ML042040187

License Amendment Request to Support 24-month Fuel Cycles, Revised Monticello TS Pages

ML042040187
Person / Time
Site:	Monticello
Issue date:	06/30/2004
From:	Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-91-004, L-MT-04-036
Download: ML042040187 (23)

Text

ENCLOSURE 7 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST TO SUPPORT 24-MONTH FUEL CYCLES REVISED MONTICELLO TS PAGES Remove Insert Current Monticello Revised Monticello TS Page TS Page 4

4 25a 25a 49 49 52 52 60a 60a 60b 60b 61 61 62 62 63 63 102 102 105 105 127 127 129 129 131 131 132 132 156 156 167 167 168 168 169 169 203 203 229w 229w 229x 229x

4.

Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.

R.

Rated Neutron Flux - Rated flux is the neutron flux that corresponds to a steady-state power level of 1775 thermal megawatts.

S.

Rated Thermal Power - Rated thermal power means a steady-state power level of 1775 thermal megawatts.

T.

Reactor Coolant System Pressure or Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those existing in the vessel steam space.

U.

Refueling Operation and Refueling Interval - Refueling Operation is any operation when the reactor water temperature is less than 212_F and movement of fuel or core components is in progress. Refueling Interval is a designated frequency for performing surveillances of once per 24 months.

V.

Safety Limit - The safety limits are limits below which the maintenance of the cladding and primary system integrity are assured.

Exceeding such a limit is cause for plant shutdown and review by the Commission before resumption of plant operation.

Operation beyond such a limit may not in itself result in serious consequences but it indicates an operational deficiency subject to regulatory review.

W.

Secondary Containment Integrity - Secondary Containment Integrity means that the reactor building is closed and the following conditions are met:

1.

At least one door in each access opening is closed.

2.

The standby gas treatment system is operable.

3.

All reactor building ventilation system automatic isolation valves are operable or are secured in the closed position.

X.

Sensor Check - A qualitative determination of operability by observation of sensor behavior during operation. This determination shall include, where possible, comparison with other independent sensors measuring the same variable.

1.0 4

Amendment No. 17, 102

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 4.0 SURVEILLANCE REQUIREMENTS A.

The surveillance requirements of this section shall be met. Each surveillance requirement shall be performed at the specified times except as allowed in B and C below.

B.

Specific time intervals between tests may be extended up to 25% of the surveillance interval to accommodate normal test schedules.

C.

Whenever the plant condition is such that a system or component is not required to be operable the surveillance testing associated with that system or component may be discontinued. Discontinued surveillance tests shall be resumed less than one test interval before establishing plant conditions requiring operability of the associated system or component.

D.

If it is discovered that a surveillance was not performed within the extended time interval allowed by 4.0.B, then the affected equipment shall be declared inoperable.

E.

Compliance with 4.0.D may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the time interval, whichever is greater. This delay period is permitted to allow performance of the surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.

3.0/4.0 25a Amendment No. 32, 115, 127

Table 3.2.1 Instrumentation That Initiates Primary Containment Isolation Functions Function Trip Settings Total No. of Instrument Channels Per Trip System Min. No. of Operable or Operating Instru-ment Channels Per Trip System (1, 2)

Required Conditions*

1.

Main Steam and Recirc Sample Line (Group 1) a.

Low Low Reactor Water Level

-48 2

2 A

b.

High Flow In Main Steam Line 140% rated 8

8 A

c.

High temp. in Main Steam Line Tunnel 209_F 8

2 of 4 in each of 2 sets A

d.

Low Pressure in Main Steam Line (3) 825 psig 2

2 B

2.

RHR System, Head Cooling, Drywell, Sump, TIP (Group 2) a.

