ML23067A152
| ML23067A152 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/29/2022 |
| From: | Union Electric Co, Ameren Missouri |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23067A139 | List:
|
| References | |
| ULNRC-06782 | |
| Download: ML23067A152 (1) | |
Text
July 6, 2022 Revision 167 OPERATING LICENSE AMENDMENT INDEX O.L.
O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. 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 Addition of two managerial positions to Section 6.5.1.2 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 Provided a Nov. 30, 1985, deadline for 2.C.(3)(a) 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 Revision to the offsite and unit Figure 6.2-2 organizational charts.
8 1023 Table 4.3-1 Extends initial 18 month surveillance Table 4.3-2 interval for various tests until prior to Section 4.5.2 startup following the first refueling Section 4.6.2.1 outage or June 1, 1986, whichever Section 4.6.3.2 comes first.
Section 4.7.3 Section 4.7.4 Section 4.8.1.1.2 Section 4.8.2.1 1
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 9 1021 Section 3/4.8.4.1 Deletes the requirement for resistance Bases 3/4.8.4 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 Increases the permitted enrichment of Section 5.3.1 fuel to be stored in spent fuel pool.
Section 5.6.1.1 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 Organization changes - QA nuclear Figure 6.2-2 associated with new corporate Quality Section 6.5.1.2 Systems Department.
15 1036 1.0 Definitions Transition from low-parasitic fuel Figure 2.1-1 assembly fueled core to optimized fuel Table 2.2-1 assembly fuel core.
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 2
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 16 1043 Figure 6.2-1 Organizational changes - established Figure 6.2-2 positions of General Manager, Nuclear Section 6.5.1.2 Operations, and Manager, Operations Section 6.5.2 Support.
Section 6.5.3.1 17 1027 Table 3.3-1 Modified the surveillance interval for Table 4.3-1 analog channel operational tests and Bases 3/4.3 the allowable out-of-service time of reactor trip system instrumentation.
18 1030 Table 3.3-5 Modify response times pertaining to Table 3.6-1 the MSIV and the main FW isolation Section 3/4.7.1.6 valves by removing the valve closure Bases 3/4.7.1.6 time to a separate specification.
19 1041 Table 3.3-1 Require 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> restoration in the Table 4.3-1 event of loss of one of the diverse reactor trip features (undervoltage or shunt trip attachment).
20 1050 Table 3.3-6 Deletes the trip functions of the Table 3.3-13 containment atmosphere radiation Bases 3/4.9 monitors associated with containment purge isolation and control room ventilation.
21 1025 Section 3/4.8.1.1 Increase overall emergency D/G Bases 3/4.8 reliability and prevent undue stress and wear on the D/G engines.
22 1081 Table 3.3-5 Increases ESF response time by 15 Bases 3/4.3 seconds for: Containment Pressure-High1, SI; Pressurizer Pressure-Low, SI; Steam Line Pressure-Low, SI.
23 1055 Figure 3.9-1 Curves for Westinghouse optimized Section 5.3.1 fuel (OFA) and standard fuel (SFA).
Section 5.6.1.1 States a maximum enrichment of 4.25 weight percent U-235 for fuel storage.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Revises requirements for reporting Section 6.9.1.6 iodine spiking. Eliminates the Section 3.4.8 requirement to shut down the plant Bases 3/4.4.8 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 Transition from low-parasitic fuel Figure 2.1-1 assembly and optimized fuel assembly Table 2.2-1 fuel core to Vantage 5 (V-5) fuel Bases 2.1 assembly fueled core.
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 29 1063 Section 3/4.1.3.5 Revises definition of the fully Figure 3.1-1 withdrawn shutdown and control rod Bases 3/4.1.3 position from 228 steps to 225 steps or higher.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 30 1054 Section 3/4.3.3.7 Remove fire protection T/S and place Section 3/4.7.10 them in plant procedures and in the Section 3/4.7.11 FSAR.
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 31 1065 Table 4.3-3 Corrects administrative oversight that Section 4.11.2.5 references the wrong specification for Table 3.1-13.
32 1071 Table 6.2-1 Reflects nuclear function Table 6.2-2 organizational changes.
Section 6.5.1.2 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 Increase in the authorized core Figure 2.1-1 thermal power.
Table 2.2-1 36 1064 Figure 3.4-2 Revises the plant heatup and Figure 3.4-3 cooldown curves, revises the Table 4.4-5 maximum allowable PORV setpoint Figure 3.4-4 curve, and revises the reactor vessel Bases 3/4.4.9 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Changes the T/S to reflect recent Section 6.2.1 organizational changes. All references Section 6.5.1.6 regarding the "Vice President, Section 6.5.1.7 Nuclear" are changed to the "Senior Section 6.5.1.8 Vice President, Nuclear". The position Section 6.5.2.1 of General Manager, Engineering Section 6.5.2.2 (Nuclear) has been deleted from the Section 6.5.2.9 Nuclear Safety Review Board (NSRB)
Section 6.5.2.10 and the Manager, Licensing and Fuels, Section 6.6.1 has been appointed Chairman of the Section 6.7.1 NSRB.
