ML20209A149

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Technical Specifications, Chapter 3.9, Refueling Operations
ML20209A149
Person / Time
Site: Callaway Ameren icon.png
Issue date: 11/13/2019
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20209A098 List: ... further results
References
ULNRC-06547
Download: ML20209A149 (15)
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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-i

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 COMPLETION CONDITION REQUIRED ACTION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

CALLAWAY PLANT 3.9-1 Amendment No. 164

Boron Concentration 3.9.1 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 3.9-2 Amendment No. 202

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 -----------------------------------------------------------

Separate Condition entry is allowed for each unborated water source isolation valve.

COMPLETION CONDITION REQUIRED ACTION TIME A. -------------- NOTE ------------- A.1 Suspend CORE Immediately Required Action A.3 must ALTERATIONS.

be completed whenever Condition A is entered. AND One or more valves not A.2 Initiate actions to secure Immediately secured in closed position. valve in closed position.

AND 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 /> CALLAWAY PLANT 3.9-3 Amendment No. 181

Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve that isolates unborated water In accordance sources is secured in the closed position. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-4 Amendment No. 202

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 COMPLETION CONDITION REQUIRED ACTION TIME A. One required source range A.1 Suspend CORE Immediately neutron flux monitor ALTERATIONS.

inoperable.

AND A.2 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B. Two required source range B.1 Initiate action to restore Immediately neutron flux monitors one source range inoperable. neutron flux monitor to OPERABLE status.

AND 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 /> CALLAWAY PLANT 3.9-5 Amendment No. 181 l

Nuclear Instrumentation 3.9.3 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 3.9-6 Amendment No. 202

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 COMPLETION CONDITION REQUIRED ACTION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in required ALTERATIONS.

status.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

CALLAWAY PLANT 3.9-7 Amendment No. 181 l

Containment Penetrations 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is in the In accordance required status. 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 In accordance valve actuates to the isolation position on a manual with the actuation signal. Surveillance Frequency Control Program CALLAWAY PLANT 3.9-8 Amendment No. 202

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 COMPLETION CONDITION REQUIRED ACTION TIME A. RHR loop requirements not A.1 Suspend operations that Immediately met. would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.

AND (continued)

CALLAWAY PLANT 3.9-9 Amendment No. 181 l

RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. RHR loop requirements not A.3 Initiate action to satisfy Immediately met. RHR loop requirements.

(continued)

AND A.4 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating In accordance reactor coolant at a flow rate of 1000 gpm. with the Surveillance Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-10 Amendment 213

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.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

OR A.2 Initiate action to Immediately establish 23 ft of water above the top of reactor vessel flange.

(continued)

CALLAWAY PLANT 3.9-11 Amendment No. 181 l

RHR and Coolant Circulation - Low Water Level 3.9.6 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. No RHR loop in operation. B.1 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore Immediately one RHR loop to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating In accordance reactor coolant at a flow rate of 1000 gpm. with the Surveillance Frequency Control Program (continued)

CALLAWAY PLANT 3.9-12 Amendment No. 202

RHR and Coolant Circulation - Low Water Level 3.9.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.6.2 Verify correct breaker alignment and indicated power In accordance available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.9.6.3 Verify RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-13 Amendment No. 213

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 COMPLETION CONDITION REQUIRED ACTION TIME A. Refueling pool water level A.1 Suspend movement of Immediately not within limit. irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling pool water level is 23 ft above the In accordance top of reactor vessel flange. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-14 Amendment No. 202

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