ML24191A288

Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Operating License Amendment Index

ML24191A288
Person / Time
Site:	Callaway
Issue date:	05/06/2024
From:	Ameren Missouri, Union Electric Co
To:	Office of Nuclear Reactor Regulation
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References
ULNRC-06877
Download: ML24191A288 (1)

Text

April 2024 Revision 173 1

A140.0001 OPERATING LICENSE AMENDMENT INDEX O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT 1

1004 Table 3.3-1 Provision to allow for blockage of both source range flux doubling switchover signals to perform reactor startup.

2 1005 Table 4.11-1 Addition of two Batch Waste Release Tanks 3

1007 Figure 6.2-2 Section 6.5.1.2 Addition of two managerial positions to the plant organization.

Addition of another ORC member.

4 1004 Table 3.3-1 Provision to allow for appropriate compensatory actions when two source range monitor channels are out of service.

5 1013 License Condition 2.C.(3)(a)

Provided a Nov. 30, 1985, deadline for the environmental qualification of electrical equipment important to safety.

6 1014 Section 4.6.1.6.1 Delay of six months in the due dates of the first three tendon surveillances.

7 1006 Figure 6.2-1 Figure 6.2-2 Revision to the offsite and unit organizational charts.

8 1023 Table 4.3-1 Table 4.3-2 Section 4.5.2 Section 4.6.2.1 Section 4.6.3.2 Section 4.7.3 Section 4.7.4 Section 4.8.1.1.2 Section 4.8.2.1 Extends initial 18 month surveillance interval for various tests until prior to startup following the first refueling outage or June 1, 1986, whichever comes first.

April 2024 Revision 173 2

A140.0001 9

1021 Section 3/4.8.4.1 Bases 3/4.8.4 Deletes the requirement for resistance testing of certain fuses. Deletes the list of containment penetration conductor overcurrent protective devices.

Deletes Table 3.8-1.

10 1017 Figures 6.2-2 Revise organizational chart - title change from Supervisor, Radwaste, to Superintendent, Radwaste.

11 1018 Section 4.7.10.1.2 Allows the 18-month inspection of a fire pump diesel engine to be performed when the plant is at power, as well as when shutdown.

12 1028 Figure 3.9-1 Section 5.3.1 Section 5.6.1.1 Increases the permitted enrichment of fuel to be stored in spent fuel pool.

Permits the storage of OFA in pool.

Revises nominal center-to-center distance between fuel assemblies in storage racks.

13 1029 Section 3/4.6.1 Containment leak rate testing to be performed at the calculated peak containment internal pressure.

14 1035 Figure 6.2-1 Figure 6.2-2 Section 6.5.1.2 Organization changes - QA nuclear associated with new corporate Quality Systems Department.

15 1036 1.0 Definitions Figure 2.1-1 Table 2.2-1 Bases 2.1 Bases 2.2 Section 3.1.3.4 Figure 3.1-1 Section 3/4.2.3 Section 3/4.2.4 Section 3/4.2.5 Section 4.10.2.2 Bases 3/4.2 Bases 3/4.4 Transition from low-parasitic fuel assembly fueled core to optimized fuel assembly fuel core.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 3

A140.0001 16 1043 Figure 6.2-1 Figure 6.2-2 Section 6.5.1.2 Section 6.5.2 Section 6.5.3.1 Organizational changes - established positions of General Manager, Nuclear Operations, and Manager, Operations Support.

17 1027 Table 3.3-1 Table 4.3-1 Bases 3/4.3 Modified the surveillance interval for analog channel operational tests and the allowable out-of-service time of reactor trip system instrumentation.

18 1030 Table 3.3-5 Table 3.6-1 Section 3/4.7.1.6 Bases 3/4.7.1.6 Modify response times pertaining to the MSIV and the main FW isolation valves by removing the valve closure time to a separate specification.

19 1041 Table 3.3-1 Table 4.3-1 Require 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> restoration in the event of loss of one of the diverse reactor trip features (undervoltage or shunt trip attachment).

20 1050 Table 3.3-6 Table 3.3-13 Bases 3/4.9 Deletes the trip functions of the containment atmosphere radiation monitors associated with containment purge isolation and control room ventilation.

21 1025 Section 3/4.8.1.1 Bases 3/4.8 Increase overall emergency D/G reliability and prevent undue stress and wear on the D/G engines.

22 1081 Table 3.3-5 Bases 3/4.3 Increases ESF response time by 15 seconds for: Containment Pressure-High1, SI; Pressurizer Pressure-Low, SI; Steam Line Pressure-Low, SI.

23 1055 Figure 3.9-1 Section 5.3.1 Section 5.6.1.1 Curves for Westinghouse optimized fuel (OFA) and standard fuel (SFA).

States a maximum enrichment of 4.25 weight percent U-235 for fuel storage.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 4

A140.0001 24 1059 Section 5.3.1 Allows for limited replacement of fuel rods with filler rods or vacancies if supported by a cycle-specific reload analysis.

25 1053 Section 3.7.5 Regards ultimate heat sink - two separate trains of cooling is available for the essential service water system.

26 1048 Table 3.3-3 Regards blocking of aux. feedwater start signals during normal plant shutdowns and startups.

27 1051 Section 6.9.1.5 Section 6.9.1.6 Section 3.4.8 Bases 3/4.4.8 Revises requirements for reporting iodine spiking. Eliminates the requirement to shut down the plant after 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> of operation with a dose equivalent I-131 value of 1 micro curie/gram or greater.

28 1057 1.0 Definitions Figure 2.1-1 Table 2.2-1 Bases 2.1 Bases 2.2.1 Section 3.1.3.4 Section 3/4.2 Table 3.2-1 Table 4.3-1 Section 3.5.1 Bases 3/4.2 Section 6.9.1.9 Section 6.10.1 Transition from low-parasitic fuel assembly and optimized fuel assembly fuel core to Vantage 5 (V-5) fuel assembly fueled core.

29 1063 Section 3/4.1.3.5 Figure 3.1-1 Bases 3/4.1.3 Revises definition of the fully withdrawn shutdown and control rod position from 228 steps to 225 steps or higher.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 5

A140.0001 30 1054 Section 3/4.3.3.7 Section 3/4.7.10 Section 3/4.7.11 Bases 3/4.3.3.7 Bases 3/4.7.10 Bases 3/4.7.11 Section 6.5.1.6 Section 6.5.1.7 Section 6.8.1 Remove fire protection T/S and place them in plant procedures and in the FSAR.

31 1065 Table 4.3-3 Section 4.11.2.5 Corrects administrative oversight that references the wrong specification for Table 3.1-13.

32 1071 Table 6.2-1 Table 6.2-2 Section 6.5.1.2 Reflects nuclear function organizational changes.

33 1034 Table 3.6-1 Increases the maximum isolation time for the containment mini-purge isolation valves.

34 1067 Table 4.3-1 Addition of functional testing requirements for the reactor trip bypass breakers.

35 1058 1.0 Definitions Figure 2.1-1 Table 2.2-1 Increase in the authorized core thermal power.

36 1064 Figure 3.4-2 Figure 3.4-3 Table 4.4-5 Figure 3.4-4 Bases 3/4.4.9 Revises the plant heatup and cooldown curves, revises the maximum allowable PORV setpoint curve, and revises the reactor vessel surveillance capsule removal schedule.

37 1066 Section 6.2 Deletes the offsite and unit organizational charts. Adds the aspects of the organizational structure which were previously defined by the organizational charts.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 6

A140.0001 38 NA License Condition 2.E Requires compliance with the amended Physical Security Plan which conforms to the requirements of 10CFR73.55.

39 1075 Section 6.1.2 Section 6.2.1 Section 6.5.1.6 Section 6.5.1.7 Section 6.5.1.8 Section 6.5.2.1 Section 6.5.2.2 Section 6.5.2.9 Section 6.5.2.10 Section 6.6.1 Section 6.7.1 Changes the T/S to reflect recent organizational changes. All references regarding the "Vice President, Nuclear" are changed to the "Senior Vice President, Nuclear". The position of General Manager, Engineering (Nuclear) has been deleted from the Nuclear Safety Review Board (NSRB) and the Manager, Licensing and Fuels, has been appointed Chairman of the NSRB.

40 1073 Section 3/4.5.1 Bases 3/4.5.1 Allows the plant to remain in Hot Standby with RCS pressure less than or equal to 1000 psig with one accumulator inoperable, and to allow closing one accumulator isolation valve for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform leakage testing of system check valves.

41 1082 Section 5.3.2 Revises "Control Rod Assemblies" to allow the use of hafnium and/or silver-indium-cadmium as the absorber material in the rod cluster control assemblies.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 7

A140.0001 42 1081 Section 4.4.9.3 Section 4.5.2 Section 3.5.4 Section 4.9.8.1 Section 3/4.9.8.2 Bases 3/4.4.9 Bases 3/4.5.2 Bases 3/4.5.3 Bases 3/4.5.4 Bases 3/4.5.5 Bases 3/4.9.8 Reduces the required RHR system flowrate during Mode 6 operation, deletes the RHR autoclosure interlock (ACI) function, and allows the safety injection pumps to be energized with the head on and with water level not above the top of the reactor vessel flange, in Modes 5 and 6.

43 1074 Table 2.2-1 Table 3.3-1 Table 3.3-2 Table 4.3-1 Table 3.3-3 Table 3.3-4 Table 3.3-5 Table 4.3-2 Bases 2.0 Revises the provisions in the T/S relating to the steam generator low-low level trip circuitry by adding an Environmental Allowance Modifier (AM) and a Trip Time Delay (TTD).

44 1079 Bases 2.1.1 Section 3.1.1.3 Section 3.1.2.5 Section 3.1.2.6 Section 3.2.1 Section 4.2.1.4 Section 3.2.2 Figure 3.2-2 Section 4.2.2.2 Section 4.2.2.3 Section 4.2.2.4 Section 3.2.3 Section 3.5.1 Section 3.5.5 Section 3.6.2.2 Bases 3/4.1.2 Bases 3/4.2.1 Bases 3/4.2.2 Bases 3/4.2.3 Bases 3/4.5.5 Revises the T/S to support a core reload for Cycle 4. The revised T/S includes increased peaking factors, a positive moderator temperature coefficient, increased refueling water storage tank and accumulator boron concentrations, and increased spray additive tank sodium hydroxide concentration.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 8

A140.0001 45 1039 Section 4.3.3.5.3 Section 3/4.7.1.7 Bases 3/4.7.1.7 Incorporates new T/S LCO and surveillance requirements for the steam generator Atmospheric Steam Dumps (ASDs) into the Callaway License in order to assume the availability of mitigating equipment assumed in the steam generator tube rupture analysis.

46 1024 Section 3/4.6.1.6 Provides clarification and relaxation of some of the existing Surveillance Requirements, adds provisions vital for monitoring the integrity or prestressed concrete containments, and modifies some of the reporting requirements and action statements found within the LCO.

47 1060 Section 3/4.7.6 Increases the allowed flow variations of the control room emergency ventilation system and reduces the control room pressurization requirement from 1/4 inch water gauge to 1/8 inch water gauge.

48 1069 Figure 5.1-1 Figure 5.1-2 Figure 5.1-3 Figure 5.1-4 Revises the referenced figures regarding the exclusion area, low population zone, site boundary for gaseous effluents, and site boundary for liquid effluents.