40 1073 Section 3/4.5.1 Allows the plant to remain in Hot Bases 3/4.5.1 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 42 1081 Section 4.4.9.3 Reduces the required RHR system Section 4.5.2 flowrate during Mode 6 operation, Section 3.5.4 deletes the RHR autoclosure interlock Section 4.9.8.1 (ACI) function, and allows the safety Section 3/4.9.8.2 injection pumps to be energized with Bases 3/4.4.9 the head on and with water level not Bases 3/4.5.2 above the top of the reactor vessel Bases 3/4.5.3 flange, in Modes 5 and 6.
Bases 3/4.5.4 Bases 3/4.5.5 Bases 3/4.9.8 43 1074 Table 2.2-1 Revises the provisions in the T/S Table 3.3-1 relating to the steam generator low-low Table 3.3-2 level trip circuitry by adding an Table 4.3-1 Environmental Allowance Modifier Table 3.3-3 (AM) and a Trip Time Delay (TTD).
Table 3.3-4 Table 3.3-5 Table 4.3-2 Bases 2.0 44 1079 Bases 2.1.1 Revises the T/S to support a core Section 3.1.1.3 reload for Cycle 4. The revised T/S Section 3.1.2.5 includes increased peaking factors, a Section 3.1.2.6 positive moderator temperature Section 3.2.1 coefficient, increased refueling water Section 4.2.1.4 storage tank and accumulator boron Section 3.2.2 concentrations, and increased spray Figure 3.2-2 additive tank sodium hydroxide Section 4.2.2.2 concentration.
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 7
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 45 1039 Section 4.3.3.5.3 Incorporates new T/S LCO and Section 3/4.7.1.7 surveillance requirements for the Bases 3/4.7.1.7 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 Revises the referenced figures Figure 5.1-2 regarding the exclusion area, low Figure 5.1-3 population zone, site boundary for Figure 5.1-4 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 />.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 50 1087 Section1.0 Relocates the existing procedural Section 3/4.3.10 details of the current Radiological Section 3/4.3.11 Effluent Technical Specifications Section 3/4.3.12 (RETS) to the Offsite Dose Calculation Bases 3/4.3.10 Manual (ODCM), and procedural Bases 3/4.3.11 details for the solid radioactive wastes Bases 3/4.3.12 to the Process Control Program (PCP).
Section 6.8 The amendment also incorporates the Section 6.9 respective programmatic controls into Section 6.10 the Administrative Controls section of Section 6.11 the Technical Specifications.
Section 6.12 Section 6.13 Section 6.14 51 1085 Section 3/4.1.3 Allows continued operation for 72 Bases 3/4.1.3 hours 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 Removes the 3.25 limit for Bases 4.0.2 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 Revises T/S Sections 5.3.1 and 5.6.1.1 Section 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Revises T/S by deleting the power Table 3.3-1 range, neutron flux, high negative rate Table 3.3-2 trip.
Table 4.3-1 Bases 2.2.1 57 1099 Table 2.2-1 Revises T/S and associated bases to Table 3.3-4 accommodate the replacement of the Table 4.3-1 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 Relocates cycle-specific core Section 3/4.1.1.3 parameters from the T/S and places Section 3/4.1.3.5 them in the Core Operating Limits Section 3/4.1.3.6 Report (COLR).
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 10 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Revised T/S by deleting references Section 6.4 superseded by the May 26, 1987 revision to 10CFR55.
61 1102 Section 3/4.1.3.2 Revises T/S to add an action Bases 3/4.1.3.2 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 The amendment extends the allowable Table 4.3-1 out-of-service times (AOTs) and the Table 3.3-3 surveillance test intervals for the Table 4.3-2 analog channels of the Engineered Bases 3/4.3.1 Safety Features Actuation System Bases 3/4.3.2 (ESFAS). These revisions also include extended AOTs for the ESFAS actuation logic and actuation relays of the solid state protection system.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 65 1123 Bases 3/4.8.1 Revises Surveillance 4.8.1.1.2.f.(2)
Bases 3/4.8.2 concerning diesel generator load reject Bases 3/4.8.3 testing by removing the reference to a Section 4.8.1.1.2.f.(2) 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 Revises Technical Specification Bases 3/4.4.6.2 3/4.4.6 and associated Bases to Section 3/4.6.2.f change the allowed leakage limit for reactor coolant system pressure isolation valves.