Low Reactor Water Level 7

2 2

C 3.2/4.2 49 Amendment No. 83, 102, 128

Table 3.2.2 Instrumentation That Initiates Emergency Core Cooling Systems Function Trip Setting Minimum No. of Operable or Operating Trip Systems (3) (6)

Total No. of Instru-ment Channels Per Trip System Minimum No. of Operable or Operating Instrument Channels Per Trip System (3) (6)

Required Conditions*

A.

Core Spray and LPCI 1.

Pump Start

a. Low Low Reactor Water Level and

-48 2

4(4) 4 A.

b. i.

Reactor Low Pressure Permissive or 450 psig 2

2(4) 2 A.

ii. Reactor Low Pressure Permissive Bypass Timer 20+/-2 min 2

1 1

B.

c. High Drywell Pressure (1) 2 psig 2

4(4) 4 A.

2.

Low Reactor Pressure (Valve Permissive) 450 psig 2

2(4) 2 A.

3.

Loss of Auxiliary Power 2

2(2) 2 A.

3.2/4.2 52 Amendment No. 62, 93, 103, 128

Table 3.2.6 Instrumentation for Safeguards Bus Degraded Voltage and Loss of Voltage Protection Function Trip Setting Minimum No. of Operable or Operating Trip Systems (1)

Total No. of Instru-ment Channels Per Trip System Minimum No. of Operable or Operating Instru-ment Channels Per Trip System (1)

Required Conditions 1.

Degraded Voltage Protection (3) 3915+/-18 volts 9+/-1 sec 1/bus 3

3 A

2.

Loss of Voltage Protection (2) 2625+/-280 volts No intentional delay 2/bus 2

2 A

NOTE:

1.

Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated to:

a.

Satisfy the requirements by placing the appropriate channels or systems in the tripped condition, or b.

Place the plant under the specified required conditions using normal operating procedures.

2.

One out of two twice logic.

3.

Two out of three logic.

• Required conditions when minimum conditions for operation are not satisfied:

A.

Cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.2/4.2 60a Amendment No. 31

Table 3.2.7 Instrumentation for Safety/Relief Valve Low-Low Set Logic Function Trip Setting Min. No. of Operable or Operating Trip Systems Total No. of Instru-ment Channels Per Trip System Min. No. of Operable or Operating Instrument Channels Per Trip System Required Conditions Reactor Scram Detection 2(2) 2 2

A or B or C Reactor Coolant System Pressure for Opening/

Closing (1) 1072+/-14 / 992+/- 14 psig 1062+/-14 / 982+/-14 psig 1052+/-14 / 972+/-14 psig 2(2) 2 2

A or B or C Discharge Pipe Pressure Inhibit and Position Indication 30+/-3 psid (3) 2(2) 2 2

A or B or C Inhibit Timers 10+/-2 sec 2(2) 2 2

A or B or C 3.2/4.2 60b Amendment No. 30, 43, 62

Table 4.2.1 Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation Instrument Channel Test (3)

Calibration (3)

Sensor Check (3)

ECCS INSTRUMENTATION 1.

Reactor Low-Low Water Level Once/3 months (Note 5)

Once/Operating Cycle - Transmitter Once/3 months -Trip Unit Once/12 hours 2.

Drywell High Pressure Once/3 months Once/3 months None 3.

Reactor Low Pressure (Pump Start)

Once/3 months Once/3 months None 4.

Reactor Low Pressure (Valve Permissive)

Once/3 months Once/3 months None 5.

Undervoltage Emergency Bus Refueling Interval Refueling Interval None 6.

Low Pressure Core Cooling Pumps Discharge Pressure Interlock Once/3 months Once/3 months None 7.

Loss of Auxiliary Power Refueling Interval Refueling Interval None 8.

Condensate Storage Tank Level Refueling Interval Refueling Interval None 9.

Reactor High Water Level Once/3 months (Note 5)

Once/Operating Cycle - Transmitter Once/3 months - Trip Unit Once/12 hours 10.

Reactor Low Pressure (Bypass Timer)

Refueling Interval Refueling Interval None 11.

