ML061180248

Tech Spec Pages for Amendment 145 Use of the Alternative Source Term for the Postulated Fuel Handling Accident

ML061180248
Person / Time
Site:	Monticello
Issue date:	04/24/2006
From:	Plant Licensing Branch III-2
To:
tam P, NRR/ADRO/DORL, 415-1451
Shared Package
ML060760284	List: ML060600572 ML061180248
References
TAC MC7596
Download: ML061180248 (14)

Text

Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation isolation And Standby Gas Treatment System Initiation Applicable Modes or Other Specified Minimum No. Total No. of Min. No. of Operable or Conditions for Which the of Operable or Instrument Operating Instrument Trip Function Must be Operating Channels Per Channels Per Trip Required Function Settings Operable or Operating

1. Trip Systems Trip System System Conditions*

1. Low Low 2 -48" Hot Shutdown, Startup, 2 2 2 (Notes 1, 2, 3) A. or B.Reactor Water Run, (a)Level 2. High Drywell <2 psig Hot Shutdown, Startup, 2 2 2 (Notes 1, 2, 3) A. or B.Pressure Sun 3. Reactor Building <100 mR/ Hot Shutdown, Startup, 2 2 2 (Notes 1, 2) A. or B.Plenum hr Run, Radiation (a), (b)Monitors 4. Refueling Floor 5100 mR/ Hot Shutdown, Startup, 2 2 2 (Notes 1, 2) A. or B.Radiation hr Run, Monitors (a), (b)(1) There shall be two operable or tripped Trip Systems for each function.

An Instrument Channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for performance of required surveillances without placing the Trip System in the tripped condition provided that at least one other OPERABLE Channel in the same Trip System is monitoring that parameter.

(2) Upon discovery that minimum requirements for the number of operable or operating Trip Systems or Instrument Channels are not satisfied nctinn -hnad he iniiatori as fLOmdn.s: 3.2/4.2 59 11/02/04 Amendment No. 10, 71, 91, 103, 128, 110 145 Notes: (cont'd)(a) With one Instrument Channel per Trip Function Inoperable:

1) For Functions 1 or 2, place the inoperable Channel or Trip System in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2) For Functions 3 or 4, place the inoperable Channel in a downscale trip condition, or place the Trip System in the tripped condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-- OR--(b) With more than one Instrument Channel per Trip Function inoperable:

1) For Functions 1 or 2, immediately satisfy the requirements by placing the appropriate Channels or Trip Systems in the tripped condition, 2) For Functions 3 or 4, immediately proceed to Note 2c-OR.-(c) If (a) or (b) cannot be met, then place the plant under the specified required conditions using normal operating procedures.

(3) Need not be operable when primary containment integrity is not required.* Required Conditions when minimum conditions for operation are not satisfied.

A. The reactor building ventilation system isolated and the standby gas treatment system operating.

B. Establish conditions where secondary containment is not required.# Other specified conditions for which the function must be operable or operating: (a) During operations with the potential for draining the reactor vessel. l (b) During movement of recently irradiated fuel assemblies in secondary containment.

3.2/4.2 59a 11/02/04 Amendment No. 103, 140 145 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS F. Scram Discharge Volume 1. During reactor operation, the scram discharge volume vent and drain valves shall be operable, except as specified below.2. If any scam discharge volume vent or drain valve is made or found Inoperable, the Integrity of the scram discharge volume shall be maintained by either: a. Verifying daily, for a period not to exceed 7 days, the operability of the redundant valve(s), or b. Maintaining the inoperable valve(s), or the associated redundant valve(s), in the closed position.

Periodically the inoperable and the redundant valve(s) may both be in the open position to allow draining the scram discharge volume.If a or b above cannot be met, at least all but one operable control rods (not including rods removed per specification 3.1 0.E or inoperable rods allowed by 3.3.A.2) shall be fully inserted within ten hours.G. Required Action 1. If Specifications 3.3.A (except when the reactor mode switch is in the Refuel position) through 3.3.D above are not met, an orderly shutdown shall be initiated and the reactor placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.3.3/4.3 F. Scram Discharge Volume The scram discharge volume vent and drain valves shall be cycled quarterly.