67 1111 Section 3/4.7.8 Revises T/S 3/4.7.8, "Snubbers", and Table 4.7-2 associated Bases by changing the Bases 3/4.7.8 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 69 1122 Section 3/4.3.2 Amendment 69 revises T/S 3/4.3.2 Section 3/4.7.6 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 Amendment 70 revises T/S 3/4.7.12, Table 3.7-4 Table 3.7-4 and associated Bases, Bases 3/4.7.12 "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 Amendment 72 revises T/S in order to Section 4.2.2.2 implement relaxed axial offset control Section 4.2.2.3 (RAOC) for Cycle 6 at Callaway. The Section 4.2.2.4 RAOC methodology supporting this Section 6.9.1.9 proposed change is consistent with Table 2.2.1 WCAP-10216-PA which has been Bases 3/4.2.1 previously reviewed and approved by the NRC.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 73 1134 Section 4.3.1.1 Amendment 73 grants a one-time only Table 4.3-1 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 75 1089 Section 3.6.1.2 Amendment 75 revises the ACTION Section 4.6.1.2.b statement in T/S 3.6.1.2 and the Bases 3/4.6.1.2 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 Amendment 76 revises Technical Figures 3.4-2 Specification Section 4.4.9.1.2, Figures 3.4-3 Figures 3.4-2, 3.4-3, and 3.4-4, Tables Figures 3.4-5 4.4-5 and B 3/4.4-1 and associated Tables 4.4-5 Bases for Reactor Coolant System Tables B 3/4.4-1 Pressure/Temperature Limits by Bases 3/4.4.9 modifying plant heatup and cooldown curves and the maximum allowable PORV setpoint curve for cold overpressure protection.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 77 1129 Section 4.6.1.2.a Amendment 77 changes the Technical Bases 3/4.6.1.2 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 Amendment 78 changes the Technical Section 4.0.4 Specifications 4.0.3, 4.0.4 and their Bases 4.0.3 associated bases to incorporate Bases 4.0.4 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Amendment 81 revises Technical Bases 3/4.9.7 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, Amendment 82 revises Technical Figure 3.9-1 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 Amendment 83 revises Technical Section 3.4.9.3 Specifications 3/4.4.4 and its Bases 3/4.4.4 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 84 1141 Tables 2.2-1 Amendment 84 revises Technical Tables 4.3-1 Specification Tables 2.2-1 and 4.3-1 Bases 3/4.2.2 and associated Bases 3/4.2.2 and Bases 3/4.2.3 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 Amendment 85 revises Technical Section 3/4.8.1 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 Amendment 86 revises various Table 3.3-10 Technical Specifications to reflect Section 3.3.3.6 editorial and typographical changes for Section 3.6.4.1 consistency and clarity. The changes Section 3.11.2.5 include trip setpoint corrections, Section 6.2.2 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.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 89 1143 Section 1.18 Amendment 89 changes the submittal Section 3.11.1.4 frequency for the Radioactive Effluent Section 3.11.2.6 Release Report from semi-annually to Section 6.9.1.7 annually. This change also makes the Section 6.14 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 Amendment 91 (tracked as O.L. 1150)
Bases 3/4.5.1 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.
- 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 Amendment 93 (tracked as O.L.
Bases 2.2.1 #1146), "Undervoltage-Reactor Coolant Pumps," revised to correct total allowance (undervoltage relay span) and allowable value (voltage) expressions.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT Revision by NRC NA Bases 2.2.1 This letter of 10/28/94 (see letter of 10/28/94 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 Amendment 94 (tracked as O.L.
Table 4.3-1 #1127) revises Technical Specification Bases B 2-8 Table 3.3-1 and 4.3-1, and Bases Bases B 3/4 4-1 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.
- 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revises T/S Bases 3/4.6.1.2 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 This amendment revises T/S 3/4.8.2.1, Section 3/4.8.2.2 3/4.8.2.2, 3/4.8.3.1, and 3/4.8.3.2.
Section 3/4.8.3.1 The changes address the 125-volt DC Section 3/4.8.3.2 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 This amendment revises T/S 3/4.8.1.1 Section 3/4.8.1.2 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 101 1154 Section 4.2.2.2 Revises T/S 4.2.2.2, 4.2.2.4, and Section 4.2.2.4 6.9.19. The changes incorporate a Section 6.9.19 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 Amendment 102 (tracked as OL 1167)
Table 2.2-1 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 This amendment revises T/S to ULNRCs 3023 and implement the NRCs Final Policy 3184. Statement on Technical Specification Improvements for Nuclear Power Reactors.
104 1165 Section 3.3.1 Amendment 105 revises T/S 3.3.1 and Table 3.3-2 T/S 3.3.2 to relocate T/S Tables 3.3-2 Table 3.3-5 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 105 1169 Section 4.1.1.1.1 This amendment revises T/S 4.1.3.1.2, Section 4.1.1.2 4.4.6.2.2.b, 4.4.3.2, 4.6.2.1.d, 4.6.4.2, Section 4.1.3.1.2 and Table 4.3-3 to implement the Section 4.4.6.2.2.b recommendations of NRC Generic Section 4.4.3.2 Letter 93-05, Line Item Technical Section 4.6.2.1.d Specification Improvements to Reduce Section 4.6.4.2 Surveillance Requirements for Testing Table 4.3-3 During Power Operations.