Auto Blowdown Timer Refueling Interval Refueling Interval None ROD BLOCKS 1.

APRM Downscale Once/3 months (Note 5)

Once/3 months None 2.

APRM Flow Variable Once/3 months (Note 5)

Once/3 months None 3.

IRM Upscale Notes (2,5)

Note 2 Note 2 4.

IRM Downscale Notes (2,5)

Note 2 Note 2 5.

RBM Upscale Once/3 months (Note 5)

Once/3 months None 6.

RBM Downscale Once/3 months (Note 5)

Once/3 months None 7.

SRM Upscale Notes (2,5)

Note 2 Note 2 8.

SRM Detector Not-Full-In Position Notes (2,9)

Note 2 None 9.

Scram Discharge Volume-High Level Once/3 months Once/3 months None 3.2/4.2 61 Amendment No. 2, 10, 37, 39, 63, 66, 81, 103, 104

Table 4.2.1 Continued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation Instrument Channel Test (3)

Calibration (3)

Sensor Check (3)

MAIN STEAM LINE (GROUP 1) ISOLATION 1.

Steam Tunnel High Temperature Refueling Interval Refueling Interval None 2.

Steam Line High Flow Once/3 months Once/3 Months Once/12 hours 3.

Steam Line Low Pressure Once/3 months Once/3 months None 4.

Reactor Low Low Water Level Once/3 months (Note 5)

Once/Operating Cycle-Transmitter Once/3 Months-Trip Unit Once/12 hours CONTAINMENT ISOLATION (GROUP 2) 1.

Reactor Low Water Level (Note 10) 2.

Drywell High Pressure (Note 10)

RWCU ISOLATION (GROUP 3)

(Note 12) 1.

High RWCU Room Temperature Once/3 months Once/Operating Cycle-RTD Input Once/3 months-Trip Unit Once/12 hours 2.

High RWCU System Flow Once/3 months Once/Operating Cycle-Transmitter Once/3 months-Trip Unit Once/12 hours 3.

Reactor Low Low Water Level (Note 11) 4.

Drywell High Pressure (Note 10)

HPCI (GROUP 4) ISOLATION 1.

Steam Line High Flow Once/3 months Once/3 months None 2.

Steam Line High Temperature Once/3 months Once/3 months None 3.

Steam Line Low Pressure Once/3 months Once/3 months None RCIC (GROUP 5) ISOLATION 1.

Steam Line High Flow Once/3 months Once/3 months None 2.

Steam Line High Temperature Once/3 months Once/3 months None 3.

Steam Line Low Pressure Once/3 months Once/3 months None

• Function changed from Low Reactor Water Level to Low Low Reactor Water Level following completion of design change.

3.2/4.2 62 Amendment No. 15, 22, 40, 45, 63, 66, 74, 81, 83, 91, 103, 104, 117

Table 4.2.1 Continued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation Instrument Channel Test (3)

Calibration (3)

Sensor Check (3)

REACTOR BUILDING VENTILATION & STANDBY GAS TREATMENT 1.

Reactor Low Low Water Level Once/3 months (Note 5)

Once/Operating Cycle - Transmitter Once/3 months - Trip Unit Once/12 hours 2.

Drywell High Pressure (Note 10) 3.

Radiation Monitors (Plenum)

Once/3 months Once/3 months Once/day 4.

Radiation Monitors (Refueling Floor)

Once/3 months Once/3 months Note 4 RECIRCULATION PUMP TRIP AND ALTERNATE ROD INJECTION 1.

Reactor High Pressure Once/3 months (Note 5)

Once/Operating Cycle -Transmitter Once/3 Months-Trip Unit Once/Day 2.

Reactor Low Low Water Level Once/3 months (Note 5)

Once/Operating Cycle - Transmitter Once/3 Months-Trip Unit Once/12 hours SHUTDOWN COOLING SUPPLY ISOLATION 1.

