ML052780367

Technical Specifications Pages Re Implementation of 24-Month Fuel Cycles

ML052780367
Person / Time
Site:	Monticello
Issue date:	09/30/2005
From:	Stang J NRC/NRR/DLPM/LPD3
To:
stang J, NRR/DLPM, 415-1345
Shared Package
ML052700255	List: ML052700252 ML052780367
References
TAC MC3692
Download: ML052780367 (23)

Text

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 2120F 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. Safely 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, 143

3.0 LIMITING CONDITIONS FOR OPERATION J4.0 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. l 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 hours1 days <br />0.143 weeks <br />0.0329 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> and the risk impact shall be managed.

3.0/4.0 25a Amendment No. 32, 115,1-27, 143

TABLE 4.1.1 (Continued)

Note 1: Deleted.

Note 2: A sensor check shall be performed on Low reactor water level once per day. I Note 3: Perform functional test prior to every startup, and demonstrate that the IRM and APRM channels overlap at least 1/2 decade prior to every normal shutdown.

Note 4: Functional tests are not required when the systems are not required to be operable or are tripped. If tests are missed, they shall be performed prior to returning the systems to an operable status.

Note 5: A functional test of this instrument means the injection of a simulated signal Into the instrument (not primary sensor) to verify the proper instrument channel response, alarm, and/or initiating action.

3.1/4.1 33 Amendment No. 63, 81, 83, 103T143

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

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

a. Low Low Reactor Water Level 2-48" 2 2 A

b. High Flow In Main Steam Line 5140% rated 8 8 A

c. High temp. in Main Steam Line Tunnel

d. Low Pressure in Main Steam Line (3) 2

<209 0 F 825 psig 8

2 2 of 4 in each of 2 sets 2

A B

I

2. RHR System, Drywell, Sump, TIP (Group 2)

a. Low ReactorWater Level Ž7" 2 2 C I

3.2/4.2 49 Amendment No. 83, 102, 128, 140,143

Table 3.2.2 Instrumentation That Initiates Emergency Core Cooling Systems Minimum No. of Minimum No. of Operable or Total No. of Instru- Operable or Operating Operating Trip ment Channels Per Instrument Channels Required Function Trip Setting Systems (3)(6) Trip System Per Trip System (3)(6) Conditions' A. Core Spray and LPCI

1. Pump Start

a. Low Low Reactor -48" 2 4(4) 4 A.

Water Level and

b. i. Reactor Low 2 450 psig 2 2(4) 2 A.

Pressure Permissive or ii. Reactor Low 20 +/- 2 min 2 1 1 B.

Pressure Permissive Bypass Timer

c. High Drywell *2 psig 2 4(4) 4 A.

Pressure (1)

2. Low Reactor Pressure >450 psig 2 2(4) 2 A.

(Valve Permissive)

3. Loss of Auxiliary Power 2 2(2) 2 A.

3.2/4.2 52 Amendment No. 62, 93, 103, 128 ,143

Table 3.2.6 Instrumentation for Safeguards Bus Degraded Voltage and Loss of Voltage Protection Minimum No. of Operable or Minimum No. of Total No. of Instru- Operating Instru-Operable or Operating ment Channels ment Channels Per Required Function Trip Setting Trip Systems (1) Per Trip System Trip System (1) Conditions

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

2. Loss of Voltage 2625 +280 volts 2/bus 2 2 A NOTE:

Protection (2) No intentional delay I

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 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

3.2/4.2 60a Amendment No. 3X, 143

Table 3.2.7 Instrumentation for Safety/Relief Valve Low-Low Set Logic Min. No. of Min. No. of Operable or Operable or Total No. of Instru- Operating Instrument Operating Trip ment Channels Per Channels Per Trip Required Function Trip Setting Systems Trip System System Conditions Reactor Scram Detection 2(2) 2 2 A or B or C Reactor Coolant System 1072+/-+14 /992+/-+14 psig 2(2) 2 2 A or B or C Pressure for Opening/ 1062+/-14 1982+/-14 psig Closing (1) 1052 +/-14 / 972 + 14 psig Discharge Pipe Pressure 30 +/- 3 psid (3) 2(2) 2 2 A or B or C Inhibit and Position Indication Inhibit Timers 10+ 2 sec 2(2) 2 2 A or B or C 3.2/4.2 60b Amendment No. .3O-43,-62,143

