ML18005B098: Difference between revisions

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{{#Wiki_filter:REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR)loops shall be OPERABLE, and at least one RHR loop shall be in operation.*
{{#Wiki_filter:REFUELING OPERATIONS LOW WATER   LEVEL LIMITING CONDITION     FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall                               be OPERABLE, and at least one RHR loop shall be in operation.*
APPLICABILITY:
APPLICABILITY: MODE 6, with irradiat'ed fuel in the vessel when the water                             level above the top of the reactor vessel 'flange is less than 23 feet.
MODE 6, with irradiat'ed fuel in the vessel when the water level above the top of the reactor vessel'flange is less than 23 feet.ACTZON: a.With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as soon as possible.b.With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
ACTZON:
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours'URVEILLANCE RE UIREMENTS 4.9.8.2.1 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours whenever the water level is at or above the reactor vessel flange.4.9.8.2.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 900 gpm at least once per 12 hours whenever the water level is below the reactor vessel flange.*The operating RHR loop may be removed from operation for up to 1 hour per 2-hour period during the performance of CORE ALTERATIONS and core loading verification in the vicinity of the reactor vessel hot legs'HEARON HARRIS-UNIT 1 85'i Oi 70308 8910i I p'R PDR ADOCK 05000" 3/4 9-10 Amendment No.
: a. With less than the required                 RHR loops OPERABLE,           immediately initiate corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as soon as possible.
~REFUELING OPERATIONS
: b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere   within 4 hours'URVEILLANCE RE UIREMENTS 4.9.8.2.1 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours whenever the water level is at or above the reactor vessel flange.
.BASES 3/4'.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1)refuel-ing machine will be.used for movement of drive rods and fuel assemblies, (2)each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3)the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
4.9.8.2.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 900 gpm at least once per 12 hours whenever the water level is below the reactor vessel flange.
3/4''CRANE TRAVEL-FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1)the activity release will be limited to that contained in a single fuel assembly, and (2)any possible distortion of fuel in the storage racks will not result in a critical array.This assumption is consistent with the activity release assumed in the safety analyses.3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR)loop be in opera-tion ensures that: (1)sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2)sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
*The operating   RHR loop may be removed from operation for up to 1 hour per 2-hour period during the performance of CORE ALTERATIONS and core loading verification in the vicinity of the reactor vessel hot legs'HEARON HARRIS   - UNIT 1                         3/4 9-10                            Amendment No.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a.single failure of the operating RHR loop will not result in a complete.loss of residual heat removal capability.
85'i Oi 70308 8910i I
With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling.Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange.'he 900 gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.3/4~9'CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge makeup and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment.
PDR p     ADOCK 05000"
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
                      'R
SHEARON HARRIS-UNIT 1 B 3/4 9-2 Amendment No.}}
 
~
REFUELING OPERATIONS   .
BASES 3/4 '.6   REFUELING MACHINE The OPERABILITY   requirements for the refueling machine ensure that: (1) refuel-ing machine will be .used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to     lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4 ' '   CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly   and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8   RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a .single failure of the operating RHR loop will not result in a complete .loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
The minimum RHR   flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange. 'he 900 gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.
3/4~9 '   CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY   of this system ensures that the containment purge makeup and exhaust penetrations     will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
SHEARON HARRIS UNIT 1               B 3/4 9-2                   Amendment No.}}

Latest revision as of 05:46, 22 October 2019

Proposed Tech Specs,Revising Surveillance Requirement 4.9.8.2.2 to Impose Min Flow Requirement of 900 Gpm When Reactor Water Level Below Reactor Vessel Flange
ML18005B098
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 10/11/1989
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005B097 List:
References
NUDOCS 8910170308
Download: ML18005B098 (2)


Text

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation.*

APPLICABILITY: MODE 6, with irradiat'ed fuel in the vessel when the water level above the top of the reactor vessel 'flange is less than 23 feet.

ACTZON:

a. With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as soon as possible.
b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'URVEILLANCE RE UIREMENTS 4.9.8.2.1 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is at or above the reactor vessel flange.

4.9.8.2.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 900 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is below the reactor vessel flange.

  • The operating RHR loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 2-hour period during the performance of CORE ALTERATIONS and core loading verification in the vicinity of the reactor vessel hot legs'HEARON HARRIS - UNIT 1 3/4 9-10 Amendment No.

85'i Oi 70308 8910i I

PDR p ADOCK 05000"

'R

~

REFUELING OPERATIONS .

BASES 3/4 '.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) refuel-ing machine will be .used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4 ' ' CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a .single failure of the operating RHR loop will not result in a complete .loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange. 'he 900 gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.

3/4~9 ' CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge makeup and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SHEARON HARRIS UNIT 1 B 3/4 9-2 Amendment No.