Once per operating cycle verify the scram discharge volume vent and drain valves close within 30 seconds after receipt of a reactor scram signal and open when the scram is reset.83a Amendment No. 24A 145 I I 3.0 LIMITING CONDITIONS FOR OPERATION 1 4.0 SURVEILLANCE REQUIREMENTS

2. If Specification 3.3.A is not met when the reactor mode switch is in the Refuel position, immediately suspend core alterations except for fuel assembly removal and immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

3.3/4.3 83b Amendment No. 145 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS I c. Whenever primary containment oxygen concentration is equal to or exceeds 4% by volume, except as permitted by 3.7.A.5.b above, within the subsequent 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period return the oxygen concentration to less than 4%by volume.d. If the requirements of 3.7.A.5 cannot be met, reduce Thermal Power to s 15% Rated Thermal Power, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.B. Standby Gas Treatment System 1. Two separate and independent standby gas treatment system trains shall be operable at all times when secondary containment integrity is required, except as specified in sections 3.7.B.1 .(a)through (d).a. After one of the standby gas treatment system trains is made or found to be inoperable with reactor water temperature

>212°F, for any reason, reactor operation is permissible only during the succeeding seven days, provided that all active components in the other standby gas treatment system are operable.

Within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following the 7 days, the reactor shall be placed In a condition for which the standby gas treatment system Is not required in accordance with Specification 3.7.C.2.(a) and (b).I I B. Standby Gas Treatment System 1. Once per month, operate each train of the standby gas treatment system for 2 10 continuous hours with the inline heaters operating.

166 Amendment No. 66, 77, 94,130 145 I 3.7/4.7 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. If both standby gas treatment system trains are not operable, with reactor water temperature

-212'F, within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) and (b).c. With one standby gas treatment system train inoperable, 1) The following activities may continue for up to 7 days: (a) Movement of recently irradiated fuel assemblies in secondary containment;(b) Movement of the fuel cask in the reactor building; and (c) Operations with the potential to drain the reactor vessel.2) After 7 days: (a) Immediately suspend movement of the fuel cask in the reactor building; and (b) Immediately place the operable standby gas treatment system train in operation, or 3.7/4.7 167 Amendment No. 60, 77, 94, 112 145 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

-4 (1) Immediately suspend movement of recently irradiated fuel assemblies in secondary containment; and (2) Immediately suspend operations with the potential to drain the reactor vessel.d. With both standby gas treatment trains inoperable immediately suspend: movement of recently irradiated fuel assemblies in secondary containment; movement of the fuel cask in the reactor building; operations with the potential for draining the reactor vessel.2. Performance Requirements

a. Periodic Requirements (1) The results of the in-place DOP tests at 3500 cfm (+/- 10%) on HEPA filters shall show < 1% DOP penetration.

(2) The results of in-place halogenated hydrocarbon tests at 3500 cfm (+/- 10%) on charcoal banks shall show 5 1 %penetration.

(3) The results of laboratory carbon sample analysis shall show s5% methyl iodine penetration when tested in accordance with ASTM D3803-1989 at 30 0 C, 95% relative humidity.2. Performance Requirement Tests a. At least once per 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; or once per operating cycle, but not to exceed 24 months, whichever occurs first; or following painting, fire, or chemical release in any ventilation zone communicating with the system while the system is operating that could contaminate the HEPA filters or charcoal absorbers, perform the following:

(1) In-place DOP test the HEPA filter banks.(2) In-place test the charcoal adsorber banks with halogenated hydrocarbon tracer.(3) Remove one carbon test sample from the charcoal adsorber in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978.Subject this sample to a laboratory analysis to verify methyl iodine removal efficiency.

13.7/4.7 1 67a Amendment No. 60, 77, 91,11, 1:13 145 3.0 LIMITING CONDITIONS FOR OPERATION 1 4.0 SURVEILLANCE REQUIREMENTS

._ .I _ _C. Secondary Containment

1. Except as specified in 3.7.C.2 and 3.7.C.3, Secondary Containment Integrity shall be maintained during all modes of plant operation.