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/1 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />

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 Once/3 months Once/3 months None Permissive)

5. Undervoltage Emergency Bus Refueling Interval Refueling Interval None

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

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/1 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />

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/Refueling Outage None 3.2/4.2 61 Amendment No. 2, 10, 37, 39, 63, 66, 81, 103, 104,143

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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />

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/1 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> Once/3 Months-Trip Unit 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/12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Once/3 months-Trip Unit

2. High RWCU System Flow Once/3 months Once/Operating Cycle-Transmitter Once/12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Once/3 months-Trip Unit

• 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, 10, 15, 63, 66,71, 81, 83, 91, 103, 101, 117,143

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/1 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> Once/3 months - Trip Unit l

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/Day Once/3 Months-Trip Unit

2. Reactor Low Low Water Level Once/3 months (Note 5) Once/Operating Cycle - Transmitter Once/1 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> Once/3 Months-Trip Unit 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/Operating Cycle CONTROL ROOM HABITABILITY PROTECTION

1. Radiation Monthly (Note 5) 24 months Daily 3.2/4.2 63 Amendment No. 62, 63, 65, 81, 117 43

3.0 LIMITING CONDITIONS FOR OPERATION l4.0 SURVEILLANCE REQUIREMENTS

3. One of the following conditions of inoperability may 3. NOTE: Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> exist for the period specified: after reactor steam pressure and flow are adequate to perform the test.

a. One Core Spray subsystem may be inoperable for 7 days, or a. Demonstrate, quarterly, with reactor pressure s1120 psig and >950 psig, the HPCI pump

b. One RHR pump may be inoperable for 30 days, can develop a flow rate 2 2700 gpm against a or system head corresponding to reactor pressure, when tested in accordance with the Inservice

c. One low pressure pump or valve (Core Spray or Testing Program.

RHR) may be inoperable with an ADS valve inoperable for 7 days, or b. Demonstrate, once per operating cycle, with reactor pressure s 165 psig, the HPCI pump

d. One of the two LPCI injection paths may be can develop a flow rate 2 2700 gpm against a inoperable for 7 days, or system head corresponding to reactor pressure.

e. Two RHR pumps may be inoperable for 7 days, or 4. Perform the following tests:

item Frequency

f. Both of the LPCI injection paths may be inoperable for 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, or ADS Valve Each Operating Operability Cycle

g. HPCI may be inoperable for 14 days, provided RCIC is operable, or NOTE: Safety/relief valve operability is verified by cycling the valve and observing a compensating

h. One ADS valve may be inoperable for 14 days, change in turbine bypass or control valve position.

or Each Operating ADS Inhibit

i. Two or more ADS valves may be inoperable for Switch Operability Cycle 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />. Perform a simulated Each Operating automatic actuation test Cycle

4. If the requirements or conditions of 3.5.A.1, 2 or 3 (including HPCI transfer to cannot be met, an orderly shutdown of the reactor the suppression pool and shall be initiated and the reactor shall be placed in a automatic restart on condition in which the affected equipment is not subsequent Low Low reactor I required to be operable within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. water level) 3.5/4.5 102 Amendment No. 77, 79, 101, 122,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D. RCIC D. RCIC

1. Except as specified in 3.5.D.2 and 3 below, the

1. NOTE: Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Reactor Core Isolation Cooling System (RCIC) shall after reactor steam pressure and flow are adequate be operable whenever irradiated fuel is in the reactor vessel and reactor pressure is greater than to perform the test.