Bases 3/4.1.3 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 The amendment revises T/S 6.5.1, Section 6.5.1 6.5.2, and 6.5.3 to relocate the review Section 6.5.2 and audit requirements of the On-Site Section 6.5.3 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT Revision by NRC NA Bases2.1.1 Bases 2.1.1, Safety Limits Reactor letter dated 2/1/ Section 3/4.3.3.6 Core, Bases 3/4.3.3.6, Accident 96 Section 3/4.6.1.4 Monitoring Instrumentation, Bases 3/
Section 3/4.1.1.3 4.6.1.4, Internal Pressure (all tracked Section 3/4.9.4 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 Amendment 108 (tracked as OL 1162)
Section 4.6.1.2.1 revises TS 4.3.2.2, TS 4.7.1.2.1, and Bases 3/4.7.1.2 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 Amendment 109 (tracked as OL 1171)
Section 5.6.1.1 revises TS 5.3.1 to reflect a change in Figure 3.9-1 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 111 1172 Section 1.7 Amendment 111 (tracked as OL 1172)
Section 4.6.1.1 revises T/S 1.7, 4.6.1.1, 3.6.1.3, Section 3.6.1.3 4.6.1.3, 6.8.4 and the associated Section 4.6.1.3 Bases section to directly reference Section 6.8.4 Regulatory Guide 1.163 as required by Bases 3/4.6.1.1 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 Amendment 112 revises T/S 3/4.8.1 Bases 3/4.8 and its associated Bases to improve overall emergency diesel generator reliability and availability.
113 1153 Section 1.7 Amendment 113 revises the allowed Section 3/4.6.1 outage times for component cooling Section 3/4.6.3 water motor operated containment Bases 3/4.6.2.3 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 Amendment 114 (O.L. 1173) revises T/
Bases 3/4.9.1 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 Modification to reduce the single FSAR 10.4.7 failure trip potential for the main FSAR 10.4.7.2.2 feedwater control and bypass valves.
FSAR Fig. 7.2-1 (513
& 514) 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 Amendment 118 (O.L. 1182) revises Section 3/4.9.13 the surveillance requirements of Bases 3/4.7.7 Technical Specifications 3/4.7.7, 3/
Bases 3/4.9.13 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 Amendment 120 (O.L. 1179) revises 1.A 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 Amendment 122 revises the title Section 6.2 Senior Vice President, Nuclear to Section 6.6 Vice President and Chief Nuclear Section 6.7 Officer due to the elimination of the Vice President, Nuclear Operations position.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 123 1184 Table 3.3-3 Correct the # of MSFIS channels listed Table 4.3-2 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 This amendment modifies the plant Figures 3.4-3 heatup and cooldown curves and the Figures 3.4-4 maximum allowable PORV setpoints Bases 3/4.4.9 for cold overpressure protection.
Bases 3/4.5.2 125 1174 Table 2.2-1 This amendment modifies setpoint and Table 4.3-1 allowable values of certain reactor trip Table 3.3-4 system (RTS) and engineered safety Bases 2.2.1 features actuation system (ESFAS) function units.
126 1189 Table 3.3-3 This amendment revises the feedwater Table 3.3-4 isolation engineered safety feature Table 4.3-2 actuation system (ESFAS) functions.
Bases 3/4.3.1 127 1195 Section 4.5.2b.1 This amendment eliminates the Bases 3/4.5.2 requirement to vent the centrifugal charging pump casings.
128 1186 Table 3.7-2 This amendment revises the lift setting Table 2.2-1 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 Spent Fuel Pool Rerack Amendment.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 130 1193 Table 3.3-3 This amendment revises the Table 3.3-4 engineered safety features actuation Table 4.3-2 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 This amendment revises operability Section B 3/4 7-3 requirements to require four Section B 3/4 7-3a atmospheric steam dump (ASD) lines to be operable.
132 1180 Section 4.4.5.4 This amendment allows the repair of Section 4.4.5.5 Callaway Plant, Unit 1 steam Table 4.4-3 generator tubes with the Electrosleeve Bases 3/4.4.5 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 This amendment corrected 14 errors in 1.1 Definition the ITSs that were issued in amendment (ACTIONS ) 133.
(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 28 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 136 1198 LCO 3.7.1 This amendment revises LCO 3.7.1 in ACTION 3.7.1 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 This amendment expanded the range SR 3.3.2.14 of acceptable lift settings and tolerance Table 3.3.2-1 of the as-found, measured lift settings LCO 3.4.10 for the pressurizer safety valves SR 3.4.10.1 (PSVs) to be considered operable.