49 1078 Section 3/4.3.3 Revises Radiation Monitoring for Plant Operation, by increasing the permitted period of inoperability for one channel of the control room air intake monitors and fuel building atmosphere monitors from 1 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 9

A140.0001 50 1087 Section1.0 Section 3/4.3.10 Section 3/4.3.11 Section 3/4.3.12 Bases 3/4.3.10 Bases 3/4.3.11 Bases 3/4.3.12 Section 6.8 Section 6.9 Section 6.10 Section 6.11 Section 6.12 Section 6.13 Section 6.14 Relocates the existing procedural details of the current Radiological Effluent Technical Specifications (RETS) to the Offsite Dose Calculation Manual (ODCM), and procedural details for the solid radioactive wastes to the Process Control Program (PCP).

The amendment also incorporates the respective programmatic controls into the Administrative Controls section of the Technical Specifications.

51 1085 Section 3/4.1.3 Bases 3/4.1.3 Allows continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for diagnosis and repair, with one or more control rod assemblies inoperable due to a rod control urgent failure alarm or other electrical problem in the rod control system provided all affected control rods remain trippable.

52 1090 Section 4.0.2 Bases 4.0.2 Removes the 3.25 limit for surveillances as provided in Generic Letter 89-14 dated August 21, 1989.

53 1088 Section 3/4.7.1.2 Adds clarification to Surveillance Requirements 4.7.1.2.1.a(4) and 4.7.1.2.1.b(1) by identifying automatic valves that are either excluded or included in the flowpath of the Auxiliary Feedwater System whose position has to be verified to demonstrate operability.

54 1093 Section 5.3.1 Section 5.6.1.1 Revises T/S Sections 5.3.1 and 5.6.1.1 to allow fuel with a maximum initial enrichment of 4.45 weight percent to be stored in Region 1 of the Callaway Plant spent fuel pool.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 10 A140.0001 55 1095 Section 3.7.1.2 Modifies the Limiting Condition of Operation to address flowpath requirements of the motor-driven and steam turbine-driven auxiliary feedwater pumps. Additionally, it provides further requirements to the ACTION Statements if any of the Essential Service Water (ESW) system valves to the steam turbine-driven auxiliary feedwater pumps are inoperable or if one ESW loop is inoperable.

56 1096 Table 2.2-1 Table 3.3-1 Table 3.3-2 Table 4.3-1 Bases 2.2.1 Revises T/S by deleting the power range, neutron flux, high negative rate trip.

57 1099 Table 2.2-1 Table 3.3-4 Table 4.3-1 Revises T/S and associated bases to accommodate the replacement of the current Resistance Temperature Detector (RTD) bypass system with an RTD/thermowell system mounted directly into the hot and cold legs of the reactor coolant system.

58 1091 Section 1.0 Section 3/4.1.1.3 Section 3/4.1.3.5 Section 3/4.1.3.6 Section 3/4.2.1 Section 3/4.2.2 Section 3/4.2.3 Bases 3/4.1.1.3 Bases 3/4.2.1 Bases 3/4.2.2 Bases 3/4.2.3 Section 6.9.1.9 Relocates cycle-specific core parameters from the T/S and places them in the Core Operating Limits Report (COLR).

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 11 A140.0001 59 1105 Section 3/4.7.1.7 Revises T/S to allow an exception to T/S 4.0.4 thus allowing sufficient plant conditions (Mode 3) to be established and completion of the required surveillance prior to applying the T/S 3/4.7.1.7 Action Statement on atmospheric steam dump valve (ASD) operability.

60 1072 Section 6.3 Section 6.4 Revised T/S by deleting references superseded by the May 26, 1987 revision to 10CFR55.

61 1102 Section 3/4.1.3.2 Bases 3/4.1.3.2 Revises T/S to add an action statement covering situations where more than one digital rod position indicator per bank is inoperable.

62 1089 Section 3/4.6.1.1 Revises T/S to clarify which containment penetration methods are acceptable.

63 1101 Section 6.5.1.2 Revises T/S to delete the specific title designations of seven of the eight members of the On-Site Review Committee (ORC).

64 1106 Table 3.3-1 Table 4.3-1 Table 3.3-3 Table 4.3-2 Bases 3/4.3.1 Bases 3/4.3.2 The amendment extends the allowable out-of-service times (AOTs) and the surveillance test intervals for the analog channels of the Engineered Safety Features Actuation System (ESFAS). These revisions also include extended AOTs for the ESFAS actuation logic and actuation relays of the solid state protection system.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 12 A140.0001 65 1123 Bases 3/4.8.1 Bases 3/4.8.2 Bases 3/4.8.3 Section 4.8.1.1.2.f.(2)

Revises Surveillance 4.8.1.1.2.f.(2) concerning diesel generator load reject testing by removing the reference to a numerical value for the largest single emergency load. This change will allow the current surveillance test to conform with the literal requirements of Technical Specifications.

66 1107 Table 3-4.1 Bases 3/4.4.6.2 Section 3/4.6.2.f Revises Technical Specification 3/4.4.6 and associated Bases to change the allowed leakage limit for reactor coolant system pressure isolation valves.

67 1111 Section 3/4.7.8 Table 4.7-2 Bases 3/4.7.8 Revises T/S 3/4.7.8, "Snubbers", and associated Bases by changing the snubber visual inspection intervals and corrective actions. The proposed changes are consistent with the guidance of Generic Letter 90-09 dated 12/11/90.

68 1109 Section 3/4.5.2.h Operating License Amendment 68 revises T/S 4.5.2.h to reflect new surveillance requirements for maximum and minimum Emergency Core Cooling System (ECCS) subsystem flow rates. In addition, the surveillance requirements for performing flow balance tests on specific ECCS subsystems are clarified. These changes will ensure that the performance of these ECCS subsystems is demonstrated to be consistent with the current plant safety analyses.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 13 A140.0001 69 1122 Section 3/4.3.2 Section 3/4.7.6 Amendment 69 revises T/S 3/4.3.2 and 3/4.7.6 to take exception to T/S 3.0.4 which prevents entry into an operational mode unless the conditions for the Limiting Condition for Operation are met. The revision allows operational mode changes in MODES 5 and 6 while certain control room ventilation T/S action statements are in effect.

70 1117 Section 3/4.7.12 Table 3.7-4 Bases 3/4.7.12 Amendment 70 revises T/S 3/4.7.12, Table 3.7-4 and associated Bases, "Area Temperature Monitoring", to increase the maximum temperature limit from 101°F to 106°F for the Electrical Penetration Rooms. The proposed change is consistent with the intent of the T/S because the absolute maximum temperature limit for the Electrical Penetration Rooms is maintained at 131°F.

71 1121 Table 6.2-1 Amendment 71 revises T/S Table 6.2-1 to permit an individual with a valid Senior Reactor Operator ("SRO")

license and who is qualified as a Shift Technical Advisor ("STA") to assume the Control Room command function during an absence of the Shift Supervisor ("SS") from the Control Room.

72 1120 Section 3/4.2.1 Section 4.2.2.2 Section 4.2.2.3 Section 4.2.2.4 Section 6.9.1.9 Table 2.2.1 Bases 3/4.2.1 Amendment 72 revises T/S in order to implement relaxed axial offset control (RAOC) for Cycle 6 at Callaway. The RAOC methodology supporting this proposed change is consistent with WCAP-10216-PA which has been previously reviewed and approved by the NRC.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 14 A140.0001 73 1134 Section 4.3.1.1 Table 4.3-1 Amendment 73 grants a one-time only extension to the surveillance interval specified for Technical Specification (TS) Surveillance 4.3.1.1, Table 4.3-1, Functional Unit 1 (Manual Trip) by adding a footnote to Note 16 which states that "complete verification of OPERABILITY of the manual reactor trip switch circuitry shall be performed prior to startup from the first shutdown to Mode 3 occurring after August 7, 1992." This amendment was required due to the discovery that the existing surveillance procedure does not adequately verify the operability of the shunt trip contacts associated with the manual reactor trip function.

74 1119 Table 3.3-4 Amendment 74 revises Technical Specification Table 3.3-4, "Engineered Safety Features Actuation System Instrumentation Trip Setpoint,"

Functional Unit 8.b, to revise the trip setpoint, the allowable value, total allowance, sensor error, and "Z" value for the "4 kV Undervoltage-Grid Degraded Voltage" protection function to agree with the required design values.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 15 A140.0001 75 1089 Section 3.6.1.2 Section 4.6.1.2.b Bases 3/4.6.1.2 Amendment 75 revises the ACTION statement in T/S 3.6.1.2 and the surveillance criteria in T/S 4.6.1.2.b and associated bases to establish two conditions for determining the acceptability of the periodic Type A tests conducted pursuant to Appendix J to 10CFR50. These conditions are the "as found" and the "as left" conditions; each has separate acceptance criteria. The amendment also revises T/S 4.6.1.2a to eliminate the requirement to conduct the third test of each set of three Type A tests during the shutdown for the 10 year plant inservice inspection.

76 1118 Section 4.4.9.1.2 Figures 3.4-2 Figures 3.4-3 Figures 3.4-5 Tables 4.4-5 Tables B 3/4.4-1 Bases 3/4.4.9 Amendment 76 revises Technical Specification Section 4.4.9.1.2, Figures 3.4-2, 3.4-3, and 3.4-4, Tables 4.4-5 and B 3/4.4-1 and associated Bases for Reactor Coolant System Pressure/Temperature Limits by modifying plant heatup and cooldown curves and the maximum allowable PORV setpoint curve for cold overpressure protection.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 16 A140.0001 77 1129 Section 4.6.1.2.a Bases 3/4.6.1.2 Amendment 77 changes the Technical Specifications by extending the surveillance requirements of Technical Specification 4.6.1.2.a and its associated Bases to allow the third Type A Containment Leakage Rate Tests within the first 10-year service period to be conducted during the Cycle 7 refueling outage. This Technical Specification change is a one-time extension of the current maximum interval from 50 months to 53 months and is consistent with a one-time exemption from Appendix J to 10 CFR Part 50, being issued concurrently under separate cover, which extends the first 10-year service period by approximately three months.

78 1068 Section 4.0.3 Section 4.0.4 Bases 4.0.3 Bases 4.0.4 Amendment 78 changes the Technical Specifications 4.0.3, 4.0.4 and their associated bases to incorporate changes as recommended in Generic Letter 87-09, "SECTIONS 3.0 AND 4.0 OF THE STANDARD TECHNICAL SPECIFICATIONS (STS) ON THE APPLICABILITY OF LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS,"

dated June 4, 1990.

79 1139 Section 4.7.8.d Amendment 79 revises Technical Specification Surveillance Requirement 4.7.8.d to allow a one-time schedule extension of the snubber transient event inspection.

O.L.

AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 17 A140.0001 80 1137 Section 4.8.1.1.2.h(2)

Amendment 80 deletes the surveillance requirement of Technical Specification 4.8.1.1.2.h(2), which involves performing a pressure test of portions of the diesel fuel oil system.

Alternate testing for the tanks and piping would include leak testing at hydrostatic head pressure with the tanks filled to design capacity and would be governed by Technical Specification 4.0.5.

81 1128 Section 3.9.7 Bases 3/4.9.7 Amendment 81 revises Technical Specification 3.9.7 and associated Bases to allow the spent fuel pool transfer gates to travel over fuel assemblies in the spent fuel pool for refueling activities, fuel handling system maintenance, and transfer gate seal replacement.

82 1132 Section 3/4.9.12, Figure 3.9-1 Amendment 82 revises Technical Specification 3/4.9.12, Figure 3.9-1 to reflect a maximum initial enrichment of 4.45 w/o U-235 for fuel storage in Region 2 of the Callaway spent fuel pool.