150 psig, except during reactor vessel hydrostatic or leakage tests. a. Demonstrate, quarterly, with reactor pressure

<1120 psig and Ž950 psig, the RCIC pump

2. RCIC may be inoperable for 14 days, provided can develop a flow rate 2 400 gpm against a HPCI is operable. system head corresponding to reactor pressure, when tested in accordance with the Inservice

3. The controls for the automatic transfer of the pump Testing Program.

suction may be inoperable for 30 days, if the pump suction is aligned to the suppression pool. b. Demonstrate, once per operating cycle, with reactor pressure < 165 psig, the RCIC pump

4. If the requirements or conditions of 3.5.D.1, 2 or 3 can develop a now rate Ž400 gpm against a system head corresponding to reactor pressure.

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 2. Perform a simulated automatic actuation test required to be operable within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. (including transfer to suppression pool and automatic restart on subsequent Low Low reactor water level) each refueling interval. I 3.5/4.5 105 Amendment No. 2-7, 7-7, 7X, 122-,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS I

2) Otherwise, be in Hot Shutdown within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in Cold Shutdown within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

c. Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 2120 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 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in Cold Shutdown within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

E. Safety/Relief Valves E. Safety/Relief Valves

1. During power operating conditions and whenever 1. a. Safety/relief valves shall be tested or replaced reactor coolant pressure is greater than 110 psig each refueling interval in accordance with the Inservice Testing Program.

I and temperature is greater than 3450F the safety valve function (self actuation) of seven safety/relief b. At least two of the safety/relief valves shall be valves shall be operable (note: Low-Low Set and disassembled and inspected each refueling ADS requirements are located in Specification interval.

3.2.H. and 3.5.A, respectively). I Valves shall be set as follows: c. The integrity of the safety/relief valve bellows shall be continuously monitored.

8 valves at *1120 psig

d. The operability of the bellows monitoring system

2. If Specification 3.6.E.1 is not met, initiate an orderly shall be demonstrated each operating cycle.

shutdown and have reactor coolant pressure and temperature reduced to 110 psig or less and 3450F 2. Low-Low Set Logic surveillance shall be performed or less within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. in accordance with Table 4.2.1.

3.614.6 127 Amendment No. 30, 62, 76, 92, 93, 11 4, 122, 128, 137 ,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 FR OERAION4.0SURVILLNCEREQIREENT IMIINGCONITINS H. Snubbers H. Snubbers

1. Except as permitted below, all safety related The following surveillance requirements apply to all snubbers shall be operable whenever the supported safety related snubbers.

system is required to be Operable.

2. With one or more snubbers made or found to be 1. Visual inspections:

Inoperable for any reason when Operability is Snubbers are categorized as inaccessible or required, within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />: accessible during reactor operation. Each of these

a. Replace or restore the inoperable snubbers to categories (inaccessible or accessible) may be Operable status and perform an engineering inspected independently according to the schedule evaluation or inspection of the supported determined by Table 4.6-1. The visual inspection components, or interval for each type of snubber shall be determined based upon the criteria provided in

b. Determine through engineering evaluation that Table 4.6-1. The initial inspection interval for new the as-found condition of the snubber had no types of snubbers shall be established at 24 months adverse effect on the supported components +25%.

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.

3.614.6 129 Amendment No. 9, 39, 45, 892,122,143

3.0 FR OERAION4.0SURVILLNCEREQIREENT IMIINGCONITINS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

.4

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. %-3%-122,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 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. Qr9, 143

3.0 LIMING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability: Applicability:

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

containment systems.

Objective: Objective:

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

Specification: Specification:

A. Primary Containment. A. Primary Containment

1. Suppression Pool Volume and Temperature 1. Suppression Pool Volume and Temperature When irradiated fuel Is in the reactor vessel and either the reactor water temperature is greater than a. The suppression chamber water temperature 212OF or work is being done which has the potential shall be checked once per day.

to drain the vessel, the following requirements shall be met, except as permitted by Specification b. Whenever there is indication of relief valve 3.5.E.2: operation which adds heat to the suppression pool, the pool temperature shall be continually

a. Water temperature during normal operating monitored and also observed and logged every shall be *90'F. 5 minutes until the heat addition is terminated.

b. Water temperature during test operation which adds heat to the suppression pool shall be c. A visual inspection of the suppression chamber

• 1 000 F and shall not be > 90OF for more than interior including water line regions and the 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. interior painted surfaces above the water line

c. If the suppression chamber water temperature shall be made at each refueling interval. I is >110OF, the reactor shall be scrammed immediately. Power operation shall not be resumed until the pool temperature is 90OF.