2. Secondary Containment Integrity is not required when all of the following conditions are satisfied:

a. The reactor is subcritical and Specification 3.3.A is met.b. The reactor water temperature is below 21 2'F.c. The fuel cask is not being moved within the reactor building.d. Recently irradiated fuel is not being moved within secondary containment.

e. Operations with the potential for draining the reactor vessel are not being performed.

3. Nith an Inoperable secondary containment Isolation damper, restore the inoperable damper to operable status or isolate the affected duct by use of a closed damper or blind flange within eight hours.I C. Secondary Containment

1. Secondary containment surveillance shall be performed as indicated below: a. Secondary containment capability to maintain at least a 1/4 inch of water vacuum under calm wind (u < 5 mph) conditions with a filter train flow rate of S 4,000 scfm, shall be demonstrated at each refueling interval prior to refueling.

If calm wind conditions do not exist during this testing, the test data is to be corrected to calm wind conditions.

b. Verification that each automatic damper actuates to its isolation position shall be performed:

(1) Each refueling interval.(2) After maintenance, repair or replacement work is performed on the damper or its associated actuator, control circuit, or power circuit.169 Amendment No.3, 63, 76, 91,143 145 3.7/4.7 3.0 LIMITING CONDITIONS FOR OPERATION 1 4.0 SURVEILLANCE REQUIREMENTS I 4. a. During Run, Startup, or Hot Shutdown if Specifications 3.7.C.1 through 3.7.C.3 cannot be met, initiate a normal orderly shutdown and have the reactor in the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.And b. If Specifications 3.7.C.1 through 3.7.C.3 cannot be met, immediately suspend: 1. Operations with a potential for draining the reactor vessel.2. Handling of recently irradiated fuel In the secondary containment.

3. Movement of a fuel cask in the reactor building.D. Primary Containment Isolation Valves (PCIVs)1. During reactor power operating conditions, all Primary Containment automatic isolation valves and all primary system instrument line flow check valves shall be operable except as specified in 3.7.D.2 and 3.7.D.3.D. Primary Containment Isolation Valves (PCIVs)1. The primary containment automatic isolation valve surveillance shall be performed as follows: a. At least once per operating cycle the operable isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times.b. At least once per operating cycle the primary system instrument line flow check valves shall be tested for proper operation.

c. All normally open power-operated isolation valves shall be tested in accordance with the Inservice Testing Program. Main Steam isolation valves shall be tested (one at a time)with the reactor power less than 75% of rated.d. At least once per week the main steam-line power-operated isolation valves shall be exercised by partial closure and subsequent reopening.

170 Amendment No. 3,71, 77,122, 130, 1-1 145 3.7/4.7 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS B. Core Monitoring During core alterations two SRM's shall be operable, one in and one adjacent to any core quadrant where fuel or control rods are being moved. For an SRM to be considered operable, the following conditions shall be satisfied:

1. The SRM shall be inserted to the normal operating level. (Use of special moveable, dunking type detectors during initial fuel loading and major core alterations is permissible as long as the detector is connected into the normal SRM circuit.)2. The SRM shall have a minimum of 3 CPS with all rods fully inserted in the core except when both of the following conditions are fulfilled:

a. No more than two fuel assemblies are present in the core quadrant associated with the SRM, b. While in core, these fuel assemblies are in locations adjacent to the SRM.C. Spent Fuel Storage Pool Water Level During movement of irradiated fuel assemblies, the spent fuel storage pool water level shall be maintained 237 feet above the bottom of the spent fuel storage pool.If the spent fuel storage pool water level is made or found not to be within limits, immediately suspend mruveaierii of irradiated fuei assembiies.

B. Core Monitoring Prior to making any alterations to the core while more than two fuel assemblies are present in any reactor quadrant, the SRM's shall be functionally tested and checked for neutron response.