83 1108 Section 3/4.4.4 Section 3.4.9.3 Bases 3/4.4.4 Amendment 83 revises Technical Specifications 3/4.4.4 and its associated bases and 3/4.4.9.3 to address changes as recommended in Generic Letter 90-06, "RESOLUTION OF GENERIC ISSUE 70, 'POWER-OPERATED RELIEF VALVE AND BLOCK VALVE RELIABILITY,' AND GENERIC ISSUE 94, 'ADDITIONAL LOW-TEMPERATURE OVERPRESSURE PROTECTION FOR LIGHT-WATER REACTORS,'

PURSUANT TO 10 CFR 50.54(f)"

dated June 25, 1990.

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AMENDMENT NO.

O.L.

CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 18 A140.0001 84 1141 Tables 2.2-1 Tables 4.3-1 Bases 3/4.2.2 Bases 3/4.2.3 Amendment 84 revises Technical Specification Tables 2.2-1 and 4.3-1 and associated Bases 3/4.2.2 and 3/4.2.3 by changing the axial flux difference (AFD) penalty function f1 (delta - I) defined in Note 1 of Table 2.2-1 for the Overtemperature Delta-T reactor trip.

85 1130 Section 3.3.2 Section 3/4.8.1 Amendment 85 revises Technical Specification 3.3.2 and 3/4.8.1 to add Mode 5 and 6 applicability for OPERABILITY of the load sequencer and supplying 4 KV Bus undervoltage circuits.

86 1104 Table 3.3-4 Table 3.3-10 Section 3.3.3.6 Section 3.6.4.1 Section 3.11.2.5 Section 6.2.2 Amendment 86 revises various Technical Specifications to reflect editorial and typographical changes for consistency and clarity. The changes include trip setpoint corrections, description clarifications, reference updates, and title deletions.

87 1124 Table 4.3-1 Amendment 87 revises Technical Specification Table 4.3-1, Note 5, to reflect that integral bias curves, rather than detector plateau curves, are used to calibrate the source range instrumentation. Intermediate Range and Power Range channels will continue to be calibrated using detector plateau curves.

88 1125 Section 6.5 Amendment 88 revises Section 6 of the Technical Specifications to reflect an organizational change to the administrative controls. The change involves the title change of the General Manager, Nuclear Operations to Vice President, Nuclear Operations.

O.L.

AMENDMENT NO.

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CHANGE NOTICE NO.

APPLICABLE TECHNICAL SPECIFICATION CONTENT

April 2024 Revision 173 19 A140.0001 89 1143 Section 1.18 Section 3.11.1.4 Section 3.11.2.6 Section 6.9.1.7 Section 6.14 Amendment 89 changes the submittal frequency for the Radioactive Effluent Release Report from semi-annually to annually. This change also makes the report date for Radioactive Effluent Release Report consistent with the reporting requirements for the Annual Radiological Environmental Operating Report.

90 1126 N/A Amendment 90 deletes Sections 2.3 and 4.3, Cultural Resources, of Appendix B, Environmental Protection Plan.

91 1150 Section 3/4.5.1 Bases 3/4.5.1 Amendment 91 (tracked as O.L. 1150) revises Technical Specification 3/4.5.1 and associated Bases Section 3/4.5.1.

A new Action Statement a. provides a 72-hour allowed outage time (AOT) for one accumulator inoperable due to boron concentration. The Action Statement b. AOT was changed to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements 4.5.1.1.a.1 and 4.5.1.1.b were revised and 4.5.1.2 was deleted from the T/S.

92 1136 Section 6.3.1.2 Amendment 92 (tracked as O.L.

1. 1136) changes Technical Specification 6.3.1.2 to allow either the Health Physics Superintendent or the Health Physics, Operations Supervisor to be designated as Radiation Protection Manager (RPM).

93 1146 Table 2.2-1 Bases 2.2.1 Amendment 93 (tracked as O.L.

1. 1146), "Undervoltage-Reactor Coolant Pumps," revised to correct total allowance (undervoltage relay span) and allowable value (voltage) expressions.

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April 2024 Revision 173 20 A140.0001 Revision by NRC letter of 10/28/94 NA Bases 2.2.1 This letter of 10/28/94 (see ULNRC-02672) addresses OT Delta-T, OP Delta-T, and Delta-T calibrations at the beginning of each cycle during startup testing. The revisions reflected that, for the startup of a refueled core, until measured at 100% RTP, Delta To is initially assumed at a value, which is conservatively lower than the last measured 100% RTP Delta To for each loop.

94 1127 Table 3.3-1 Table 4.3-1 Bases B 2-8 Bases B 3/4 4-1 Amendment 94 (tracked as O.L.

1. 1127) revises Technical Specification Table 3.3-1 and 4.3-1, and Bases pages B 2-8 and B 3/4 4-1. The changes reflect the re-analysis of the boron dilution transient for shutdown modes to address non-conservatisms in the previous event analysis.

95 1163 Section 4.8.1.1.2f.7 Amendment 95 (tracked as O.L.

1. 1163) revises Technical Specification (TS) Surveillance Requirement 4.8.1.1.2f.7. The change removes the requirement to perform the hot restart test within 5 minutes of completing the 24-hour endurance test and places that requirement in a separate TS.

96 1152 Section 3/4.6.2.2 This amendment replaces Technical Specification (TS) 3/4.6.2.2, Spray Additive System, with a new TS 3/4.6.2.2 entitled Recirculation Fluid pH control (RFPC) System.

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April 2024 Revision 173 21 A140.0001 97 1159 Bases 3/4.9 The amendment revises Bases 3/4.9, Refueling Operations and FSAR Sections 9.1.3. Fuel Pool Cooling and Cleanup, 9.1.4 Fuel Handling System and 15.4.6 Chemical and Volume Control System Malfunction that result in a Decrease in the Boron Concentration in the Reactor Coolant.

The changes document the results of a safety evaluation that considers the effects using reactor water makeup to spray down the refueling pool during pool drain evolutions. The changes establish procedural controls to address the possibility of a different type of boron dilution event than previously considered.

98 1164 Section 4.6.1.2.a Bases 3/4.6.1.2 This amendment revises T/S Surveillance Requirement 4.6.1.2.a and its associated Bases. The change defers the requirement to perform the Type A Containment Integrated Leak Rate Test until Refuel 8 (October 1996), in conjunction with the exemption to 10 CFR Part 50, Appendix J.

99 1158 Section 3/4.8.2.1 Section 3/4.8.2.2 Section 3/4.8.3.1 Section 3/4.8.3.2 This amendment revises T/S 3/4.8.2.1, 3/4.8.2.2, 3/4.8.3.1, and 3/4.8.3.2.

The changes address the 125-volt DC busses, adds provisions for swing battery chargers, and removes provisions for the 4160-volt and 480-volt AC emergency busses.

100 1110 Section 3/4.8.1.1 Section 3/4.8.1.2 This amendment revises T/S 3/4.8.1.1 and 3/4.8.1.2 to address the minimum required storage volumes of the Emergency Fuel Oil storage and day tanks.

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April 2024 Revision 173 22 A140.0001 101 1154 Section 4.2.2.2 Section 4.2.2.4 Section 6.9.19 Revises T/S 4.2.2.2, 4.2.2.4, and 6.9.19. The changes incorporate a penalty in the Core Operating Limits Report (COLR) to account for heat flux (FQ) increases greater than 2 percent between measurements.

102 1167 Section 2.2.1 Table 2.2-1 Amendment 102 (tracked as OL 1167) revises Technical Specification 2.2.1, Table 2.2-1. The changes address reducing repeated alarms and partial reactor trips by revising the Overpower Delta-T (OPT) setpoint function.

103 1151 Various. Refer to ULNRCs 3023 and 3184.

This amendment revises T/S to implement the NRCs Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors.

104 1165 Section 3.3.1 Table 3.3-2 Table 3.3-5 Amendment 105 revises T/S 3.3.1 and T/S 3.3.2 to relocate T/S Tables 3.3-2 and 3.3-5 to FSAR Table 16.3-1 and FSAR Table 16.3-2 per FSAR CN 95-07, which provide the response time limits for the reactor trip system (RTS) and the engineered safety features actuation system (ESFAS) instruments. The amendment also relocates the Bases discussion for T/S 3.3.1. and T/S 3.3.2 to Section 16.3 of the updated FSAR.

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April 2024 Revision 173 23 A140.0001 105 1169 Section 4.1.1.1.1 Section 4.1.1.2 Section 4.1.3.1.2 Section 4.4.6.2.2.b Section 4.4.3.2 Section 4.6.2.1.d Section 4.6.4.2 Table 4.3-3 Bases 3/4.1.3 This amendment revises T/S 4.1.3.1.2, 4.4.6.2.2.b, 4.4.3.2, 4.6.2.1.d, 4.6.4.2, and Table 4.3-3 to implement the recommendations of NRC Generic Letter 93-05, Line Item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operations.

Additionally, the amendment revises T/S 4.1.1.1.1, 4.1.1.2, 3/4.1.3.1 and the associated Bases to implement portions of NUREG-1431,Standard Technical Specifications -

Westinghouse Plants.

106 1168 Section 3/4.7.6 Amendment 106 revises T/S 3/4.7.6 to reduce the upper limit on the flow rate through the control room filtration subsystem and adopts ASTM D-3803-1989 as the laboratory testing standard for control room filtration and control building pressurization charcoal adsorber. The amendment also revises the Bases for T/S 3/4.7.6 to reflect the changes.

107 1156 Section 6.2.3 Section 6.5.1 Section 6.5.2 Section 6.5.3 The amendment revises T/S 6.5.1, 6.5.2, and 6.5.3 to relocate the review and audit requirements of the On-Site Review Committee (ORC) and the Nuclear Safety Review Board (NSRB) to the Operational Quality Assurance Manual (OQAM). In addition, the amendment deletes reference to the Manager, Nuclear Safety and Emergency Preparedness, in T/S 6.2.3.

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April 2024 Revision 173 24 A140.0001 Revision by NRC letter dated 2/1/

96 NA Bases2.1.1 Section 3/4.3.3.6 Section 3/4.6.1.4 Section 3/4.1.1.3 Section 3/4.9.4 Bases 2.1.1, Safety Limits Reactor Core, Bases 3/4.3.3.6, Accident Monitoring Instrumentation, Bases 3/

4.6.1.4, Internal Pressure (all tracked by O.L. 1116); Bases 3/4.1.1.3, Moderator Temperature Coefficient (tracked by O.L. 1140); and Bases 3/

4.9.4, Containment Building Penetrations (tracked by O.L. 1148).

108 1162 Section 4.3.2.2 Section 4.6.1.2.1 Bases 3/4.7.1.2 Amendment 108 (tracked as OL 1162) revises TS 4.3.2.2, TS 4.7.1.2.1, and the Bases for TS 3/4.7.1.2 to decrease the frequency of auxiliary feedwater pump testing, remove inconsistencies in testing requirements for the turbine-driven auxiliary feedwater pump, and clarify performance parameters in the TS Bases.

109 1171 Section 5.3.1 Section 5.6.1.1 Figure 3.9-1 Amendment 109 (tracked as OL 1171) revises TS 5.3.1 to reflect a change in the maximum initial enrichment for reload fuel, subject to the integral fuel burnable absorber (IBFA) requirements, and a change in the maximum fuel enrichment not requiring IFBAs. The amendment also changes the maximum reference k in TS 5.6.1.1 for fuel storage in Region 1 of the spent fuel pool and revises TS Figure 3.9-1 to reflect a change to the maximum initial enrichment for fuel stored in Region 2 of the spent fuel pool.

