be within the limits specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
not within limit.
A.1 Reduce THERMAL POWER 1% RTP for each 1%
exceeds limit.
AND 15 minutes after each determination A.2 Reduce Power Range Neutron Flux High trip setpoints 1% for each 1%
exceeds limit.
AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each determination A.3 Reduce Overpower T trip setpoints 1% for each 1%
exceeds limit.
AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each determination A.4 Perform SR 3.2.1.1.
Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)
FQ Z
FC Q Z
FW Q Z
FC Q Z
FC Q Z
FC Q Z
FC Q Z
FC Q Z
FC Q Z
FC Q Z
A Westinghouse COLR Methods A
A Westinghouse COLR Methods
NOTE ------------------------------------
This LCO is not applicable when Framatome COLR methods govern COLR development A
FQ(Z) (FQ Methodology) 3.2.1 ACTIONS (continued)
CALLAWAY PLANT 3.2-2 Amendment No. 133 B.
not within limits.
B.1 Reduce AFD limits 1%
for each 1%
exceeds limit.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C.
Required Action and associated Completion Time not met.
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 /> CONDITION REQUIRED ACTION COMPLETION TIME FW Q Z
FW Q Z
A Westinghouse COLR Methods
FQ(Z) (FQ Methodology) 3.2.1 CALLAWAY PLANT 3.2-3 Amendment No. 202 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 is within limit.
Once after each refueling prior to 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 was last verified AND In accordance with the Surveillance Frequency Control Program (continued)
FC Q Z
FC Q Z
A Westinghouse COLR Methods A
FQ(Z) (FQ Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
CALLAWAY PLANT 3.2-4 Amendment No. 182 SR 3.2.1.2
NOTE ------------------------------
If measurements indicate maximum over z has increased since the previous evaluation of a.
Increase by the appropriate factor specified in the COLR and reverify is within limits; or b.
Repeat SR 3.2.1.2 once per 7 EFPD until two successive power distribution measurements indicate.
maximum over z has not increased.
Verify is within limit Once after each refueling prior to THERMAL POWER exceeding 75%
RTP AND (continued)
SURVEILLANCE FREQUENCY FC Q Z
FC Q Z
K Z
FC Q Z
FW Q Z
FW Q Z
FC Q Z
K Z
FW Q Z
A Westinghouse COLR Methods A
A
FQ(Z) (FQ Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS CALLAWAY PLANT 3.2-5 Amendment 202 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 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 SURVEILLANCE FREQUENCY INSERT E follows this page A
Westinghouse COLR Methods A
1 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 the limit.
A.1 Reduce THERMAL POWER 1% RTP for
15 minutes after each (Z) determination
each 1% (Z) exceeds limit.
AND A.2 Reduce Power Range Neutron Flux - High trip setpoints 1% for each 1% (Z) exceeds limit.
AND A.3 Reduce Overpower T trip setpoints 1%
RTP for each 1% (Z) exceeds limit.
AND A.4 Perform SR 3.2.1B.1 and SR 3.2.1B.2.
FQ(Z) Framatome COLR Methods 3.2.1B 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each (Z) determination 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each (Z) determination Prior to increasing THERMAL POWER above the limit of Required Action A.1 INSERT E
2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
B. (Z) not within limit.
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 /> 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 FQ(Z) Framatome COLR Methods 3.2.1B
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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Prior to increasing THERMAL POWER above the limit of Required Action B.2.3.
OR B.2.1 Reduce THERMAL POWER 1% RTP
for each 1% (Z) exceeds limit.
AND B.2.2 Reduce Power Range Neutron Flux -
High trip setpoints 1% for each 1%
(Z) exceeds limit.
AND B.2.3 Reduce Overpower T trip
setpoints 1% RTP for each 1%
(Z) exceeds limit.
AND B.2.4 Perform SR 3.2.1B.1 and SR 3.2.1B.2.
C.
Required Action and associated Completion Time not met.
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 />
3 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 specified in the COLR.
Once after each refueling prior to 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 (Z) was last verified AND In accordance with Surveillance Frequency Control Program FQ(Z) Framatome COLR Methods 3.2.1B
SR 3.2.1B.2 Verify (Z) is within limit specified in the COLR.
Once after each refueling prior to 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 V (Z) was last verified AND In accordance with Surveillance Frequency Control Program
CALLAWAY PLANT 3.2-6 Amendment No. 133 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (
)
LCO 3.2.2 shall be within the limits specified in the COLR.
APPLICABILITY:
MODE 1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE -------------
Required Actions A.2 and A.3 must be completed whenever Condition A is entered.
not within limit.
A.1.1 Restore to within limit.
OR A.1.2.1 Reduce THERMAL POWER to < 50% RTP.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours A.1.2.2 Reduce Power Range Neutron Flux - High trip setpoints to 55% RTP.
AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A.2 Perform SR 3.2.2.1.
AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
FN H
FN H
FN H
FN H
FN H
Westinghouse COLR Methods A
NOTE ------------------------------------
This LCO is not applicable when Framatome COLR Methods govern COLR development A
Westinghouse COLR Methods A
A
3.2.2 ACTIONS FN H
CALLAWAY PLANT 3.2-7 Amendment 133 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 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 associated Completion Time not met.
