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 # 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

-- 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.

1. 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 F. Scram Discharge Volume

1. During reactor operation, the scram discharge The scram discharge volume vent and drain valves shall volume vent and drain valves shall be operable, be cycled quarterly.

except as specified below. Once per operating cycle verify the scram discharge volume vent and drain valves close within 30 seconds

2. If any scam discharge volume vent or drain valve is after receipt of a reactor scram signal and open when made or found Inoperable, the Integrity of the scram the scram is reset.

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 I mode switch is in the Refuel position) through 3.3.D above are not met, an orderly shutdown shall be I 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 83a Amendment No. 24A 145

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

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 B. Standby Gas Treatment System

1. Two separate and independent standby gas 1. Once per month, operate each train of the standby I treatment system trains shall be operable at all gas treatment system for 2 10 continuous hours times when secondary containment integrity is with the inline heaters operating.

required, except as specified in sections 3.7.B.1 .(a)

I through (d).

a. After one of the standby gas treatment system I

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 I (b).

3.7/4.7 166 Amendment No. 66, 77, 94,130 145

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 4.0 SURVEILLANCE REQUIREMENTS (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 2. Performance Requirement Tests

a. Periodic Requirements 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 (1) The results of the in-place DOP tests at operation; or once per operating cycle, but not 3500 cfm (+/- 10%) on HEPA filters shall to exceed 24 months, whichever occurs first; or show < 1% DOP penetration. following painting, fire, or chemical release in any ventilation zone communicating with the (2) The results of in-place halogenated system while the system is operating that could hydrocarbon tests at 3500 cfm (+/- 10%) on contaminate the HEPA filters or charcoal charcoal banks shall show 5 1% absorbers, perform the following:

penetration.

(1) In-place DOP test the HEPA filter banks.

(3) The results of laboratory carbon sample analysis shall show s5% methyl iodine (2) In-place test the charcoal adsorber banks penetration when tested in accordance with with halogenated hydrocarbon tracer.

ASTM D3803-1989 at 300 C, 95% relative (3) Remove one carbon test sample from the humidity. 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 167a Amendment No. 60, 77, 91,11, 1:13 145

3.0 LIMITING CONDITIONS FOR OPERATION 14.0 I _ _

SURVEILLANCE REQUIREMENTS C. Secondary Containment C. Secondary Containment

1. Except as specified in 3.7.C.2 and 3.7.C.3, 1. Secondary containment surveillance shall be Secondary Containment Integrity shall be performed as indicated below:

maintained during all modes of plant operation.

a. Secondary containment capability to maintain

2. Secondary Containment Integrity is not required at least a 1/4 inch of water vacuum under calm when all of the following conditions are satisfied: wind (u < 5 mph) conditions with a filter train flow rate of S4,000 scfm, shall be

a. The reactor is subcritical and Specification demonstrated at each refueling interval prior to 3.3.A is met. refueling. If calm wind conditions do not exist during this testing, the test data is to be

b. The reactor water temperature is below 21 2'F. corrected to calm wind conditions.

c. The fuel cask is not being moved within the b. Verification that each automatic damper I actuates to its isolation position shall be reactor building.

performed:

d. Recently irradiated fuel is not being moved within secondary containment. (1) Each refueling interval.

e. Operations with the potential for draining the (2) After maintenance, repair or replacement reactor vessel are not being performed. work is performed on the damper or its associated actuator, control circuit, or

3. Nith an Inoperable secondary containment Isolation power circuit.

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.

3.7/4.7 169 Amendment No.3, 63, 76, 91,143 145

3.0 LIMITING CONDITIONS FOR OPERATION 14.0 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:

D. Primary Containment Isolation Valves (PCIVs)

1. Operations with a potential for draining the 1. The primary containment automatic isolation valve reactor vessel. surveillance shall be performed as follows:

2. Handling of recently irradiated fuel In the

a. At least once per operating cycle the operable secondary containment. isolation valves that are power operated and automatically initiated shall be tested for

3. Movement of a fuel cask in the reactor simulated automatic initiation and closure times.

building.

b. At least once per operating cycle the primary D. Primary Containment Isolation Valves (PCIVs) system instrument line flow check valves shall be tested for proper operation.

1. During reactor power operating conditions, all Primary Containment automatic isolation valves and c. All normally open power-operated isolation all primary system instrument line flow check valves valves shall be tested in accordance with the shall be operable except as specified in 3.7.D.2 and Inservice Testing Program. Main Steam 3.7.D.3. 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.

3.7/4.7 170 Amendment No. 3,71, 77,122, 130, 1-1 145

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS B. Core Monitoring B. Core Monitoring During core alterations two SRM's shall be operable, Prior to making any alterations to the core while more one in and one adjacent to any core quadrant where fuel than two fuel assemblies are present in any reactor or control rods are being moved. For an SRM to be quadrant, the SRM's shall be functionally tested and considered operable, the following conditions shall be checked for neutron response. Thereafter, the SRM's satisfied: will be checked daily for response.

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 C. Spent Fuel Storage Pool Water Level During movement of irradiated fuel assemblies, the Verify that the spent fuel storage pool water level is spent fuel storage pool water level shall be maintained t37 feet above the bottom of the spent fuel storage 237 feet above the bottom of the spent fuel storage pool:

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 If the spent fuel storage pool water level is made or fuel assemblies, or found not to be within limits, immediately suspend mruveaierii of irradiated fuei assembiies. 2. Once every 7 days, when irradiated fuel assemblies are stored in the spent fuel storage pool.

3.10/4.10 207 Amendment No. 20,1'23, 145

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 FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.17 CONTROLCONDITIONS 3.0 UMITING ROOM HABITABILITY 4.17 CONTROL ROQM HABITABILITY Applicability: Applicability:

Applies to the control room ventilation system equipment Applies to the periodic testing requirements of systems necessary to maintain habitability. required to maintain control room habitability.

Objectives: Obje~ctiveg:

To assure the control room is habitable both under normal To verify the operability of equipment related to control room and accident conditions. habitability.

Specification: Specification:

A. Control Room Ventilation System A. Control Room Ventilation System

1. Except as specified in 3.17.A.2 and 3.17.A.3 below, both 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.

trains of the control room ventilation system shall be operable, whenever irradiated fuel isin the reactor vessel and reactor coolant temperature is greater than 21 20 F, or during movement of irradiated fuel assemblies I 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 229u Amendment No. 65-,89,104 145

3.0 LIMITING CONDITIONS FOR OPERATION l 4.0 SURVEILLANCE REQUIREMENTS I -

2.c If 2.a is not met during movement of irradiated fuel I 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 />.

I 3.c With both control room ventilation trains inoperable, during movement of irradiated fuel assemblies in the I secondary containment or activities having the potential for draining the reactor vessel then immediately suspend these activities.

B. Control Room Emergency Filtration System B. Control Room Emergency Filtration System

1. Except as specified in 3.1 7.B.1 .a through d below, two 1. At least once per month, initiate from the control room control room emergency filtration system filter trains 1000 cfm (+/- 10%) flow through both trains of the shall be operable whenever irradiated fuel is in the emergency filtration treatment system. The system shall reactor vessel and reactor coolant temperature is 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 greater than 2121F, or during movement of recently irradiated fuel assemblies in the secondary containment, I or activities having the potential for draining the reactor vessel.

3.17/4.17 229v Amendment No. 65,898-11-2 145

3.0 LIMITING CONDITIONS FOR OPERATION 14.0 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 secondary l containment, or activities having the potential for d.ini fin~nrth_ .. . .t . .asl

.Im ditYsup these activities.

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