110 1175 Section 5.3.1 Amendment 110 (tracked as OL 1175) revises TS 5.3.1 to allow the use of ZIRLO clad fuel rods and ZIRLO filler rods.

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April 2024 Revision 173 25 A140.0001 111 1172 Section 1.7 Section 4.6.1.1 Section 3.6.1.3 Section 4.6.1.3 Section 6.8.4 Bases 3/4.6.1.1 Amendment 111 (tracked as OL 1172) revises T/S 1.7, 4.6.1.1, 3.6.1.3, 4.6.1.3, 6.8.4 and the associated Bases section to directly reference Regulatory Guide 1.163 as required by 10 CFR 50, Appendix J, Option B for the Type A containment integrated leak rate tests and the Type B and C local leak rate tests.

112 1170 Section 3/4.8.1 Bases 3/4.8 Amendment 112 revises T/S 3/4.8.1 and its associated Bases to improve overall emergency diesel generator reliability and availability.

113 1153 Section 1.7 Section 3/4.6.1 Section 3/4.6.3 Bases 3/4.6.2.3 Amendment 113 revises the allowed outage times for component cooling water motor operated containment isolation valves, removes the list of containment isolation valves from T/S, and allows containment penetration check valves to be used as isolation devices.

114 1173 Section 3/4.9.4 Bases 3/4.9.1 Amendment 114 (O.L. 1173) revises T/

S 3.9.4 and its associated Bases to allow the containment personnel airlock doors to be open during core alterations and movement of irradiated fuel in containment.

115 1181 FSAR 7.1.2.5.2 FSAR 10.4.7 FSAR 10.4.7.2.2 FSAR Fig. 7.2-1 (513

& 514)

Modification to reduce the single failure trip potential for the main feedwater control and bypass valves.

116 1178 Section 3/4.4 Amendment 116 (O.L. 1178) revises T/S 3/4.4.5 and its associated Bases to address the installation of laser welded tube sleeves in the steam generators.

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April 2024 Revision 173 26 A140.0001 117 1176 Section 3/4.3 Amendment 117 (O.L. 1176) revises T/S 3/4.3 to support a modification to replace existing analog portions of the main steam and feedwater isolation system (MSFIS) with digital processor equipment and would authorize revision of the FSAR to include a description of the MSFIS mod.

118 1182 Section 3/4.7.7 Section 3/4.9.13 Bases 3/4.7.7 Bases 3/4.9.13 Amendment 118 (O.L. 1182) revises the surveillance requirements of Technical Specifications 3/4.7.7, 3/

4.9.13 and the corresponding Bases.

The changes implement an updated charcoal test methodology for the emergency exhaust system.

119 1187 Table 3.3-3 Amendment 119 revises T/S Table 3.3-3 to correct administrative errors associated with the start logic of the turbine driven auxiliary feedwater pump.

120 1179 Operating License 1.A Amendment 120 (O.L. 1179) revises Page 1 of the Operating License to incorporate Union Electrics merger with CIPS and the formation of Ameren Corporation.

121 1185 Section 3/4.7.4 Amendment 121 (O.L. 1185) revises T/S 3/4.7.4 to remove the during shutdown requirement for the ESW surveillances.

122 1188 Section 6.1 Section 6.2 Section 6.6 Section 6.7 Amendment 122 revises the title Senior Vice President, Nuclear to Vice President and Chief Nuclear Officer due to the elimination of the Vice President, Nuclear Operations position.

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April 2024 Revision 173 27 A140.0001 123 1184 Table 3.3-3 Table 4.3-2 Correct the # of MSFIS channels listed in Table 3.3-3 for items 4.b.2 and 5.a.2 to be consistent with SSPS requirments and change Table 4.3-2 surveillance requirements for items 4.b.2 and 5.a.2 from a quarterly slave relay test to a monthly staggered actuation logic test.

124 1191 Figures 3.4-2 Figures 3.4-3 Figures 3.4-4 Bases 3/4.4.9 Bases 3/4.5.2 This amendment modifies the plant heatup and cooldown curves and the maximum allowable PORV setpoints for cold overpressure protection.

125 1174 Table 2.2-1 Table 4.3-1 Table 3.3-4 Bases 2.2.1 This amendment modifies setpoint and allowable values of certain reactor trip system (RTS) and engineered safety features actuation system (ESFAS) function units.

126 1189 Table 3.3-3 Table 3.3-4 Table 4.3-2 Bases 3/4.3.1 This amendment revises the feedwater isolation engineered safety feature actuation system (ESFAS) functions.

127 1195 Section 4.5.2b.1 Bases 3/4.5.2 This amendment eliminates the requirement to vent the centrifugal charging pump casings.

128 1186 Table 3.7-2 Table 2.2-1 This amendment revises the lift setting tolerance of the Main Steam Safety Valves. Additionally, Table 2.2-1 has been revised to reduce the sensor error for the pressurizer pressure-high trip.

129 1196 Section 3/4.9.12 Bases 3/4.9.12 Section 5.3 Section 5.6 Spent Fuel Pool Rerack Amendment.

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April 2024 Revision 173 28 A140.0001 130 1193 Table 3.3-3 Table 3.3-4 Table 4.3-2 This amendment revises the engineered safety features actuation system (ESFAS) functional units 6.f, Loss of Offsite Power - Start Turbine Driven Pump and 8.a and 8.b Loss of Power.

131 1197 Section 3/4 7-9b Section B 3/4 7-3 Section B 3/4 7-3a This amendment revises operability requirements to require four atmospheric steam dump (ASD) lines to be operable.

132 1180 Section 4.4.5.4 Section 4.4.5.5 Table 4.4-3 Bases 3/4.4.5 This amendment allows the repair of Callaway Plant, Unit 1 steam generator tubes with the Electrosleeve tube repair method.

133 1177 All Sections This amendment converted the Callaway Unit 1 Technical Specifications to the Improved Technical Specifications 134 1203 Section 5.6.6 This amendment revises Section 5.6.6, "Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)," of the ITSs that were issued in amendment 133.

135 1204 TOC 1.1 Definition (ACTIONS )

(STAGGERED TEST BASIS)

EXAMPLE 1.3-6 ACTION 3.4.15.B ACTION 3.7.1.B ACTION 3.7.2.D ACTION 3.7.4.D LCO 3.7.13 ACTION 3.7.16.A ACTION 3.8.5.A Section 5.6.5.a.7 This amendment corrected 14 errors in the ITSs that were issued in amendment 133.

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April 2024 Revision 173 29 A140.0001 136 1198 LCO 3.7.1 ACTION 3.7.1 This amendment revises LCO 3.7.1 in that the maximum allowable reactor power for a given number of operable MSSVs per steam generator is reduced in Table 3.7.1-1 and Action A.1. Additionally, two format errors in the actions for LCO 3.7.1 are corrected.

137 1206 ACTION 3.3.2.H SR 3.3.2.14 Table 3.3.2-1 LCO 3.4.10 SR 3.4.10.1 CONDITION 3.4.11.A CONDITION 3.4.11.B This amendment expanded the range of acceptable lift settings and tolerance of the as-found, measured lift settings for the pressurizer safety valves (PSVs) to be considered operable.

Following testing, the as-left lift settings of the PSVs would remain at the current tolerance of +/- 1%, but the nominal lift setting would be reduced.

138 1209 LCO 3.9.4 NOTE COMPLETION TIME 3.8.3.E.2 This amendment allows containment penetrations with direct access to the outside atmosphere to be open under administrative controls during refueling operations, by adding a note to the LCO 3.9.4. In addition, there was a format and editorial correction to TS 3.8.3 to correct an error in the conversion to the improved TS issued in Amendment No. 133.

139 1199 FSAR Changes This amendment request revised the description of the steam generator tube rupture and main steam line break accident in the Callaway Final Safety Analysis Report (FSAR) to reflect increases in the radiological dose consequences calculated for these accidents. These revisions were incorporated into FSAR update revision OL-12.

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April 2024 Revision 173 30 A140.0001 140 1212 SR 3.5.2.5 This amendment added a footnote to Surveillance Requirement (SR) 3.5.2.5 that states that verification of the automatic closure function of the residual heat removal (RHR) pump suction Valve BNHV8812A shall be performed prior to startup from the first shutdown to Mode 5 occurring after September 8, 2000, but not later than June 1, 2001. The next refueling outage for Callaway is scheduled for April 200l.

141 1208 Table 3.3.2-1 This amendment added Surveillance Requirement (SR) 3.3.2.10 for the following two ESFAS instrumentation in the table: item 6.f, loss of offsite power, and item 6.h, auxiliary feedwater pump suction transfer on suction pressure-low.

142 1213 Section 5.5.14 This amendment revised Technical Specifications (TS) Bases Control Program to reflect the changes made to 10 CFR 50.59 as published in the Federal Register on October 4, 1999.

143 1210 FSAR Changes This amendment authorized changes to the FSAR related to the installation of replacement engineered safety feature (ESF) transformers. This amendment allows the replacement of the ESF transformers with new transformers having active automatic load tap changers (LTCs).

144 1214 Section 5.5.3 This amendment deletes Section 5.5.3, Post Accident Sampling, from the Technical Specifications and thereby eliminates the requirements to have and maintain the post-accident sampling system (PASS).

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April 2024 Revision 173 31 A140.0001 145 1215 Section 5.2.1 This amendment revised Technical Specification 5.2.1.c to replace the title "Vice President and Chief Nuclear Officer" with Senior Vice President and Chief Nuclear Officer."

146 1219 LCO 3.5.5 ACTION 3.5.5.A SR 3.5.5.1 This amendment revised Technical Specification 3.5.5 to remove the phrase "and the charging flow control valve full open" from Limiting Condition for Operation, Required Action A.1, and Surveillance Requirement 3.5.5.1 for the reactor coolant pump seal injection flow.

147 1222 SR 3.0.3 Revised Surveillance Requirement (SR) 3.0.3 to extend the delay period before entering a limiting condition for operation upon a missed SR from the current limit of "up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less" to "up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater." In addition, the following requirement is added to SR 3.0.3: "A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed."

148 1211 SR 3.3.1.2 SR 3.3.1.3 The amendment revised Surveillance Requirements (SRs) 3.3.1.2 and 3.3.1.3 on reactor trip system (RTS) instrumentation. The change to SR 3.3.1.2 would replace the reference to the nuclear instrumentation system channel output with a reference to the power range channel output and would delete Note 1 to this SR. The change to SR 3.3.1.3 is editorial.

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April 2024 Revision 173 32 A140.0001 149 1221 ACTIONS 3.3.1.G ACTIONS 3.3.1. I ACTIONS 3.3.9.B LCO 3.4.5 Note ACTIONS 3.4.5.D LCO 3.4.6 Note ACTIONS 3.4.6.B LCO 3.4.7 Notes ACTIONS 3.4.7.B LCO 3.4.8 Notes ACTIONS 3.4.8.B ACTIONS 3.8.2.B ACTIONS 3.8.8.A ACTIONS 3.8.5.A ACTIONS 3.8.10.A ACTIONS 3.9.3.A LCO 3.9.5 Note ACTIONS 3.9.5.A ACTIONS 3.9.6.B This amendment revised several of the Required Actions in the Technical Specifications that require suspension of operations involving positive reactivity additions or suspension of operations involving reactor coolant system (RCS) boron concentration reductions. In addition, the amendment revised several Limiting Condition for Operation (LCO) Notes that preclude reductions in RCS boron concentration. The Required Actions and LCO Notes were revised to allow small, controlled, safe insertions of positive reactivity, but limits the introduction of positive reactivity such that compliance with the required shutdown margin or refueling boron concentration limits will still be satisfied. This amendment is based on a NRC-approved traveler, Technical Specification Task Force (TSTF)-286, Revision 2.