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 /> CONDITION REQUIRED ACTION COMPLETION TIME Westinghouse COLR Methods A
A
3.2.2 FN H
CALLAWAY PLANT 3.2-8 Amendment No. 202 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 is within limits specified in the COLR.
Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND In accordance with the Surveillance Frequency Control Program FN H
INSERT F follows this page Westinghouse COLR Methods A
A
1 3.2 POWER DISTRIBUTION LIMITS 3.2.2B Nuclear Enthalpy Rise Hot Channel Factor (FNH) Framatome COLR Methods LCO 3.2.2B FN H 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-------------
Required Actions A.2 and A.3 must be completed whenever Condition A is entered.
not within the limit.
A.1.1 Restore to within limit.
OR A.1.2.1 Reduce THERMAL POWER to
< 50% RTP.
AND A.1.2.2 Reduce Power Range Neutron Flux -
High trip setpoints to 55% RTP 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A.2 Perform SR 3.2.2B.1.
AND (continued) 3.2.2B FN H Framatome COLR Methods INSERT F
2 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 associated Completion Time not met.
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 /> 3.2.2B FN H Framatome COLR Methods
3 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.
Verify FN H is within the limit specified in the COLR.
Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND In accordance with Surveillance Frequency Control Program 3.2.2B FN H Framatome COLR Methods
CALLAWAY PLANT 3.2-9 Amendment No. 202 AFD (RAOC Methodology) 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)
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 SURVEILLANCE REQUIREMENTS CONDITION REQUIRED ACTION COMPLETION TIME A.
AFD not within limits.
A.1 Reduce THERMAL POWER to < 50% RTP.
30 minutes SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore channel.
In accordance with the Surveillance Frequency Control Program INSERT G follows this page Westinghouse COLR Methods A
NOTE ------------------------------------
This LCO is not applicable when Framatome COLR Methods govern COLR development Westinghouse COLR Methods A
A A
1 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 ------------
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.
A.1 Reduce THERMAL POWER to < 50% RTP.
30 minutes AFD Framatome COLR Methods 3.2.3B INSERT G
2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3B.1 Verify AFD is within limits for each OPERABLE excore channel.
In accordance with Surveillance 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 near RTP as practical, equilibrium xenon, and normal bank positions), the target AFD when FQ(Z) is measured in accordance with SR 3.2.1B.2.
Once within 31 EFPD after each refueling AND In accordance with Surveillance Frequency Control Program AFD Framatome COLR Methods 3.2.3B
CALLAWAY PLANT 3.2-10 Amendment No. 133 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 POWER 3% from RTP for each 1% of QPTR
> 1.00.
AND 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination A.2 AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> A.3 Determine QPTR.
NOTE ---------
Perform applicable SR based on governing COLR development method.
Perform SR 3.2.1A.1, SR 3.2.1A.2 and SR 3.2.2A.1.
OR Perform SR 3.2.1B.1, SR 3.2.1B.2 and 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 /> after achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND (continued)
QPTR 3.2.4 ACTIONS CALLAWAY PLANT 3.2-11 Amendment 133 A.
(continued)
A.4 Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition.
AND Prior to increasing THERMAL POWER above the limit of Required Action A.1 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 to restore QPTR to within limit.
AND Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
QPTR 3.2.4 ACTIONS CALLAWAY PLANT 3.2-12 Amendment 133 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, SR 3.2.1A.2 and SR 3.2.2A.1.
OR Perform SR 3.2.1B.1, SR 3.2.1B.2 and 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 /> after achieving equilibrium conditions not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing THERMAL POWER above the limit of Required Action A.1 B.
Required Action and associated Completion Time not met.
B.1 Reduce THERMAL POWER to 50% RTP 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CONDITION REQUIRED ACTION COMPLETION TIME
QPTR 3.2.4 CALLAWAY PLANT 3.2-13 Amendment No. 202 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 measurement information.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 4.0-1 Amendment 133 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 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) zircaloy, ZIRLOTM or M5
Reporting Requirements 5.6 5.6 Reporting Requirements CALLAWAY PLANT 5.0-24 Amendment No. 215 l 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.
Control Bank Insertion Limits for Specification 3.1.6, 4.
Axial Flux Difference Limits for Specification 3.2.3, 5.
Heat Flux Hot Channel Factor, FQ(Z), FQ RTP, K(Z), W(Z) and FQ Penalty Factors for Specification 3.2.1, 6.
Nuclear Enthalpy Rise Hot Channel Factor
, 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, and 3.1.8, 8.
Reactor Core Safety Limits Figure for Specification 2.1.1, 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.
F N H
(continued) s 3.2.3A and 3.2.3B, 3.2.1A, and FCQ(z),
FVQ(z), Measurement Uncertainty, Manufacturing Tolerance, and V(z) for Specification 3.2.1B 3.2.2A, and measured FNH, F
NH uncertainty, UH for Specification 3.2.2B
Reporting Requirements 5.6 5.6 Reporting Requirements CALLAWAY PLANT 5.0-25 Amendment No. 217 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.
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)
INSERT H
Reporting Requirements 5.6 5.6 Reporting Requirements CALLAWAY PLANT 5.0-26 Amendment No. 217 l 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)
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.
- 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.