CONDITION 3.4.11.A Following testing, the as-left lift CONDITION 3.4.11.B 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 This amendment allows containment COMPLETION TIME penetrations with direct access to the 3.8.3.E.2 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revised Technical ACTION 3.5.5.A Specification 3.5.5 to remove the SR 3.5.5.1 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 The amendment revised Surveillance SR 3.3.1.3 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 149 1221 ACTIONS 3.3.1.G This amendment revised several of the ACTIONS 3.3.1. I Required Actions in the Technical ACTIONS 3.3.9.B Specifications that require suspension LCO 3.4.5 Note of operations involving positive ACTIONS 3.4.5.D reactivity additions or suspension of LCO 3.4.6 Note operations involving reactor coolant ACTIONS 3.4.6.B system (RCS) boron concentration LCO 3.4.7 Notes reductions. In addition, the ACTIONS 3.4.7.B amendment revised several Limiting LCO 3.4.8 Notes Condition for Operation (LCO) Notes ACTIONS 3.4.8.B that preclude reductions in RCS boron ACTIONS 3.8.2.B concentration. The Required Actions ACTIONS 3.8.8.A and LCO Notes were revised to allow ACTIONS 3.8.5.A small, controlled, safe insertions of ACTIONS 3.8.10.A positive reactivity, but limits the ACTIONS 3.9.3.A introduction of positive reactivity such LCO 3.9.5 Note that compliance with the required ACTIONS 3.9.5.A shutdown margin or refueling boron ACTIONS 3.9.6.B 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 This amendment revised Technical ACTIONS 3.5.5.A Specification 3.5.5 to replace the flow SR 3.5.5.1 and differential pressure limits that Figure 3.5.5-1 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 The amendment revised Technical Table 3.3.1-1 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 152 1218 ACTIONS 3.3.6.C This amendment revised the Limiting Table 3.3.6-1 Conditions for Operation (LCO's),
ACTIONS 3.3.7.E Required Actions for LCO's SR 3.3.7.6 Surveillance Requirements, and Table 3.3.7-1 Tables specifying requirements on ACTIONS 3.3.8.A instrumentation in Technical ACTIONS 3.3.8.B Specification 3.3.6, Technical ACTIONS 3.3.8.C Specification 3.3.8, and Technical LCO 3.9.4.a Specification 3.9.4. This amendment LCO 3.9.4.b allows the equipment hatch and the SR 3.9.4.2 emergency air lock to be open in SR 3.9.4.3 refueling outages during core alterations and/or movement of irradiated fuel within containment.
153 1216 Section 5.5.9.d.1.j)2) The amendment revised paragraph 1235 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 155 1241 Section 5.1.1 This amendment revised paragraphs Section 5.2.1 in Section 5.0, "Administrative Section 5.2.2 Controls," to allow the use of generic Section 5.3.1.2 personnel titles in place of plant-Section 5.5.1 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 This amendment revised Technical TABLE 3.3.1-2 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 34 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 159 1226 Section 1.0 This amendment 1) revised the SR 3.7.3.1 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 The amendment 1) revised Technical Section 5.5.16 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 35 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 162 1228 SR 3.8.1.10 This amendment revised several SR 3.8.1.11 surveillance requirements (SRs) in TS SR 3.8.1.12 3.8.1 on alternating current sources for SR 3.8.1.13 plant operation. The revised SRs have SR 3.8.1.14 notes deleted or modified to adopt in SR 3.8.1.16 part the Staff-approved TSTF-283, SR 3.8.1.17 Revision 3, which will allow these SR 3.8.1.18 revised SRs to be performed, or SR 3.8.1.19 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 This amendment modifies the TS SR 3.0.4 requirements for MODE change limitations APPL 3.1.1 in Limiting Condition for Operation (LCO)
ACTION 3.1.1.C 3.0.4 and Surveillance Requirement (SR)
ACTION 3.3.2.O 3.0.4 to adopt the provisions of TSTF-ACTIONS Note 3.3.3 359, Increase Flexibility in Mode ACTIONS Note 3.3.4 Restraints. This change also deletes ACTIONS 3.4.8 or revises notes in individual TSs that ACTIONS Note are associated with the changes to 3.4.11 LCO 3.0.4 and SR 3.0.4 above.
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 36 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 165 1205 ACTIONS 3.3.1.D This amendment revised required ACTIONS 3.3.1.E actions far certain action conditions; ACTIONS 3.3.1.M increase the completion times for ACTIONS 3.3.1.O several required actions (including ACTIONS 3.3.1.P some notes); delete notes in certain ACTIONS 3.3.1.Q required actions; increase frequency ACTIONS 3.3.1.R time intervals (including certain notes)
ACTIONS 3.3.1.W in several surveillance requirements ACTIONS 3.3.1.X (SRs); add an action condition and SR 3.3.1.4 required actions; revise notes in SR 3.3.1.5 certain SRs; and revise Table 3.3.2-1.
SR 3.3.1.7 These change were made to adopt the SR 3.3.1.8 completion time, test bypass time, and ACTIONS 3.3.2.C surveillance time interval changes in ACTIONS 3.3.2.D NRC-approved W CAP-14333-P-A, ACTIONS 3.3.2.E "Probabilistic Risk Analysis of the RPS ACTIONS 3.3.2.G [reactor protection system] and ESFAS ACTIONS 3.3.2.I Test Times and Completion Times,"
ACTIONS 3.3.2.K and WCAP-15376-P-A, "Risk-Informed ACTIONS 3.3.2.M Assessment of the RTS and ESFAS ACTIONS 3.3.2.N Surveillance Test Intervals and ACTIONS 3.3.2.O Reactor Trip Breaker Test and ACTIONS 3.3.2.S Completion Times." In addition, an SR 3.3.2.2 administrative correction to the format SR 3.3.2.3 of the TSs.
SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 TABLE 3.3.2-1 SR 3.3.9.3 166 1254 Section 5.6.1 This amendment eliminated the Section 5.6.4 requirements in Technical Specification to submit monthly operating reports and annual occupational radiation exposure reports.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 167 1252 All Sections of Revises TS 3.7.3, to adopt the TS 3.7.3 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 The amendment is to support the Section 1.1 installation of replacement steann Figure 2.1.1-1 generators (SGs) atCallaway during ACTIONS 3.3.1.W the refueling outage in the fall of 2005.