150 1220 LCO 3.5.5 ACTIONS 3.5.5.A SR 3.5.5.1 Figure 3.5.5-1 This amendment revised Technical Specification 3.5.5 to replace the flow and differential pressure limits that were stated for the reactor coolant pump seal injection flow by limits provided in Figure 3.5.5-1, which was added to the Technical Specification.

151 1231 SR 3.3.1.16 Table 3.3.1-1 The amendment revised Technical Specification 3.3.1 by adding Surveillance Requirement 3.3.1.16 to Function 3 of Table 3.3.1-1.

Surveillance Requirement 3.3.1.16 verifies that the reactor trip system response times are within limits every 18 months on a staggered test basis.

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April 2024 Revision 173 33 A140.0001 152 1218 ACTIONS 3.3.6.C Table 3.3.6-1 ACTIONS 3.3.7.E SR 3.3.7.6 Table 3.3.7-1 ACTIONS 3.3.8.A ACTIONS 3.3.8.B ACTIONS 3.3.8.C LCO 3.9.4.a LCO 3.9.4.b SR 3.9.4.2 SR 3.9.4.3 This amendment revised the Limiting Conditions for Operation (LCO's),

Required Actions for LCO's Surveillance Requirements, and Tables specifying requirements on instrumentation in Technical Specification 3.3.6, Technical Specification 3.3.8, and Technical Specification 3.9.4. This amendment allows the equipment hatch and the emergency air lock to be open in refueling outages during core alterations and/or movement of irradiated fuel within containment.

153 1216 1235 Section 5.5.9.d.1.j)2)

The amendment revised paragraph d.1.j)2) of Technical Specification 5.5.9 to 1) delete the requirement that all steam generator tubes containing an Electrosleeve be removed from service within two operating cycles following installation; 2) added requirement that Electrosleeves cannot be installed in the outermost periphery tubes of the steam generator bundles where potentially locked tubes would cause high axial loads;

3) revised references describing electrosleeving: and 4) added the requirement that all sleeves with detected inside diameter flaw indications will be removed from service upon detection.

154 1227 LCO 3.1.8 The amendment revised Limiting Condition for Operation (LCO) 3.1.8, to reduce the required number of channels from four to three channels for certain functions in Technical Specification Table 3.3.1-1 during physics testing in MODE 2.

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April 2024 Revision 173 34 A140.0001 155 1241 Section 5.1.1 Section 5.2.1 Section 5.2.2 Section 5.3.1.2 Section 5.5.1 This amendment revised paragraphs in Section 5.0, "Administrative Controls," to allow the use of generic personnel titles in place of plant-specific personnel titles and require either the operations manager or the assistant operations manager to hold a senior reactor operator license 156 1243 ACTIONS 3.8.3.A This amendment revised Technical Specification 3.8.3 Condition A to increase the specified minimum fuel oil inventories maintained in the fuel oil storage tanks for the diesel generators.

157 1230 TABLE 3.3.1-1 TABLE 3.3.1-2 This amendment revised Technical Specification Tables 3.3.1-1 (Reactor Trip System (RTS) Instrumentation) and 3.3.2-1 (Engineered Safety Feature Actuation System (ESFAS)

Instrumentation) of Limiting Conditions for Operation 3.3.1, "RTS Instrumentation," and 3.3.2, "ESFAS Instrumentation," of the TSs. The revisions are for the SG water level low-low (adverse and normal containment environment) functions.

158 1251 ACTION 3.7.5.C Incorporate a one-time provision that extended the allowed outage time (AOT) for an inoperable turbine-driven auxiliary feedwater pump (TDAFP) by an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, as specified per Required Action C.1. This Amendment permitted additional time to complete troubleshooting, repair, and restoration of the TDAFP O.L.

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April 2024 Revision 173 35 A140.0001 159 1226 Section 1.0 SR 3.7.3.1 This amendment 1) revised the definition of dose equivalent radioiodine 131 (I-131), and 2) increased the maximum allowed closure time of each main feedwater isolation valve (MFIV) from 5 seconds to 15 seconds. In addition, this amendment approved the re-analysis of the steam generator tube rupture with overfill accident.

160 1245 Section 5.5.6 Section 5.5.16 The amendment 1) revised Technical Specification (TS) Section 5.5.6, "Containment Tendon Surveillance Program," for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC and 2) deleted the provisions of Surveillance Requirement (SR) 3.0.2 from this TS.

In addition, the amendment revised TS 5.5.16, "Containment Leakage Rate Testing Program," to add exceptions to Regulatory Guide 1.163, "Performance-Based Containment Leak-Testing Program."

161 1244 None The amendment approved the application of leak-before-break (LBB) for the accumulator and residual heat removal (RHR) lines, and the installation of an opening in the secondary shield wall in terms of the effects of the opening on occupational exposure O.L.

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April 2024 Revision 173 36 A140.0001 162 1228 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.12 SR 3.8.1.13 SR 3.8.1.14 SR 3.8.1.16 SR 3.8.1.17 SR 3.8.1.18 SR 3.8.1.19 This amendment revised several surveillance requirements (SRs) in TS 3.8.1 on alternating current sources for plant operation. The revised SRs have notes deleted or modified to adopt in part the Staff-approved TSTF-283, Revision 3, which will allow these revised SRs to be performed, or partially performed, in reactor modes that previously were not allowed by the TSs.

163 1247 Section 5.5.7 The amendment changed the reactor coolant pump flywheel inspection interval from 10 years to 20 years.

164 1237 LCO 3.0.4 SR 3.0.4 APPL 3.1.1 ACTION 3.1.1.C ACTION 3.3.2.O ACTIONS Note 3.3.3 ACTIONS Note 3.3.4 ACTIONS 3.4.8 ACTIONS Note 3.4.11 ACTIONS Note 3.4.12 ACTIONS 3.4.15 ACTION 3.4.16.A Note ACTIONS Note 3.5.3 ACTION 3.6.8.A ACTION 3.7.4.A ACTION 3.7.4.D ACTIONS Note 3.7.5 ACTIONS Note 3.8.1 APPL 3.9.1 APPL 3.9.6 This amendment modifies the TS requirements for MODE change limitations in Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4 to adopt the provisions of TSTF-359, Increase Flexibility in Mode Restraints. This change also deletes or revises notes in individual TSs that are associated with the changes to LCO 3.0.4 and SR 3.0.4 above.

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April 2024 Revision 173 37 A140.0001 165 1205 ACTIONS 3.3.1.D ACTIONS 3.3.1.E ACTIONS 3.3.1.M ACTIONS 3.3.1.O ACTIONS 3.3.1.P ACTIONS 3.3.1.Q ACTIONS 3.3.1.R ACTIONS 3.3.1.W ACTIONS 3.3.1.X SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.8 ACTIONS 3.3.2.C ACTIONS 3.3.2.D ACTIONS 3.3.2.E ACTIONS 3.3.2.G ACTIONS 3.3.2.I ACTIONS 3.3.2.K ACTIONS 3.3.2.M ACTIONS 3.3.2.N ACTIONS 3.3.2.O ACTIONS 3.3.2.S SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 TABLE 3.3.2-1 SR 3.3.9.3 This amendment revised required actions far certain action conditions; increase the completion times for several required actions (including some notes); delete notes in certain required actions; increase frequency time intervals (including certain notes) in several surveillance requirements (SRs); add an action condition and required actions; revise notes in certain SRs; and revise Table 3.3.2-1.

These change were made to adopt the completion time, test bypass time, and surveillance time interval changes in NRC-approved W CAP-14333-P-A, "Probabilistic Risk Analysis of the RPS

[reactor protection system] and ESFAS Test Times and Completion Times,"

and WCAP-15376-P-A, "Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times." In addition, an administrative correction to the format of the TSs.

166 1254 Section 5.6.1 Section 5.6.4 This amendment eliminated the requirements in Technical Specification to submit monthly operating reports and annual occupational radiation exposure reports.

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April 2024 Revision 173 38 A140.0001 167 1252 All Sections of TS 3.7.3 Revises TS 3.7.3, to adopt the NUREG-1431, "Standard Technical Specifications Westinghouse Plants,"

Revision 3. The requirements add operability and suitable surveillance requirements for main feedwater regulating valves (MFRV) and MFRV bypass valves (MFRVBV), and allow for an extended out-of-service time for one or more main feedwater isolation valves (MFIVs).

168 1248 TOC Section 1.1 Figure 2.1.1-1 ACTIONS 3.3.1.W Table 3.3.1-1 ACTIONS 3.3.2.M Table 3.3.2-1 LCO 3.4.1 SR 3.4.1.1 SR 3.4.1.2 SR 3.4.5.2 SR 3.4.6.2 LCO 3.4.7 SR 3.4.7.2 LCO 3.4.13 ACTION 3.4.13.A ACTION 3.4.13.B SR 3.4.13.1 SR 3.4.13.2 New Spec 3.4.17 Table 3.7.1-1 Section 5.5.9 Section 5.5.16 Section 5.5.10 The amendment is to support the installation of replacement steann generators (SGs) atCallaway during the refueling outage in the fall of 2005.

The amendment also revises (1 ) the affected transient analyses such as an excessive increase in secondary steam flow event, loss of normal feedwater event, tra.nsient mass and energy releases, radiological consequences of 'associated events, and containment pressure/

temperature responses; and (2) the nuclear steam and s~upply system (NSSS) design parameters and transients, and fatigue usage factors and stresses for the replacement SGs.

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April 2024 Revision 173 39 A140.0001 169 1217 Operating License The amendment (1) deletes Conditions 2.C.(3), 2.C.(4), 2.C.(6) through 2.C.(14), Section 2.F, and Attachments 1 and 2, and (2) revises Conditions 2.C.(1) and :3,C.(5), to the facility operating license, to reflect completed requirements. In addition, the list of the attachments and appendices to the operating license is revised to reflect the deletion of Attachments 1 and 2.

170 1258 SR 3.7.3.1 SR 3.7.3.2 SR 3.7.3.3 Figure 3.7.3-1 This amendment revises the stroke time test requirement for the MFIVs by replacing the single-value 15-second stroke time limit with a figure that specifies the stroke time limit as a function of steam generator steam pressure.

171 1260 ACTION 3.6.6.D ACTION 3.6.6.E The amendment revises Required Action D.l, in TS 3.6.6, "Containment Spray and Cooling Systems," to require plant shutdown if both containment cooling trains are out of service, which is more conservative than the previous requirement that allowed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore one of the inoperable trains. There are also changes to other required actions in TS 3.6.6 to reflect the revision to Required Action D.1.

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April 2024 Revision 173 40 A140.0001 172 1262 LCO 3.7.2 ACTION 3.7.2.A ACTION 3.7.2.B ACTION 3.7.2.C ACTION 3.7.2.D ACTION 3.7.2.E ACTION 3.7.2.F ACTION 3.7.2.G ACTION 3.7.2.H ACTION 3.7.2.I This amendment revised TS 3.7.2 by adding the MSIV actuator trains to (1) the limiting condition for operation (LCO) and (2) the conditions, rrequired actions, and completion times for the LCO. The existing conditions, required actions in TS 3.7.2 were renumbered to account for the new conditions and required actions.