Thereafter, the SRM's will be checked daily for response.C. Spent Fuel Storage Pool Water Level Verify that the spent fuel storage pool water level is t37 feet above the bottom of the spent fuel storage pool: 1. Once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, during movement of irradiated fuel assemblies, or 2. Once every 7 days, when irradiated fuel assemblies are stored in the spent fuel storage pool.207 Amendment No. 20,1'23, 145 3.10/4.10 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D. The reactor shall be shutdown for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to movement of fuel within the reactor.E. Extended Core and Control Rod Drive Maintenance More than one control rod may be withdrawn from the reactor core during outages provided that, except for momentary switching to the Startup mode for interlock testing, the reactor mode switch shall be locked in the Refuel position.

The refueling interlock signal from a control rod may by bypassed after the fuel assemblies in the cell containing (controlled by) that control rod have been removed from the reactor core.3.10/4.10 208 Amendment No- 63T 145 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLAkNCE REQUIREMENTS 3.0 UMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.17 CONTROL ROOM HABITABILITY Applicability:

Applies to the control room ventilation system equipment necessary to maintain habitability.

Objectives:

To assure the control room is habitable both under normal and accident conditions.

Specification:

A. Control Room Ventilation System 1. Except as specified in 3.17.A.2 and 3.17.A.3 below, both trains of the control room ventilation system shall be operable, whenever irradiated fuel is in the reactor vessel and reactor coolant temperature is greater than 21 2 0 F, or during movement of irradiated fuel assemblies in the secondary containment or activities having the potential for draining the reactor vessel.2.a With one control room ventilation train Inoperable, restore the Inoperable train to operable status within 30 days.2.b If 2.a is not met, then be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the 30 days and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.3.17/4.17 4.17 CONTROL ROQM HABITABILITY Applicability:

Applies to the periodic testing requirements of systems required to maintain control room habitability.

Obje~ctiveg:

To verify the operability of equipment related to control room habitability.

Specification:

A. Control Room Ventilation System 1. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> check control room temperature.

229u Amendment No. 65-,89,104 145 I 3.0 LIMITING CONDITIONS FOR OPERATION l 4.0 SURVEILLANCE REQUIREMENTS I -I I I 2.c If 2.a is not met during movement of irradiated fuel assemblies in the secondary containment or activities having the potential for draining the reactor vessel then immediately place the operable control room ventilation train in operation or immediately suspend these activities.

3.a With both control room ventilation trains inoperable, restore at least one train to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.3.b If 3.a is not met, then be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.3.c With both control room ventilation trains inoperable, during movement of irradiated fuel assemblies in the secondary containment or activities having the potential for draining the reactor vessel then immediately suspend these activities.

B. Control Room Emergency Filtration System 1. Except as specified in 3.1 7.B.1 .a through d below, two control room emergency filtration system filter trains shall be operable whenever irradiated fuel is in the reactor vessel and reactor coolant temperature is greater than 2121F, or during movement of recently irradiated fuel assemblies in the secondary containment, or activities having the potential for draining the reactor vessel.B. Control Room Emergency Filtration System 1. At least once per month, initiate from the control room 1000 cfm (+/- 10%) flow through both trains of the emergency filtration treatment system. The system shall operate for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters operable.I I 3.17/4.17 229v Amendment No. 65,898-11-2 145 3.0 LIMITING CONDITIONS FOR OPERATION 1 4.0 SURVEILLANCE REQUIREMENTS

a. When one control room emergency filtration system filter train is made or found to be inoperable for any reason, restore the inoperable train to operable status within seven days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the seven days and either reduce the reactor coolant temperature to below 212 0 F or Initiate and maintain the operable emergency filtration system filter train In the pressurization mode within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b. When both filter trains of the control room emergency filtration system are inoperable, restore at least one train to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and reduce the reactor coolant water temperature to below 2120 F within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.c. With one control room emergency filtration system filter train inoperable during movement of recently irradiated fuel assemblies in the secondary containment, or activities having the potential for draining the reactor vessel, restore the inoperable train to operable status within 7 days or immediately after the 7 days initiate and maintain the operable emergency filtration system filter train in the pressurization mode or immediately suspend these activities.

d. With both control room emergency filtration system filter trains inoperable during movement of recently irradiated fuel assemblies in the secondaryl containment, or activities having the potential for d.ini fin~n rth_ .. ..t ..asl .Im ditYsup these activities.

3.17/4.17 229w Amendment No. 44-2 145