Reactor Pressure Interlock Once/3 months Once/3 Months None SAFEGUARDS BUS VOLTAGE 1.

Degraded Voltage Protection Once/month Quarterly Not applicable 2.

Loss of Voltage Protection Once/month Once/Operating Cycle Not applicable SAFETY/RELIEF VALVE LOW-LOW SET LOGIC 1.

Reactor Scram Sensing Once/Shutdown (Note 8) 2.

Reactor Pressure - Opening Once/3 months (Note 5)

Once/Operating Cycle Once/day 3.

Reactor Pressure - Closing Once/3 months (Note 5)

Once/Operating Cycle Once/day 4.

Discharge Pipe Pressure Once/3 months (Note 5)

See Table 4.14.1 See Table 4.14.1 5.

Inhibit Timer Once/3 months (Note 5)

Once/3 Months CONTROL ROOM HABITABILITY PROTECTION 1.

Radiation Monthly (Note 5) 24 months Daily 3.2/4.2 63 Amendment No. 62, 63, 65, 89, 117

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.

One of the following conditions of inoperability may exist for the period specified:

a.

One Core Spray subsystem may be inoperable for 7 days, or b.

One RHR pump may be inoperable for 30 days, or c.

One low pressure pump or valve (Core Spray or RHR) may be inoperable with an ADS valve inoperable for 7 days, or d.

One of the two LPCI injection paths may be inoperable for 7 days, or e.

Two RHR pumps may be inoperable for 7 days, or f.

Both of the LPCI injection paths may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or g.

HPCI may be inoperable for 14 days, provided RCIC is operable, or h.

One ADS valve may be inoperable for 14 days, or i.

Two or more ADS valves may be inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.

If the requirements or conditions of 3.5.A.1, 2 or 3 cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be placed in a condition in which the affected equipment is not required to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

NOTE: Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

a.

Demonstrate, quarterly, with reactor pressure 1120 psig and 950 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure, when tested in accordance with the Inservice Testing Program.

b.

Demonstrate, once per operating cycle, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

4.

Perform the following tests:

Item Frequency ADS Valve Each Operating Operability Cycle NOTE: Safety/relief valve operability is verified by cycling the valve and observing a compensating change in turbine bypass or control valve position.

ADS Inhibit Each Operating Switch Operability Cycle Perform a simulated Each Operating automatic actuation test Cycle (including HPCI transfer to the suppression pool and automatic restart on subsequent Low Low reactor water level) 3.5/4.5 102 Amendment No. 77, 79, 104, 122

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D.

RCIC 1.

Except as specified in 3.5.D.2 and 3 below, the Reactor Core Isolation Cooling System (RCIC) shall be operable whenever irradiated fuel is in the reactor vessel and reactor pressure is greater than 150 psig, except during reactor vessel hydrostatic or leakage tests.

2.

RCIC may be inoperable for 14 days, provided HPCI is operable.

3.

The controls for the automatic transfer of the pump suction may be inoperable for 30 days, if the pump suction is aligned to the suppression pool.

4.

If the requirements or conditions of 3.5.D.1, 2 or 3 cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be placed in a condition in which the affected equipment is not required to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D.

RCIC 1.

NOTE: Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

a.

Demonstrate, quarterly, with reactor pressure 1120 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure, when tested in accordance with the Inservice Testing Program.

b.

Demonstrate, once per operating cycle, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.

2.

Perform a simulated automatic actuation test (including transfer to suppression pool and automatic restart on subsequent Low Low reactor water level) each refueling interval.

3.5/4.5 105 Amendment No. 27, 77, 79, 122

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 2)

Otherwise, 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 the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 212_F at least one channel of the required leakage detection instrumentation shall be operable. If all channels of both systems (Drywell Floor Drain Sump Monitoring System and drywell particulate radioactivity monitoring system) are inoperable, restore at least one channel of the required leakage detection instrumentation to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

Safety/Relief Valves 1.