173 1267 Section 5.1.2 Section 5.2.2.c Section 5.2.2.d Section 5.2.2.f Section 5.3.1.1 Section 5.7.2.a.1 This amendment revises Technical Specification (TS) 5.0, "Administrative Controls", by removing references to the specific position title "Shift Supervisor" and replacing it with a new position title "Shift Manager". In addition, TS 5.0 is revised to change references to "health physics technician(s)" and "Health Physics Supervision" to "Radiation Protection Department technician(s)" and "Radiation Protection Department Supervision".

174 1256 TS 3.1.9 (New)

ACTION 3.3.1.V ACTION 3.3.1.Y ACTION 3.3.1.Z TABLE 3.3.1-1 The amendment adds a new TS 3.1.9, "RCS [Reactor Coolant System] Boron Limitations <500°F," and revises TS 3.3.1, "Reactor Trip System (RTS)

Instrumentation," for the power range neutron flux - low reactor trip function.

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April 2024 Revision 173 41 A140.0001 175 1246 LCO 3.4.15 ACTIONS 3.4.15.B ACTIONS 3.4.15.C ACTIONS 3.4.15.D ACTIONS 3.4.15.E ACTIONS 3.4.15.F SR 3.4.15.1 SR 3.4.15.2 SR 3.4.15.4 The amendment revises Technical Specification (TS) 3.4.1 5, "RCS

[Reactor Coolant System] Leakage Detection Instrumentation" to delete the containment atmosphere gaseous radioactivity monitor from TS 3.4.1 5 and revise the existing conditions, required actions, completion times, and surveillance requirements in TS 3.4.1 5 to account for the monitor being deleted.

176 1255 SR 3.7.2.1 SR 3.7.3.1 SR 3.7.3.3 This amendment revised TS Surveillance Requirements 3.7.2.1, 3.7.3.1, and 3.7.3.3 on verifying the closure time of the main steam isolation valves, main feedwater regulating valves, main feedwater regulating valve bypass valves, and main feedwater isolation valves in the TSs. This amendment also moved TS Figure 3.7.3-1 to TSB.

177 1274 Section 1.1 Section 5.6.6 This amendment revised (1) the definition of the Pressure and Temperature Limits Report (PTLR) in TS 1.1, "Definitions," and (2) TS 5.6.6, "Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)." to allow the use of previously reviewed and approved analytical methods that are specified by number and title only.

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April 2024 Revision 173 42 A140.0001 178 1257 Section 1.1 LCO 3.4.16 APP 3.4.16 ACTION 3.4.16.A ACTION 3.4.16.B ACTION 3.4.16.C SR 3.4.16.1 FIG 3.4.16-1 (Del)

This amendment revised Technical Specifications (TSs) 1.1, "Definitions,"

and 3.4.16, "RCS [Reactor Coolant System] Specific Activity" to replace the current Limiting Condition for Operation (LCO) 3.4.16 limit on RCS gross-specific activity with limits on RCS Dose Equivalent I-1 31 and Dose Equivalent Xe-133 (DEX). In addition, the current definition of Dose Equivalent I-131 in TS 1.1 would be revised to allow alternate, NRC-approved thyroid dose conversion factors.

179 1269 LCO 3.0.1 LCO 3.0.8 (New)

The amendment revises the Technical Specifications by adding a new Limiting Condition for Operation (LCO) 3.0.8.

which modifies TS requirements for inoperable snubbers. This new LCO allowing a delay time for entering a supported system TS, when the inoperability is due solely to an inoperable snubber, if the risk is assessed and managed.

180 1270 SR 3.5.2.8 SR 3.6.7.1 SR 3.6.7.2 Appendix C This amendment revised Technical Specification Surveillance Requirements (SR) 3.5.2.8, SR 3.6.7.1, and adding new SR 3.6.7.2 as needed to reflect the replacement of the containment emergency sumps suction inlet trash racks and screens with strainers in response to Generic Letter 2004-02. In addition the one time note to SR 3.5.2.5 is being removed as a clean up item since it is no longer applicable..

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April 2024 Revision 173 43 A140.0001 181 1238 ACTION 3.3.9.B ACTION 3.3.9.C LCO 3.9.2 SR 3.9.2.1 The amendment deletes reference to specific isolation valves in the chemical and volume control system (CVCS) and modifies notes to allow exceptions for decontamination activities and for CVCS resin vessel operation.

182 1268 ACTION 3.1.7.A ACTION 3.1.7.B ACTION 3.1.7.C SR 3.2.1.2 SR 3.2.4.2 SR 3.3.1.3 SR 3.3.1.6 The amendment revises TSs 3.1.7, "Rod Position Indication," 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z)) (F, Methodology)," 3.2.4, "Quadrant Power Tilt Ratio (QPTR)," and 3.3.1, "Reactor Trip System (RTS)

Instrumentation," to allow use of the Westinghouse proprietary computer code, the Best Estimate Analyzer for Core Operations - Nuclear (BEACON).

183 1236 Section 2.1.1 Figure 2.1.1-1 (Del)

Table 3.3.1-1 3.4.1 LCO SR 3.4.1.1 SR 3.4.1.2 SR 3.4.1.4 Section 5.6.5 This amendment relocated cycle-specific parameter limits from TS to the Core Operating Limits Report (COLR) and added several topical reports and allowed all cited topical reports to be identified by tile and number only.

These change are consistent with TSTF-339 and TSTF-363.

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April 2024 Revision 173 44 A140.0001 184 1259 ACTION 3.7.10.D.1 ACTION 3.7.11.C.1 ACTION 3.7.13.A ACTION 3.7.13.D The amendment deletes Required Action D.1.2 in TS 3.7.1 0, Control Room Emergency Ventilation System (CREVS), and Required Action C.1.2 in TS 3.7.1 1, Control Room Air Conditioning System (CRACS). For TS 3.7.13, Emergency Exhaust System (EES), the amendment also deletes the phrase in MODE 1, 2, 3, or 4 from Condition A (one EES train inoperable) and revises Condition D to state the following: Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the fuel building.

185 1271 ACTION 3.8.3.A SR 3.8.3.1 This amendment revises TS 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air, and its associated Surveillance Requirement 3.8.3.1 to increase the current minimum emergency diesel generator (EDG) fuel oil inventory required to be maintained onsite.

186 1282 ACTION 3.7.8.A.1 ACTION 3.8.1.B.4 This amendment revised the TSs to allow a one-time extension to the Completion Times for both essential service water (ESW) trains and the emergency diesel generators from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The revision to the TSs would apply when each train of the ESW system is inoperable during their respective ESW system piping replacements.

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April 2024 Revision 173 45 A140.0001 187 1284 Section 5.5.8 The amendment revised TS 5.5.8, Inservice Testing Program, to indicate that Inservice Testing (IST)

Program shall include testing frequencies applicable to the ASME Code for operation and Maintenance of Nuclear Power Plants (OM Code),

and to indicate that there may be some non-standard frequencies, specified as once every 2 years or less in the IST Program, to which provisions of surveillance requirement (SR) 3.0.2 are applicable.

188 1281 ACTION 3.4.10.B.2 ACTION NOTE ACTION 3.4.11.F.1 ACTION 3.4.12.G.1 This amendment revised TS 3.4.10, Pressurizer Safety Valve, TS 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), and TS 3.4.12, Cold Overpressure Mitigation Systtem (COMS), to adopt NRC approved TS Task Force (TSTF) travelers to the Standard TSs TSTF-247-A and TSTF-352-A 189 1279 TABLE 3.3.2-1 SR 3.7.2.1 SR 3.7.2.2 The amendment revised the exception in TS Table 3.3.2-1 for the main feedwater isolation system to be consistent with the modes of applicability for that same system in TS 3.7.3, "Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and Main Feedwater Regulating Valve Bypass Valves (MFRVBVs)," and deleted the same note in SRs 3.7.2.1 and 3.7.2.2 on the MSIVs because the note is no longer needed or appropriate for the two SRs.

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April 2024 Revision 173 46 A140.0001 190 1287 3.7.10 LCO Note ACTIONS 3.7.10.A ACTIONS 3.7.10.B ACTIONS 3.7.10.E SR 3.7.10.2 SR 3.7.10.4 SECTION 5.5.17 The amendment adds a new license condition on the control room envelope (CRE) habitability program, revises the TS requirements related to the CRE habitability in TS 3.7.10, "Control Room Emergency Ventilation System (CREVS)," and establishes a CRE habitability program in TS Section 5.5, "Administrative Controls -Programs and Manuals." These changes are consistent with the NRC-approved IndustryfTS Task Force (TSTF)

Traveler TSTF-448, Revision 3, "Control Room Habitability."

191 1282 ACTION 3.7.8.A.1 ACTION 3.8.1.B.4 This amendment revised the TSs to allow a one-time extension to the Completion Times for both essential service water (ESW) trains and the emergency diesel generators from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The revision to the TSs would apply when B train of the ESW system is inoperable during the ESW system piping replacements.

192 1283 ACTION 3.3.7.E Table 3.3.7-1 3.3.8 ACTION Notes 3.7.10 APPLICABILITY ACTION 3.7.10.D ACTION 3.7.10.E 3.7.13 ACTION Note 3.8.2 APPLICABILITY 3.8.2 ACTION Note 3.8.5 APPLICABILITY 3.8.5 ACTION Note 3.8.8 APPLICABILITY 3.8.8 ACTION Note 3.8.10 APPLICABILITY 3.8.10 ACTION Note This amendment (1) deletes MODES 5 and 6 from the Control Room Emergency Ventilation System and its actuation instrumentation in TS 3.7.10 and TS 3.3.7; (2) adopts NRC-approved Technical Specification Task Force (TSTF) change traveler TSTF-36-A for TSs 3.3.8, 3.7.13, 3.8.2,3.8.5,3.8.8, and 3.8.10; and (3) adds a restriction to the Limiting Condition for Operation (LCO) applicability for TSs 3.8.2, 3.8.5, 3.8.8, and 3.8.10 such that these LCOs apply not only during MODES 5 and 6, but also during the movement of irradiated fuel assemblies regardless of the MODE in which the plant is operating.

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April 2024 Revision 173 47 A140.0001 193 09-0014 SECTION 5.2.2.d This amendment revised the TS 5.2.2, "Unit Staff," to eliminate working hour restrictions in paragraph d to support compliance with Title 10 of the Code of Federal Regulations (10 CFR) Part 26.

The request is consistent with the guidance contained in the U.S.

Nuclear Regulatory Commission (NRC)-approved Revision 0 to Technical Specifications Task Force (TSTF) change traveler TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26."

194 08-0002 SR 3.8.4.2 SR 3.8.4.5 This amendment revises the battery connection resistance verification limits in Surveillance Requirement (SR) 3.8.4.2 and SR 3.8.4.5, by lowering the acceptance criteria for cell-to-cell (i.e., inter-cell) and terminal battery connection resistance from 150 micro-ohms to 69 micro-ohms.

195 09-0008 Section 5.5.16 This amendment revised TS 5.5.16, "Containment Leakage Rate Testing Program." The revision reflects a one-time extension of the current containment Type A leak rate test (integrated leak rate test or ILRT) interval requirement of Title 10 of the Code of Federal Regulations (10 CFR)

Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,"

Option B, "Performance Based Requirements," from 10 years to 15 years. The change allows the next ILRT to be performed no later than October 25, 2014.

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April 2024 Revision 173 48 A140.0001 196 10-0011 ACTIONS 3.3.2.J The amendment revises TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation,"

Condition J for ESFAS instrumentation function 6.g to read, "One or more Main Feedwater Pumps trip channel(s) inoperable," make corresponding changes to Required Action J.1, and place a Note above Required Actions J.1 and J.2 for consistency with the revised Condition.