Table 3.3.1-1 The amendment also revises (1 ) the ACTIONS 3.3.2.M affected transient analyses such as an Table 3.3.2-1 excessive increase in secondary LCO 3.4.1 steam flow event, loss of normal SR 3.4.1.1 feedwater event, tra.nsient mass and SR 3.4.1.2 energy releases, radiological SR 3.4.5.2 consequences of 'associated events, SR 3.4.6.2 and containment pressure/
LCO 3.4.7 temperature responses; and (2) the SR 3.4.7.2 nuclear steam and s~upply system LCO 3.4.13 (NSSS) design parameters and ACTION 3.4.13.A transients, and fatigue usage factors ACTION 3.4.13.B and stresses for the replacement SGs.
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 38 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revises the stroke SR 3.7.3.2 time test requirement for the MFIVs by SR 3.7.3.3 replacing the single-value 15-second Figure 3.7.3-1 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 The amendment revises Required ACTION 3.6.6.E 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 172 1262 LCO 3.7.2 This amendment revised TS 3.7.2 by ACTION 3.7.2.A adding the MSIV actuator trains to (1)
ACTION 3.7.2.B the limiting condition for operation ACTION 3.7.2.C (LCO) and (2) the conditions, rrequired ACTION 3.7.2.D actions, and completion times for the ACTION 3.7.2.E LCO. The existing conditions, required ACTION 3.7.2.F actions in TS 3.7.2 were renumbered ACTION 3.7.2.G to account for the new conditions and ACTION 3.7.2.H required actions.
ACTION 3.7.2.I 173 1267 Section 5.1.2 This amendment revises Technical Section 5.2.2.c Specification (TS) 5.0, "Administrative Section 5.2.2.d Controls", by removing references to Section 5.2.2.f the specific position title "Shift Section 5.3.1.1 Supervisor" and replacing it with a new Section 5.7.2.a.1 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) The amendment adds a new TS 3.1.9, ACTION 3.3.1.V "RCS [Reactor Coolant System] Boron ACTION 3.3.1.Y Limitations <500°F," and revises TS ACTION 3.3.1.Z 3.3.1, "Reactor Trip System (RTS)
TABLE 3.3.1-1 Instrumentation," for the power range neutron flux - low reactor trip function.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 175 1246 LCO 3.4.15 The amendment revises Technical ACTIONS 3.4.15.B Specification (TS) 3.4.1 5 , "RCS ACTIONS 3.4.15.C [Reactor Coolant System] Leakage ACTIONS 3.4.15.D Detection Instrumentation" to delete ACTIONS 3.4.15.E the containment atmosphere gaseous ACTIONS 3.4.15.F radioactivity monitor from TS 3.4.1 5 SR 3.4.15.1 and revise the existing conditions, SR 3.4.15.2 required actions, completion times, SR 3.4.15.4 and surveillance requirements in TS 3.4.1 5 to account for the monitor being deleted.
176 1255 SR 3.7.2.1 This amendment revised TS SR 3.7.3.1 Surveillance Requirements 3.7.2.1, SR 3.7.3.3 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 This amendment revised (1) the Section 5.6.6 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 178 1257 Section 1.1 This amendment revised Technical LCO 3.4.16 Specifications (TSs) 1.1, "Definitions,"
APP 3.4.16 and 3.4.16, "RCS [Reactor Coolant ACTION 3.4.16.A System] Specific Activity" to replace ACTION 3.4.16.B the current Limiting Condition for ACTION 3.4.16.C Operation (LCO) 3.4.16 limit on RCS SR 3.4.16.1 gross-specific activity with limits on FIG 3.4.16-1 (Del) 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 The amendment revises the Technical LCO 3.0.8 (New) 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 This amendment revised Technical SR 3.6.7.1 Specification Surveillance SR 3.6.7.2 Requirements (SR) 3.5.2.8, SR Appendix C 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 181 1238 ACTION 3.3.9.B The amendment deletes reference to ACTION 3.3.9.C specific isolation valves in the LCO 3.9.2 chemical and volume control system SR 3.9.2.1 (CVCS) and modifies notes to allow exceptions for decontamination activities and for CVCS resin vessel operation.
182 1268 ACTION 3.1.7.A The amendment revises TSs 3.1.7, ACTION 3.1.7.B "Rod Position Indication," 3.2.1, "Heat ACTION 3.1.7.C Flux Hot Channel Factor (FQ(Z)) (F, SR 3.2.1.2 Methodology)," 3.2.4, "Quadrant SR 3.2.4.2 Power Tilt Ratio (QPTR)," and 3.3.1, SR 3.3.1.3 "Reactor Trip System (RTS)
SR 3.3.1.6 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 This amendment relocated cycle-Figure 2.1.1-1 (Del) specific parameter limits from TS to the Table 3.3.1-1 Core Operating Limits Report (COLR) 3.4.1 LCO and added several topical reports and SR 3.4.1.1 allowed all cited topical reports to be SR 3.4.1.2 identified by tile and number only.