During power operating conditions and whenever reactor coolant pressure is greater than 110 psig and temperature is greater than 345_F the safety valve function (self actuation) of seven safety/relief valves shall be operable (note: Low-Low Set and ADS requirements are located in Specification 3.2.H. and 3.5.A, respectively).

Valves shall be set as follows:

8 valves at 1120 psig 2.

If Specification 3.6.E.1 is not met, initiate an orderly shutdown and have reactor coolant pressure and temperature reduced to 110 psig or less and 345_F or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E.

Safety/Relief Valves 1.

a. Safety/relief valves shall be tested or replaced each refueling interval in accordance with the Inservice Testing Program.

b. At least two of the safety/relief valves shall be disassembled and inspected each refueling interval.

c. The integrity of the safety/relief valve bellows shall be continuously monitored.

d. The operability of the bellows monitoring system shall be demonstrated each operating cycle.

2.

Low-Low Set Logic surveillance shall be performed in accordance with Table 4.2.1.

3.6/4.6 127 Amendment No. 30, 62, 76, 92, 93, 114, 122, 128, 137

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS H.

Snubbers 1.

Except as permitted below, all safety related snubbers shall be operable whenever the supported system is required to be Operable.

2.

With one or more snubbers made or found to be inoperable for any reason when Operability is required, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:

a.

Replace or restore the inoperable snubbers to Operable status and perform an engineering evaluation or inspection of the supported components, or b.

Determine through engineering evaluation that the as-found condition of the snubber had no adverse effect on the supported components and that they would retain their structural integrity in the event of design basis seismic event, or c.

Declare the supported system inoperable and take the action required by the Technical Specifications for inoperability of that system.

H.

Snubbers The following surveillance requirements apply to all safety related snubbers.

1.

Visual inspections:

Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible or accessible) may be inspected independently according to the schedule determined by Table 4.6-1. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.6-1. The initial inspection interval for new types of snubbers shall be established at 24 months

+25%.

3.6/4.6 129 Amendment No. 9, 39, 45, 82, 122

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.

Functional testing of snubbers shall be conducted at least once per 24 months +25% during cold shutdown. Ten percent of the total number of each brand of snubber shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria in Specification 4.6.H.4 below, an additional ten percent of that brand shall be functionally tested until no more failures are found or all snubbers of that brand have been tested.

The representative sample selected for functional testing shall include the various configurations, operating environments, and the range of size and capacity of the snubbers.

In addition to the regular sample and specified re-samples, snubbers which failed the previous functional test shall be retested during the next test period if they were reinstalled as a safety-related snubber. If a spare snubber has been installed in place of a failed safety related snubber, it shall be tested during the next period.

If any snubber selected for functional testing either fails to lockup or fails to move (i.e. frozen in place) the cause shall be evaluated and if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested.

3.6/4.6 131 Amendment No. 9, 39, 122

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 4.

Hydraulic snubber functional tests shall verify that:

a.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

b.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

5.

For any snubbers found inoperable, an engineering evaluation or inspection shall be performed on the components which are supported by the snubbers.

The purpose of this engineering evaluation or inspection shall be to determine if the components supported by the snubbers were adversely affected by the inoperability of the snubbers in order to ensure that the supported component remains capable of meeting the designed service.

6.

The installation and maintenance records for each safety related snubber shall be reviewed once every 24 months to verify that the indicated service life will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement, or reconditioning shall be indicated in the records.

3.6/4.6 132 Amendment No. 9, 39

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS Applicability:

Applies to the operating status of the primary and secondary containment systems.

Objective:

To assure the integrity of the primary and secondary containment systems.

Specification:

A.

Primary Containment.

1.

Suppression Pool Volume and Temperature When irradiated fuel is in the reactor vessel and either the reactor water temperature is greater than 212_F or work is being done which has the potential to drain the vessel, the following requirements shall be met, except as permitted by Specification 3.5.E.2:

a.