197 1277 ACTIONS 3.3.2.P.2 Table 3.3.2-1 LCO 3.7.2 Applicability 3.7.2 ACTIONS 3.7.2.E ACTIONS 3.7.2.H ACTIONS 3.7.2.H.1 ACTIONS 3.7.2.H.2 ACTIONS 3.7.2.I ACTIONS 3.7.2.I.1 ACTIONS 3.7.2.I.2 ACTIONS 3.7.2.J ACTIONS 3.7.2.J.1 ACTIONS 3.7.2.J.2 ACTIONS 3.7.2.K ACTIONS 3.7.2.K.1 ACTIONS 3.7.2.K.2 SR 3.7.2.2 SR 3.7.2.3 TS 3.7.19 (New)

This amendment made the following changes. 1) Revised TS 3.7.2, "Main Steam Isolation Valves (MSIVs)," to add the main steam isolation valve bypass valves and main steam low point drain isolation valves to the scope of the TS 3.7.2; 2) Revise footnotes (i) and (k) in TS Table 3.3.2-1, to make the Applicability of TS Table 3.3.2-1 consistent with the Applicability of TS 3.7.2; and 3) Add new TS 3.7.19, "Secondary System Isolation Valves (SSIVs)," Correspondingly, add new Function 10 in TS Table 3.3.2-1.

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April 2024 Revision 173 49 A140.0001 198 1289 Table 3.3.2-1 LCO 3.7.3 Applicability 3.7.3 ACTIONS 3.7.3.C.1 ACTIONS 3.7.3.C.2 This amendment made the following changes. 1) Revised TS 3.7.3 so that the LCO and Applicability more accurately reflect the conditions for when the LCO should be applicable and more effectively provide appropriate exceptions to the Applicability for certain valve configurations.; 2)Revise the title of TS 3.7.3; and 3) Revised the exception footnotes in TS 3.3.2, Table 3.3.2-1, to improve the application of existing notes and/or incorporate more appropriate notes as applicable.

199 1253 ACTIONS 3.3.3.C ACTIONS 3.3.3.D ACTIONS 3.3.3.E ACTIONS 3.3.3.F ACTIONS 3.3.3.G SR 3.3.3.1 TABLE 3.3.3-1 SPEC 3.6.8 (Del)

ACTIONS 3.7.4.D ACTIONS 3.7.4.D.1ACTIONS 3.8.1.A.2 ACTIONS 3.8.1.C.1 Section 5.5.16 Section 5.6.3 Section 5.6.8 The amendment deletes the TS requirements for the containment hydrogen recombiners and relaxed the requirements for hydrogen and oxygen monitoring. The TS changes would support implementation of the revisions to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.44, "Combustible gas control for nuclear power reactors," that became effective on October 16, 2003. In addition, the amendment corrected four typographical errors in the TSs.

200 09-0017 Applicability 3.3.9 This amendment revises the LCO 3.3.9 Applicability Note to clarify the situations during which the Boron Dilution Mitigation System signal may be blocked in MODES 2 and 3.

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April 2024 Revision 173 50 A140.0001 201 09-0039 ACTIONS 3.3.2.J ACTIONS 3.3.2.M ACTIONS 3.3.2.O ACTIONS 3.3.2.Q Table 3.3.2-1 The amendment revises TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," to provide a 24-hour Completion Time (CT) for restoration of an inoperable Balance of Plant (BOP) ESFAS train and extends the CTs associated with individual instrument channels in the BOP ESFAS train to maintain overall consistency of related TS actions.

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April 2024 Revision 173 51 A140.0001 202 SR 3.1.1.1 SR 3.1.2.1 SR 3.1.4.1 SR 3.1.4.2 SR 3.1.5.1 SR 3.1.6.2 SR 3.1.6.3 SR 3.1.8.2 SR 3.1.8.3 SR 3.1.8.4 SR 3.1.9.1 SR 3.2.1.1 SR 3.2.1.2 SR 3.2.2.1 SR 3.2.3.1 SR 3.2.4.1 SR 3.2.4.2 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.8 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.13 SR 3.3.1.14 SR 3.3.1.16 SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.7 SR 3.3.2.8 SR 3.3.2.9 SR 3.3.2.10 The amendment revised the TSs by relocating specific surveillance frequencies to a lCallaway controlled program with the guidance of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies."

This amendment adopts NRC-approved Technical Specification Task Force (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF]

Initiative 5b." When implemented, TSTF-425 relocates most periodic frequencies of TS surveillances to a licensee-controlled program, the Surveillance Frequency Control Program (SFCP),

and provides requirements for the new program in the Administrative Controls section of the TSs.

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April 2024 Revision 173 52 A140.0001 202 (cont.)

SR 3.3.2.11 SR 3.3.2.12 SR 3.3.2.13 SR 3.3.2.14 SR 3.3.3.1 SR 3.3.3.2 SR 3.3.4.1 SR 3.3.4.2 SR 3.3.4.3 SR 3.3.5.1 SR 3.3.5.2 SR 3.3.5.3 SR 3.3.5.4 SR 3.3.6.1 SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.4 SR 3.3.6.5 SR 3.3.6.6 SR 3.3.7.1 SR 3.3.7.2 SR 3.3.7.3 SR 3.3.7.4 SR 3.3.7.5 SR 3.3.7.6 SR 3.3.8.1 SR 3.3.8.2 SR 3.3.8.3 SR 3.3.8.4 SR 3.3.8.5 SR 3.3.9.1 SR 3.3.9.2 SR 3.3.9.3 SR 3.3.9.4 SR 3.3.9.5 SR 3.3.9.6 SR 3.4.1.1 SR 3.4.1.2 SR 3.4.1.3 SR 3.4.1.4 SR 3.4.2.1 O.L.

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April 2024 Revision 173 53 A140.0001 202 (cont.)

SR 3.4.3.1 SR 3.4.4.1 SR 3.4.5.1 SR 3.4.5.2 SR 3.4.5.3 SR 3.4.6.1 SR 3.4.6.2 SR 3.4.6.3 SR 3.4.7.1 SR 3.4.7.2 SR 3.4.7.3 SR 3.4.8.1 SR 3.4.8.2 SR 3.4.9.1 SR 3.4.9.2 SR 3.4.11.1 SR 3.4.12.1 SR 3.4.12.2 SR 3.4.12.3 SR 3.4.12.4 SR 3.4.12.5 SR 3.4.12.6 SR 3.4.12.7 SR 3.4.12.8 SR 3.4.13.1 SR 3.4.13.2 SR 3.4.14.1 SR 3.4.14.2 SR 3.4.15.1 SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SR 3.4.15.5 SR 3.4.16.1 SR 3.4.16.2 SR 3.5.1.1 SR 3.5.1.2 SR 3.5.1.3 SR 3.5.1.4 SR 3.5.1.5 SR 3.5.2.1 O.L.

AMENDMENT NO.

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April 2024 Revision 173 54 A140.0001 202 (cont.)

SR 3.5.2.2 SR 3.5.2.3 SR 3.5.2.5 SR 3.5.2.6 SR 3.5.2.7 SR 3.5.2.8 SR 3.5.4.1 SR 3.5.4.2 SR 3.5.4.3 SR 3.5.5.1 SR 3.6.2.2 SR 3.6.3.1 SR 3.6.3.2 SR 3.6.3.3 SR 3.6.3.6 SR 3.6.3.7 SR 3.6.3.8 SR 3.6.4.1 SR 3.6.5.1 SR 3.6.6.1 SR 3.6.6.2 SR 3.6.6.3 SR 3.6.6.5 SR 3.6.6.6 SR 3.6.6.7 SR 3.6.6.8 SR 3.6.7.1 SR 3.7.2.2 SR 3.7.3.2 SR 3.7.5.1 SR 3.7.5.3 SR 3.7.5.4 SR 3.7.6.1 SR 3.7.7.1 SR 3.7.7.2 SR 3.7.7.3 SR 3.7.8.1 SR 3.7.8.2 SR 3.7.8.3 SR 3.7.9.1 SR 3.7.9.2 O.L.

AMENDMENT NO.

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April 2024 Revision 173 55 A140.0001 202 (cont.)

SR 3.7.9.3 SR 3.7.10.1 SR 3.7.10.3 SR 3.7.11.1 SR 3.7.13.1 SR 3.7.13.3 SR 3.7.13.4 SR 3.7.13.5 SR 3.7.15.1 SR 3.7.16.1 SR 3.7.18.1 SR 3.7.19.2 SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 SR 3.8.1.4 SR 3.8.1.6 SR 3.8.1.7 SR 3.8.1.10 SR 3.8.1.11 SR 3.8.1.12 SR 3.8.1.13 SR 3.8.1.14 SR 3.8.1.15 SR 3.8.1.16 SR 3.8.1.17 SR 3.8.1.18 SR 3.8.1.19 SR 3.8.1.20 SR 3.8.1.21 SR 3.8.3.1 SR 3.8.3.2 SR 3.8.3.4 SR 3.8.3.5 SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SR 3.8.4.6 SR 3.8.4.7 SR 3.8.4.8 O.L.

AMENDMENT NO.

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April 2024 Revision 173 56 A140.0001 202 (cont.)

SR 3.8.6.1 SR 3.8.6.2 SR 3.8.6.3 SR 3.8.7.1 SR 3.8.8.1 SR 3.8.9.1 SR 3.8.10.1 SR 3.9.1.1 SR 3.9.1.2 SR 3.9.3.1 SR 3.9.3.2 SR 3.9.4.1 SR 3.9.4.2 SR 3.9.4.3 SR 3.9.5.1 SR 3.9.6.1 SR 3.9.6.2 SR 3.9.7.1 Section 5.5.18 203 10-0022 Operating License E The amendment approves the Callaway Plant, Unit 1, Cyber Security Plan and associated implementation schedule, and revises Paragraph 2.E of Facility Operating License No. NPF-30 to provide a license condition to require the licensee to fully implement and maintain in effect all provisions of the NRC-approved Cyber Security Plan.

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April 2024 Revision 173 57 A140.0001 204 10-0036 SR 3.3.8.6 Table 3.3.8-1 The amendment adds new Surveillance Requirement (SR) 3.3.8.6, to TS 3.3.8, "Emergency Exhaust System (EES) Actuation Instrumentation" and to Table 3.3.8-1, "EES Actuation Instrumentation." The new SR requires the performance of response time testing on the portion of the EES required to isolate the normal fuel building ventilation exhaust flow path and initiate the fuel building ventilation isolation signal mode of operation.

205 09-0040 ACTION 3.3.6.B.1 This amendment adds a Note to Required Action B.1 of TS 3.3.6, "Containment Purge Isolation Instrumentation," to conditionally allow containment mini-purge supply and exhaust valves that have been closed in accordance with the Action to be opened under administrative controls as required for certain operational needs.

206 11-0012 Operating License C(2)

Operating License C(5)

Section 5.4.1 The amendment transitions the Callaway fire protection program to a risk-informed, performance-based program based on National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition" (NFPA 805), in accordance with 10 CFR 50.48(c).

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AMENDMENT NO.

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April 2024 Revision 173 58 A140.0001 207 12-0041 Operating License C(2)

This amendment revises the methodology in the licensing basis as described in the FSAR-SP to include damping values for the seismic design and analysis of the integrated head assembly that are consistent with the recommendations of NRC Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," Revision 1, March 2007.

