ML24191A324: Difference between revisions
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Latest revision as of 11:48, 20 June 2025
| ML24191A324 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/06/2024 |
| From: | Ameren Missouri, Union Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24191A265 | List:
|
| References | |
| ULNRC-06877 | |
| Download: ML24191A324 (1) | |
Text
CALLAWAY PLANT 3.9-i CHAPTER TABLE OF CONTENTS CHAPTER 3.9 REFUELING OPERATIONS Section Page 3.9.1 Boron Concentration........................................................................................... 3.9-1 ACTIONS........................................................................................................ 3.9-1 SURVEILLANCE REQUIREMENTS............................................................... 3.9-2 3.9.2 Unborated Water Source Isolation Valves.......................................................... 3.9-3 ACTIONS........................................................................................................ 3.9-3 SURVEILLANCE REQUIREMENTS............................................................... 3.9-4 3.9.3 Nuclear Instrumentation...................................................................................... 3.9-5 ACTIONS........................................................................................................ 3.9-5 SURVEILLANCE REQUIREMENTS............................................................... 3.9-6 3.9.4 Containment Penetrations................................................................................... 3.9-7 ACTIONS........................................................................................................ 3.9-7 SURVEILLANCE REQUIREMENTS............................................................... 3.9-8 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level............................................................................ 3.9-9 ACTIONS........................................................................................................ 3.9-9 SURVEILLANCE REQUIREMENTS............................................................. 3.9-10 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level........................................................................... 3.9-11 ACTIONS...................................................................................................... 3.9-11 SURVEILLANCE REQUIREMENTS............................................................. 3.9-12 3.9.7 Refueling Pool Water Level............................................................................... 3.9-14 ACTIONS...................................................................................................... 3.9-14 SURVEILLANCE REQUIREMENTS............................................................. 3.9-14
CALLAWAY PLANT 3.9-1 Amendment No. 164 Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of all filled portions of the Reactor Coolant System and the refueling pool that have direct access to the reactor vessel, shall be maintained sufficient to ensure that the more restrictive of the following reactivity conditions is met:
a.
A keff 0.95, or b.
A boron concentration of 2000 ppm.
APPLICABILITY:
MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Boron concentration not within limit.
A.1 Suspend CORE ALTERATIONS.
AND Immediately A.2 Suspend positive reactivity additions.
AND Immediately A.3 Initiate action to restore boron concentration to within limit.
Immediately
Boron Concentration 3.9.1 CALLAWAY PLANT 3.9-2 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.9-3 Amendment No. 181 Unborated Water Source Isolation Valves 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Unborated Water Source Isolation Valves LCO 3.9.2 Each valve used to isolate unborated water sources shall be secured in the closed position.
NOTE ---------------------------------------------
Unborated water sources may be unisolated under administrative controls for planned boron dilution evolutions.
APPLICABILITY:
MODE 6.
ACTIONS
NOTE -----------------------------------------------------------
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each unborated water source isolation valve.
CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE -------------
Required Action A.3 must be completed whenever Condition A is entered.
A.1 Suspend CORE ALTERATIONS.
AND Immediately One or more valves not secured in closed position.
A.2 Initiate actions to secure valve in closed position.
AND Immediately A.3 Perform SR 3.9.1.1.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
Unborated Water Source Isolation Valves 3.9.2 CALLAWAY PLANT 3.9-4 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated water sources is secured in the closed position.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.9-5 Amendment No. 181 l Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 Two source range neutron flux monitors shall be OPERABLE.
APPLICABILITY:
MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required source range neutron flux monitor inoperable.
A.1 Suspend CORE ALTERATIONS.
AND Immediately A.2 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
Immediately B.
Two required source range neutron flux monitors inoperable.
B.1 Initiate action to restore one source range neutron flux monitor to OPERABLE status.
AND Immediately B.2 Perform SR 3.9.1.1.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
Nuclear Instrumentation 3.9.3 CALLAWAY PLANT 3.9-6 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.9.3.2
NOTE ----------------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.9-7 Amendment No. 181 l Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:
a.
