ML18005A939

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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
ML18005A939
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 06/07/1989
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005A938 List:
References
NUDOCS 8906120039
Download: ML18005A939 (5)
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Text

ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT REFUELING OPERATIONS - LOW WATER LEVEL TECHNICAL SPECIFICATION PAGES 8906120039 890607 PDR ADOCK 05000400 0

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REFUELING OPERATIONS LQM MATER LEVEl.

LIMITING CONOITION FQR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be fn aperatfon.~

APPLICABILITY: HQQE 6, with frradfated fuel in the vessel when the water level alcove the top of the reactor vessel flange fs less than 23 feet-ACTION:

a. Wth less than the required RHR loops OPERABLE, fmmedfately initiate car rectfve actian to return the required RHR loops ta OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as saon as possible.
b. Nth na RHR loop in operation, suspend all operations involving a reduction fn bonn concentration of'he Reactor Coolant System and immediately initiate corrective actian to return the required RHk loop ta operation. Close all containment penetrations access from the containment atmosphere ta the outside providing'frect atmosphere ~ithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.9.8.2QAt 1eaet ane RNR 1aap nbe11 be verfrfee In aperntIon ana aironIetInp reactor coolant at a flow rate of greater than or equal to 2500.gpm at least anne per 12 bours/ 1o/1eoeven ge @ra/el /eve/ I'e n/ ar a/oave the reaerar ye~oel flange.

<q8~ g ~/ <f>ne QI/trop phd//k varifieJ in i/a~ va/e ai qlea/e/ '7/Tal7 af ojoernfion and &mulahg a//aa/ rb poOg/a/77 a/ /caw/ once per /2 i/oaa eo/'Tenever He eoa/er level is g/au Qd l-/aver yaSSel Xlanye, "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 ALTERATION and core loading veri ffcatfoa fn the vfcfnfty of the reactor vessel hot legs.

SHEARON HARRIS - ND 1 3/4 9 M

REFUELING OPERATIONS BASES 3/4.9. 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 assenblfes, (2) each crane has sufficient load capacity to lift a drive rad or assembly, and (3) the core internals and reactor vessel are protected fram fuel, excessive lifting force in the event they are faadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL FUEL HANOLING BUILOING The restriction on movement of loads in excess of the nominal weight of a fuel and control rad assembly and associated handling tool over other fuel assemblies in the storage pool ensures that fn the event this load is drapped: (1) the activity release will be limited to that cantained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks wi11 not result in a critical array. This assumption is consistent with the activity reIease assumed in the safety analyses.

3/4.9.8 RESIOUAL HEAT RIVAL ANO COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient caolfng capacity fs available to remove decay heat and maintain the water in the reactor vessel below 140oF as required during the REFUELING MOOE, and (2) sufficient coolant circulatfon fs maintained through the care to mfnfmfze the effect of a boron dilution incident and prevent boron stratification.

The requirement to have ~ RHR loops OPERABLE when there fs less than 23 feet of water above the reactor vessel flange ensures that a sfngIe failure of the operating RHR Iaap will nat result fn a complete lass of residual- heat removal capability. Wfth the reactor vessel head removed and at least 23 feet af water above the reactor pressure vessel flange, a large heat sink fs available for care cooling. Thus, in the event of a failure of the operating RHR Iaop, ade-quate time is provided ta initiate emergency pracedures to caol the care.

3/4.9.9 CONTAINMENT VENTILATION ISOLATION SY~

Thi OPERABILITY of this systaa ensures that the cantainment purge makeup and exhaust penetratfons will be automatfcally isolated upon detection of high radfatfoa levels within the containment. The OPERABILITY of this steN issJJ required -to restrict the release of radioactive material from the containment atmasphire to the environment.

M~ nc'P:

The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange. The 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.

SHEARQN HARRIS - UNIT 1 B 3/4 S-2

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 irradiated fuel in the vessel when the water level above the top of the reactor vessel flange is less than 23 feet.

ACTION:

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 />.

SURVEILLANCE 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 remove'd 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 />'er 2-hour period during the performance of CORE ALTERATIONS and core loading verification, in the vicinity of .the reactor vessel hot legs SHEARON HARRIS UNIT 1 3/4 9-10 Amendment No.

REFUELING OPERATIONS BASES 3/4.9.6 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'o 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 ~ 9 ~ 7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on'ovement 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 belo~ the reactor vessel flange. The 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.

3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment p'urge 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.

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