Water temperature during normal operating shall be 90_F.

b.

Water temperature during test operation which adds heat to the suppression pool shall be 100_F and shall not be >90_F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

If the suppression chamber water temperature is >110_F, the reactor shall be scrammed immediately. Power operation shall not be resumed until the pool temperature is 90_F.

4.7 CONTAINMENT SYSTEMS Applicability:

Applies to the primary and secondary containment integrity.

Objective:

To verify the integrity of the primary and secondary containment.

Specification:

A.

Primary Containment 1.

Suppression Pool Volume and Temperature a.

The suppression chamber water temperature shall be checked once per day.

b.

Whenever there is indication of relief valve operation which adds heat to the suppression pool, the pool temperature shall be continually monitored and also observed and logged every 5 minutes until the heat addition is terminated.

c.

A visual inspection of the suppression chamber interior including water line regions and the interior painted surfaces above the water line shall be made at each refueling interval.

3.7/4.7 156 Amendment No. 63, 93

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS b.

If both standby gas treatment system circuits are not operable, 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) through (d).

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 1%

penetration.

(3) The results of laboratory carbon sample analysis shall show 5% methyl iodine penetration when tested in accordance with ASTM D3803-1989 at 30_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.

3.7/4.7 167 Amendment No. 60, 77, 94, 112

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS b.

The system shall be shown to be operable with:

(1) Combined filter pressure drop 6 inches water.

(2) Inline heater power output 18kW.

c.

The system shall be shown to be operable with automatic initiation upon receipt of the following inputs:

(a) Low Low Reactor Water Level, or (b) High drywell pressure, or (c) Reactor building ventilation plenum high radiation, or (d) Refueling floor high radiation 3.

Post Maintenance Requirements a.

After any maintenance or testing that could affect the HEPA filter or HEPA filter mounting frame leak tight integrity, the results of the in-place DOP tests at 3500 cfm (+/-10%) on HEPA filters shall show 1% DOP penetration.

b.

After any maintenance or testing that could affect the charcoal adsorber leak tight integrity, the results of in-place halogenated hydrocarbon tests at 3500 cfm (+/-10%) on charcoal adsorber banks shall show 1% penetration.

b.

Once per quarter demonstrate that the pressure drop across the combined filters of each standby gas treatment system circuit shall be measured at 3500 cfm (+/-10%) flow rate.

c.

Once per operating cycle the operability of inline heater at nominal rated power shall be verified for each standby gas treatment system.

d.

At least once per operating cycle, automatic initiation of each standby gas treatment system circuit shall be demonstrated.

3.

Post Maintenance Testing a.

After any maintenance or testing that could affect the leak tight integrity of the HEPA filters, perform in-place DOP tests on the HEPA filters.

b.

After any maintenance or testing that could affect the leak tight integrity of the charcoal adsorber banks, perform halogenated hydrocarbon tests on the charcoal absorbers.

3.7/4.7 168 Amendment No. 94

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 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 212_F.

c.

No activity is being performed which can reduce the shutdown margin below that specified in Specification 3.3.A d.

The fuel cask or irradiated fuel is not being moved within the reactor building.

3.

With 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.

4.

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 />. Alterations of the 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 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.

3.7/4.7 169 Amendment No. 3, 63, 76, 94

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 4.

Station Battery System If one of the two 125 V battery systems or one of the two 250 V battery systems is made or found to be inoperable for any reason, an orderly shutdown of the reactor shall be initiated and the reactor water temperature shall be reduced to less than 212_F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless such battery systems are sooner made operable 5.

24V Battery Systems From and after the date that one of the two 24V battery systems is made or found to be inoperable for any reason, refer to Specification 3.2 for appropriate action.

4.

Station Battery System a.