208 12-0015 SR 3.7.9.1 SR 3.7.9.3 SR 3.7.9.4 This amendment revised TS 3.7.9, "Ultimate Heat Sink (UHS)," to incorporate a more restrictive UHS level and pond temperature limits which are specified in Surveillance Requirements (SRs) 3.7.9.1 and 3.7.9.2, respectively. A new SR 3.7.9.4 is added to verify that the UHS cooling tower fans respond appropriately to automatic start signals.

209 13-0010 SR 3.7.10.1 SR 3.7.13.1 The amendment revises TS Surveillance Requirement (SR) 3.7.10.1 and SR 3.7.13.1 to reduce the required run time for periodic operation of the control room pressurization system filter trains and emergency exhaust system filter trains, with heaters on, from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 15 minutes. The amendment is consistent with plant-specific options provided in the NRC's model safety evaluation in Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month," as part of the consolidated line item improvement process.

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AMENDMENT NO.

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April 2024 Revision 173 59 A140.0001 210 13-0003 Table 3.3.1-1 3.4.12 LCO 3.4.12 LCO Notes ACTIONS 3.4.12.B ACTIONS 3.4.12.B.1 SR 3.4.12.2 The amendment revises TS 3.4.12, "Cold Overpressure Mitigation System (COMS)," to reflect the mass input transient analysis that assumes an Emergency Core Cooling System centrifugal charging pump and the normal charging pump capable of injecting into the reactor coolant system when TS 3.4.12 is applicable.

The amendment also revises TS Table 3.3.1-1, "Reactor Trip System Instrumentation," to remove unnecessary page number references.

211 13-0016 SP SEC 3.6.2.1.2.4 SP TBL 3.6-2 The amendment adds a new pipe crack exclusion allowance to FSAR-Standard Plant Section 3.6.2.1.2.4, "ASME [American Society of Mechanical Engineers] Section Ill and Non-Nuclear Piping-Moderate-Energy," and FSAR-Standard Plant Table 3.6-2, "Design Comparison to Regulatory Positions of Regulatory Guide 1.46, Revision 0, dated May 1973, titled 'Protection Against Pipe Whip Inside Containment,"' in particular regard to the high-density polyethylene (HOPE) piping installed in ASME Class 3 line segments of the essential service water system. Also, new Reference 25 is added to FSAR-Standard Plant Section 3.6.3 to cite the NRG-approved version of the HOPE requirements covered by Relief Request 13R-10 dated October 31, 2008.

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AMENDMENT NO.

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April 2024 Revision 173 60 A140.0001 212 NA Emergency Action Level (EAL)

The amendment revises Callaways EAL scheme to a scheme based on Nuclear Energy Institute (NEI) 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors," November 2012.

213 14-0003 SR 3.4.6.4 SR 3.4.7.4 SR 3.4.8.3 SR 3.5.2.2 SR 3.5.2.3 SR 3.6.6.1 SR 3.6.6.9 SR 3.9.5.2 SR 3.9.6.3 This amendment revised the TS requirements to address NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems as described in Technical Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, Generic Letter 2008-01, Managing gas Accumulation.

214 15-0009 Operating License 17(E)

This amendment revised the final impelementation date associated with the Callaway Plant Cyber Security Plan and License Amendment 203 215 14-0014 3.4.17 LCO 3.4.17 ACTION A SR 3.4.17.2 Section 5.5.9 Section 5.6.10 This amendment revised the TS requirements to adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection 216 15-0005 2.1.1.1 LCO Section 5.6.5.b This amendment revise the TS requirements to adopt WCAP-14565-P-A Addendum 2-P-A methodology and revise the DNBR to align with previously approved WCAP-14483 217 16-0011 Section 5.6.5.b This amendment revises the TS requirements to adopt the approved core design methodology described in WCAP-16045-P-A and WCAP-16045-P-A Addendum 1-A.

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AMENDMENT NO.

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April 2024 Revision 173 61 A140.0001 218 16-0001 FSAR SP Appendix 3A FSAR SP 8.3.1.1.2 This amendment revises the commitment to Reg. Guide 1.106 to specify use of Regulatory Position C.2 for the auxiliary feedwater control valves (ALHV0005, ALHV0007, ALHV0009, and ALHV0011).

219 16-0013 License Condition 2.C.(18)

This amendment adds a new TS 3.7.20, "Class 1E Electrical Equipment Air Conditioning System," and adds a new License Condition 2.C.(18) for completion of plant modifications to install supplemental cooling trains and reduce the power of each control room pressurization system charcoal adsorber unit heater from 15 kW to 5 kW.

220 N/A N/A This amendment revises Callaway's EAL scheme by changing EAL CA6.1, "Cold Shutdown/Refueling System Malfunction Hazardous event affecting a SAFETY SYSTEM needed for the current operating MODE: Alert," and EAL SA9.1, "System Malfunction Hazardous event affecting a SAFETY SYSTEM needed for the current operating MODE: Alert," and deleting Initiating Condition HG1 and associated EAL HG1.1, "Hazard HOSTILE ACTION resulting in loss of physical control of the facility: General Emergency."

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AMENDMENT NO.

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April 2024 Revision 173 62 A140.0001 221 18-0025 TS SR 3.3.2.6 TS SR 3.3.2.14 TS TBL 3.3.2-1 This amendment revises TS Table 3.3.2-1 Function 5.a and relocates TS SR relocates requirements for SLAVE RELAY TEST of slave relay K602 from TS SR 3.3.2.14 to TS SR 3.3.2.6.

222 18-0021 TS 1.1 TS SR 3.4.10.1 TS SR 3.4.11.1 TS SR 3.5.2.4 TS SR 3.6.3.5 TS SR 3.6.6.4 TS SR 3.7.1.1 TS SR 3.7.2.1 TS SR 3.7.2.3 TS SR 3.7.3.1 TS SR 3.7.3.3 TS SR 3.7.4.1 TS SR 3.7.4.2 TS SR 3.7.19.1 TS AC 5.5.8 This amendment deletes TS AC 5.5.8, "Inservice Testing Program," and revises TS SR 3.4.10.1, TS SR 3.4.11.2, TS SR 3.5.2.4, TS SR 3.6.3.5, TS SR 3.6.6.4, TS SR 3.7.1.1, TS SR 3.7.2.1, TS SR 3.7.2.3, TS SR 3.7.3.1, TS SR 3.7.3.3, TS SR 3.7.4.1, TS SR 3.7.4.2, and TS SR 3.7.19.1, by replacing TS AC 5.5.8, "Inservice Testing Program" with a new term "INSERVICE TESTING PROGRAM" defined in TS 1.1 as per TSTF-545, Rev. 3.

223 20-0013 TS AC 5.5.9 This amendment revises TS AC 5.5.9, "Steam Generator (SG) Program," to implement a one-time deferral of the steam generator inspection scheduled for Refuel Outage 24 (fall 2020) to Refuel Outage 25 (spring 2022).

224 19-0012 License Condition 2.C.(5)

This amendment revises License Condition 2.C.(5) to reflect NRC approval for acceptance, by use of performance-based methods, of installed and new installations of anti-sweat insulation (not conforming to NFPA-805) in limited applications at Callaway Plant.

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AMENDMENT NO.

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April 2024 Revision 173 63 A140.0001 225 19-0013 TS AC 5.3.1 TS AC 5.3.1.1 TS AC 5.3.1.2 This amendment deletes TS AC 5.3.1.1 and TS AC 5.3.1.1 and revises TS AC 5.3.1 to replace specific requirements for unit staff qualifications with a reference to the standards that are referenced in the OQAM, subject to the exceptions that are specified in the OQAM.

226 21-0024 License Condition 2.C.(19)

This amendment approves implementation of 10 CFR 50.69 for categorization of Risk Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs).

227 20-0009 TS 1.3 LCO 3.0.4 SR 3.0.3 This amendment revises TS Sections 1.3, "Completion Times," and 3.0, "LCO Applicability" and "SR Applicability." The proposed changes clarify and expand the use and application of the TS usage rules.

228 19-0014 SR 3.5.2.8 SR 3.5.2.1 LCO 3.6 AC 5.5.15 This amendment adopts a risk-informed approach to address GSI 191, and respond to Generic Letter 2004-02.

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April 2024 Revision 173 64 A140.0001 229 20-0007 License Condition 2.C.(20)

TS 1.3 LCO 3.3.1 LCO 3.3.2 LCO 3.3.5 LCO 3.4.11 LCO 3.5.2 LCO 3.6.2 LCO 3.6.3 LCO 3.6.6 LCO 3.7.2 LCO 3.7.4 LCO 3.7.5 LCO 3.7.7 LCO 3.7.8 LCO 3.7.9 LCO 3.8.1 LCO 3.8.4 LCO 3.8.7 LCO 3.8.9 AC 5.5.19 This amendment adopts TSTF-505, Provide Risk-Informed Extended Completion Times, Rev. 2, and TSTF-439, Eliminate Second Completion Times Limiting Time From Discovery of Failure To Meet an LCO, Rev. 2.

230 21-0013 AC 5.5.9 AC 5.6.10 This amendment modifies the Steam Generator (SG) Program, and Steam Generator Tube Inspection Report consistent with TSTF-577, Revised Frequencies for Steam Generator Tube Inspections.

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AMENDMENT NO.

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April 2024 Revision 173 65 A140.0001 231 N/A N/A This amendment revises the RERP to make the following changes:

- Remove the 15-minute and 30-minute "Normal Hours" response and activation goals, leaving the 75-minute and 90-minute "Off-Normal Hours" activation goals as the station standard to cover all hours.

- Extend the State and counties "follow-up" notification goal from 30 minutes to 60 minutes and allow for even further increases when conditions are stable, with the agreement of the State of Missouri and local counties.

232 22-0015 LCO 3.7.16 LCO 3.7.17 FIG 3.7.17 Section 4.3 This Amendment revises the TS to accommodate a simplified storage configuration that establishes two regions in the spent fuel pool and provide a bounding nuclear criticality safety analysis for additional fuel assembly designs.

233 21-0015 Section 1.1 LCO 3.7.10 Section 5.5.11 Section 5.5.12 Section 5.5.17 This Amendment enhances the alignment between FSAR Chapter 15 accident radiological dose evaluation models, and the control room design and operation. This includes increasing the maximum allowable unfiltered air inleakage values to provide additional margin to measured values and removing credit for the charcoal adsorbers in the control building pressurization unit in the alternate source term dose analyses.

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April 2024 Revision 173 66 A140.0001 234 20-0004 Section 5.5.16 This Amendment revises the TS to allow a permanent extension of the Type A integrated leakage rate test and Type C leak rate test frequencies based on the guidance in Nuclear Energy Institute Topical Report NEI 94-01.

235 22-0002 Section 2.1 Section 4.2 This Amendment revises the TS to allow a limited number of Framatome, Inc GAIA fuel with M5 as a fuel cladding material in operating cycle 27 to obtain incore performance data and obtain operational experience with the GAIA fuel design. Sections 2.1 and 4.2 are revised to reflect the corresponding Safety Limits and cladding material of the new fuel design.

236 20-0014 LCO 3.8.3 This Amendment revises the TS by removing the current stored diesel fuel oil and lube oil numerical volume requirements and replacing them with duration-based diesel operating time requirements, consistent with TSTF 501, Rev. 1.

237 22-0029 LCO 3.4.8 LCO 3.7.11 LCO 3.9.6 This Amendment revises the Callaway Licensing Basis to allow use of one train of the normal, non-safety-related service water system to solely provide cooling water support for one of two redundant trains of TS-required equipment when both equipment trains are required to be operable during cold shutdown/refueling conditions.

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AMENDMENT NO.

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