SR 3.4.1.4 These change are consistent with Section 5.6.5 TSTF-339 and TSTF-363.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 184 1259 ACTION 3.7.10.D.1 The amendment deletes Required ACTION 3.7.11.C.1 Action D.1.2 in TS 3.7.1 0, Control ACTION 3.7.13.A Room Emergency Ventilation System ACTION 3.7.13.D (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 This amendment revises TS 3.8.3, SR 3.8.3.1 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 This amendment revised the TSs to ACTION 3.8.1.B.4 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revised TS 3.4.10, ACTION NOTE Pressurizer Safety Valve, TS 3.4.11, ACTION 3.4.11.F.1 Pressurizer Power Operated Relief ACTION 3.4.12.G.1 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 The amendment revised the exception SR 3.7.2.1 in TS Table 3.3.2-1 for the main SR 3.7.2.2 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 190 1287 3.7.10 LCO Note The amendment adds a new license ACTIONS 3.7.10.A condition on the control room envelope ACTIONS 3.7.10.B (CRE) habitability program, revises the ACTIONS 3.7.10.E TS requirements related to the CRE SR 3.7.10.2 habitability in TS 3.7.10, "Control SR 3.7.10.4 Room Emergency Ventilation System SECTION 5.5.17 (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 This amendment revised the TSs to ACTION 3.8.1.B.4 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 This amendment (1) deletes MODES 5 Table 3.3.7-1 and 6 from the Control Room 3.3.8 ACTION Notes Emergency Ventilation System and its 3.7.10 APPLICABILITY actuation instrumentation in TS 3.7.10 ACTION 3.7.10.D and TS 3.3.7; (2) adopts NRC-ACTION 3.7.10.E approved Technical Specification Task 3.7.13 ACTION Note Force (TSTF) change traveler TSTF-3.8.2 APPLICABILITY 36-A for TSs 3.3.8, 3.7.13, 3.8.2 ACTION Note 3.8.2,3.8.5,3.8.8, and 3.8.10; and (3) 3.8.5 APPLICABILITY adds a restriction to the Limiting 3.8.5 ACTION Note Condition for Operation (LCO) 3.8.8 APPLICABILITY applicability for TSs 3.8.2, 3.8.5, 3.8.8, 3.8.8 ACTION Note and 3.8.10 such that these LCOs apply 3.8.10 APPLICABILITY not only during MODES 5 and 6, but 3.8.10 ACTION Note also during the movement of irradiated fuel assemblies regardless of the MODE in which the plant is operating.
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revises the battery SR 3.8.4.5 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment made the following Table 3.3.2-1 changes. 1) Revised TS 3.7.2, "Main LCO 3.7.2 Steam Isolation Valves (MSIVs)," to Applicability 3.7.2 add the main steam isolation valve ACTIONS 3.7.2.E bypass valves and main steam low ACTIONS 3.7.2.H point drain isolation valves to the ACTIONS 3.7.2.H.1 scope of the TS 3.7.2; 2) Revise ACTIONS 3.7.2.H.2 footnotes (i) and (k) in TS Table 3.3.2-ACTIONS 3.7.2.I 1, to make the Applicability of TS Table ACTIONS 3.7.2.I.1 3.3.2-1 consistent with the Applicability ACTIONS 3.7.2.I.2 of TS 3.7.2; and 3) Add new TS 3.7.19, ACTIONS 3.7.2.J "Secondary System Isolation Valves ACTIONS 3.7.2.J.1 (SSIVs)," Correspondingly, add new ACTIONS 3.7.2.J.2 Function 10 in TS Table 3.3.2-1.
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) 48 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 198 1289 Table 3.3.2-1 This amendment made the following LCO 3.7.3 changes. 1) Revised TS 3.7.3 so that Applicability 3.7.3 the LCO and Applicability more ACTIONS 3.7.3.C.1 accurately reflect the conditions for ACTIONS 3.7.3.C.2 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 The amendment deletes the TS ACTIONS 3.3.3.D requirements for the containment ACTIONS 3.3.3.E hydrogen recombiners and relaxed the ACTIONS 3.3.3.F requirements for hydrogen and oxygen ACTIONS 3.3.3.G monitoring. The TS changes would SR 3.3.3.1 support implementation of the TABLE 3.3.3-1 revisions to Title 10 of the Code of SPEC 3.6.8 (Del) Federal Regulations (10 CFR) Section ACTIONS 3.7.4.D 50.44, "Combustible gas control for ACTIONS nuclear power reactors," that became 3.7.4.D.1ACTIONS effective on October 16, 2003. In 3.8.1.A.2 addition, the amendment corrected ACTIONS 3.8.1.C.1 four typographical errors in the TSs.
Section 5.5.16 Section 5.6.3 Section 5.6.8 200 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 201 09-0039 ACTIONS 3.3.2.J The amendment revises TS 3.3.2, ACTIONS 3.3.2.M "Engineered Safety Feature Actuation ACTIONS 3.3.2.O System (ESFAS) Instrumentation," to ACTIONS 3.3.2.Q provide a 24-hour Completion Time (CT)
Table 3.3.2-1 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 202 SR 3.1.1.1 The amendment revised the TSs by SR 3.1.2.1 relocating specific surveillance SR 3.1.4.1 frequencies to a lCallaway controlled SR 3.1.4.2 program with the guidance of Nuclear SR 3.1.5.1 Energy Institute (NEI) 04-10, "Risk-SR 3.1.6.2 Informed Technical Specifications SR 3.1.6.3 Initiative 5b, Risk-Informed Method for SR 3.1.8.2 Control of Surveillance Frequencies."