Every week the specific gravity and voltage of the pilot cell and temperature of the adjacent cells and overall battery voltage shall be measured.

b.

Every three months the measurements shall be made of voltage of each cell to nearest 0.01 volt, specific gravity of each cell, and temperature of every fifth cell.

c.

Every refueling interval, the station batteries shall be subjected to a rated load discharge test. Determine specific gravity and voltage of each cell after the discharge.

5.

24V Battery Systems a.

Every week the specific gravity and voltage of the pilot cell and temperature of adjacent cells and overall battery voltage shall be measured.

b.

Every three months the measurements shall be made of voltage of each cell to nearest 0.01 volt, specific gravity of each cell, and temperature of every fifth cell.

3.9/4.9 203 Amendment No. 3, 41

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 2.

Performance Requirements a.

Acceptance Criteria - Periodic Requirements (1) The results of the in-place DOP tests at 1000 cfm (+/-10%) shall show 1% DOP penetration on each individual HEPA filter and shall show 0.05% DOP penetration on the combined HEPA filters.

(2) The results of in-place halogenated hydrocarbon tests at 1000 cfm (+/-10%) shall show 1% penetration on each individual charcoal adsorber and shall show 0.05%

penetration on the combined charcoal banks.

(3) The results of laboratory carbon sample analysis shall show 0.5% methyl iodide penetration when tested at 30°C and 95%

relative humidity.

2.

Performance Requirement Test The in-place performance testing of HEPA filter banks and charcoal adsorber banks shall be conducted in accordance with Sections 10 and 11 of ASME N510-1989. The carbon sample test for methyl iodide shall be conducted in accordance with ASTM D 3803-1989. Sample removal shall be in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978.

a.

At least once per operating cycle, but not to exceed 24 months; or following painting, fire, or chemical release while the system is operating that could contaminate the HEPA filters or charcoal adsorbers, 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 each charcoal adsorber bank. Subject this sample to a laboratory analysis to verify methyl iodide removal efficiency.

(4) Initiate from the control room 1000 cfm (+/-10%)

flow through both trains of the emergency filtration treatment system.

3.17/4.17 229w Amendment No. 65, 101, 108, 112

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS c.

The system shall be shown to be operable with:

(1) Combined filter pressure drop 8 inches water.

(2) Inlet heater power output 5kw+/-10%.

(3) Automatic initiation upon receipt of a high radiation signal.

3.

Post Maintenance Requirements a.

After any maintenance or testing that could affect the HEPA filter or HEPA filter mounting frame leak tight integrity, the results of the in-place DOP tests at 1000 cfm (+/-10%) shall show 1% DOP penetration on each individual HEPA filter and shall show 0.05% DOP penetration on the combined HEPA filters.

b.

After any maintenance or testing that could affect the charcoal adsorber leak tight integrity, the results of in-place halogenated hydrocarbon tests at 1000 cfm (+/-10%) shall show 1% penetration on each individual charcoal adsorber and shall show 0.05% penetration on the combined charcoal adsorber banks.

c.

At least once per operating cycle, but not to exceed 24 months, the following conditions shall be demonstrated for each emergency filtration system train:

(1) Pressure drop across the combined filters of each train shall be measured at 1000 cfm

(+/-10%) flow rate.

(2) Operability of inlet heater at nominal rated power shall be verified.

(3) Verify that on a simulated high radiation signal, the train switches to the pressurization mode of operation and the control room is maintained at a positive pressure with respect to adjacent areas at the design flow rate of 1000 cfm

(+/-10%).

3.

Post Maintenance Testing a.

After any maintenance or testing that could affect the leak tight integrity of the HEPA filters, perform in-place DOP tests on the HEPA filters.

b.

After any maintenance or testing that could affect the leak tight integrity of the charcoal adsorber banks, perform halogenated hydrocarbon tests on the charcoal adsorbers.

3.17/4.17 229x Amendment No. 65, 101, 108, 112