The equipment hatch closed and held in place by four bolts, or if open, capable of being closed; b.
One door in the emergency air lock and one door in the personnel air lock capable of being closed; and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
1.
closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2.
capable of being closed by an OPERABLE Containment Purge Isolation valve.
NOTE ------------------------------------------
Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.
APPLICABILITY:
During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more containment penetrations not in required status.
A.1 Suspend CORE ALTERATIONS.
AND Immediately A.2 Suspend movement of irradiated fuel assemblies within containment.
Immediately
Containment Penetrations 3.9.4 CALLAWAY PLANT 3.9-8 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is in the required status.
In accordance with the Surveillance Frequency Control Program SR 3.9.4.2
NOTE ----------------------------
Only required for an open equipment hatch.
Verify the capability to install the equipment hatch.
In accordance with the Surveillance Frequency Control Program SR 3.9.4.3 Verify each required containment purge isolation valve actuates to the isolation position on a manual actuation signal.
In accordance with the Surveillance Frequency Control Program
CALLAWAY PLANT 3.9-9 Amendment No. 181 l RHR and Coolant Circulation - High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.
NOTE ---------------------------------------------
The required RHR loop may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause introduction into the Reactor Coolant System, coolant with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1.
APPLICABILITY:
MODE 6 with the water level 23 ft above the top of reactor vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
RHR loop requirements not met.
A.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
AND Immediately A.2 Suspend loading irradiated fuel assemblies in the core.
AND Immediately (continued)
RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS CALLAWAY PLANT 3.9-10 Amendment 213 SURVEILLANCE REQUIREMENTS A.
RHR loop requirements not met.
(continued)
A.3 Initiate action to satisfy RHR loop requirements.
AND Immediately A.4 Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm.
In accordance with the Surveillance Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program CONDITION REQUIRED ACTION COMPLETION TIME
CALLAWAY PLANT 3.9-11 Amendment No. 237 RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
NOTE ---------------------------------------------
The Service Water system may serve as the alternate source of cooling water to the Essential Service Water system for support of the second required RHR train, i.e., the RHR train not supported by the emergency diesel generator required per Technical Specification 3.8.2, provided the plant is not in a reduced-inventory, hot-core condition.
APPLICABILITY:
MODE 6 with the water level < 23 ft above the top of reactor vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Less than the required number of RHR loops OPERABLE.
A.1 Initiate action to restore required RHR loops to OPERABLE status.
OR Immediately A.2 Initiate action to establish 23 ft of water above the top of reactor vessel flange.
Immediately (continued)
RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)
CALLAWAY PLANT 3.9-12 Amendment No. 202 SURVEILLANCE REQUIREMENTS B.
No RHR loop in operation.
B.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
AND Immediately B.2 Initiate action to restore one RHR loop to operation.
AND Immediately B.3 Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm.
In accordance with the Surveillance Frequency Control Program (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
RHR and Coolant Circulation - Low Water Level 3.9.6 SURVEILLANCE REQUIREMENTS (continued)
CALLAWAY PLANT 3.9-13 Amendment No. 213 SR 3.9.6.2 Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.
In accordance with the Surveillance Frequency Control Program SR 3.9.6.3 Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program SURVEILLANCE FREQUENCY
CALLAWAY PLANT 3.9-14 Amendment No. 202 Refueling Pool Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Pool Water Level LCO 3.9.7 Refueling pool water level shall be maintained 23 ft above the top of reactor vessel flange.
APPLICABILITY:
During movement of irradiated fuel assemblies within containment.
ACTIONS SURVEILLANCE REQUIREMENTS CONDITION REQUIRED ACTION COMPLETION TIME A.
Refueling pool water level not within limit.
A.1 Suspend movement of irradiated fuel assemblies within containment.
Immediately SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling pool water level is 23 ft above the top of reactor vessel flange.
In accordance with the Surveillance Frequency Control Program