SR 3.1.8.3 This amendment adopts NRC-approved SR 3.1.8.4 Technical Specification Task Force SR 3.1.9.1 (TSTF)-425, Revision 3, "Relocate SR 3.2.1.1 Surveillance Frequencies to Licensee SR 3.2.1.2 Control - RITSTF [Risk-Informed TSTF]
SR 3.2.2.1 Initiative 5b." When implemented, TSTF-SR 3.2.3.1 425 relocates most periodic frequencies SR 3.2.4.1 of TS surveillances to a licensee-SR 3.2.4.2 controlled program, the Surveillance SR 3.3.1.1 Frequency Control Program (SFCP),
SR 3.3.1.2 and provides requirements for the new SR 3.3.1.3 program in the Administrative Controls SR 3.3.1.4 section of the TSs.
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 51 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 52 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 53 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 54 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 55 A140.0001
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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 204 10-0036 SR 3.3.8.6 The amendment adds new Table 3.3.8-1 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) The amendment transitions the Operating License C(5) Callaway fire protection program to a Section 5.4.1 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 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 This amendment revised TS 3.7.9, SR 3.7.9.3 "Ultimate Heat Sink (UHS)," to SR 3.7.9.4 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 The amendment revises TS SR 3.7.13.1 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 210 13-0003 Table 3.3.1-1 The amendment revises TS 3.4.12, 3.4.12 LCO "Cold Overpressure Mitigation System 3.4.12 LCO Notes (COMS)," to reflect the mass input ACTIONS 3.4.12.B transient analysis that assumes an ACTIONS 3.4.12.B.1 Emergency Core Cooling System SR 3.4.12.2 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 The amendment adds a new pipe SP TBL 3.6-2 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 212 NA Emergency Action The amendment revises Callaways Level (EAL) 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 This amendment revised the TS SR 3.4.7.4 requirements to address NRC Generic SR 3.4.8.3 Letter 2008-01, Managing Gas SR 3.5.2.2 Accumulation in Emergency Core SR 3.5.2.3 Cooling, Decay Heat Removal, and SR 3.6.6.1 Containment Spray Systems as SR 3.6.6.9 described in Technical Specification SR 3.9.5.2 Task Force (TSTF) Traveler TSTF-SR 3.9.6.3 523, 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 This amendment revised the TS 3.4.17 ACTION A requirements to adopt TSTF-510, SR 3.4.17.2 Revision to Steam Generator Section 5.5.9 Program Inspection Frequencies and Section 5.6.10 Tube Sample Selection 216 15-0005 2.1.1.1 LCO This amendment revise the TS Section 5.6.5.b 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 218 16-0001 FSAR SP Appendix 3A This amendment revises the FSAR SP 8.3.1.1.2 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 This amendment adds a new TS 2.C.(18) 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 221 18-0025 TS SR 3.3.2.6 This amendment revises TS Table TS SR 3.3.2.14 3.3.2-1 Function 5.a and relocates TS TS TBL 3.3.2-1 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 This amendment deletes TS AC 5.5.8, TS SR 3.4.10.1 "Inservice Testing Program," and TS SR 3.4.11.1 revises TS SR 3.4.10.1, TS SR TS SR 3.5.2.4 3.4.11.2, TS SR 3.5.2.4, TS SR TS SR 3.6.3.5 3.6.3.5, TS SR 3.6.6.4, TS SR 3.7.1.1, TS SR 3.6.6.4 TS SR 3.7.2.1, TS SR 3.7.2.3, TS SR TS SR 3.7.1.1 3.7.3.1, TS SR 3.7.3.3, TS SR 3.7.4.1, TS SR 3.7.2.1 TS SR 3.7.4.2, and TS SR 3.7.19.1, by TS SR 3.7.2.3 replacing TS AC 5.5.8, "Inservice TS SR 3.7.3.1 Testing Program" with a new term TS SR 3.7.3.3 "INSERVICE TESTING PROGRAM" TS SR 3.7.4.1 defined in TS 1.1 as per TSTF-545, TS SR 3.7.4.2 Rev. 3.
TS SR 3.7.19.1 TS AC 5.5.8 223 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 This amendment revises License 2.C.(5) 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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O.L. CHANGE APPLICABLE AMENDMENT NOTICE TECHNICAL NO. NO. SPECIFICATION CONTENT 225 19-0013 TS AC 5.3.1 This amendment deletes TS AC TS AC 5.3.1.1 5.3.1.1 and TS AC 5.3.1.1 and revises TS AC 5.3.1.2 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 This amendment approves 2.C.(19) 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 This amendment revises TS Sections LCO 3.0.4 1.3, "Completion Times," and 3.0, SR 3.0.3 "LCO Applicability" and "SR Applicability." The proposed changes clarify and expand the use and application of the TS usage rules.
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