3.714.7 156 Amendment No. 63, 93, 14144, 143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS I

b. If both standby gas treatment system circuits are not operable, within 36 hours1.5 days <br />0.214 weeks <br />0.0493 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 2. Performance Requirement Tests

a. Periodic Requirements a. At least once per 720 hours30 days <br />4.286 weeks <br />0.986 months <br /> of system operation; or once per operating cycle, but not (1) The results of the in-place DOP tests at to exceed 24 months, whichever occurs first; or 3500 cfm (+10%) on HEPA filters shall following painting, fire, or chemical release in show < 1% DOP penetration. any ventilation zone communicating with the system while the system is operating that could (2) The results of in-place halogenated contaminate the HEPA filters or charcoal hydrocarbon tests at 3500 cfm (+/-10%) on absorbers, perform the following:

charcoal banks shall show *1 %

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

(3) The results of laboratory carbon sample (2) In-place test the charcoal adsorber banks analysis shall show *5% methyl iodine with halogenated hydrocarbon tracer.

penetration when tested in accordance with ASTM D3803-1989 at 300C, 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.

3.7/4.7 167 Amendment No. 60, 77, 94, 112 ,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. The system shall be shown to be operable with: b. Once per quarter demonstrate that the pressure drop across the combined filters of each (1) Combined filter pressure drop *6 inches standby gas treatment system circuit shall be water. measured at 3500 cfm (+/-t 10%) flow rate.

(2) Inline heater power output > 18kW. c. Once per operating cycle the operability of inline heater at nominal rated power shall be

c. The system shall be shown to be operable with verified for each standby gas treatment system.

automatic initiation upon receipt of the following inputs: d. At least once per operating cycle, automatic initiation of each standby gas treatment system (a) Low Low Reactor Water Level, or circuit shall be demonstrated.

(b) High drywell pressure, or (c) Reactor building ventilation plenum high radiation, or (d) Refueling floor high radiation

3. Post Maintenance Requirements 3. Post Maintenance Testing

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

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 leak tight integrity of the charcoal

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

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

3.7/4.7 168 Amendment No. 34 ,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION + 4.0 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 c 4,000 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 20F. corrected to calm wind conditions.

c. No activity is being performed which can reduce b. Verification that each automatic damper the shutdown margin below that specified in actuates to its isolation position shall be Specification 3.3.A performed:

d. The fuel cask or irradiated fuel is not being (1) Each refueling interval. I moved within the reactor building.

(2) After maintenance, repair or replacement

3. With an inoperable secondary containment isolation work is performed on the damper or its damper, restore the inoperable damper to operable associated actuator, control circuit, or status or isolate the affected duct by use of a closed power circuit.

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 hours1.5 days <br />0.214 weeks <br />0.0493 months <br />. Alterations of the 3.7/4.7 169 Amendment No. 3, 63, 7-6, 94, 143

I.

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS I

4. Station Battery System 4. Station Battery System If one of the two 125 V battery systems or one of a. Every week the specific gravity and voltage of the two 250 V battery systems is made or found to the pilot cell and temperature of the adjacent be inoperable for any reason, an orderly shutdown cells and overall battery voltage shall be of the reactor shall be initiated and the reactor water measured.

temperature shall be reduced to less than 212O F within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> unless such battery systems are b. Every three months the measurements shall be sooner made operable 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 I shall be subjected to a rated load discharge test. Determine specific gravity and voltage of each cell after the discharge.

5. 24V Battery Systems 5. 24V Battery Systems From and after the date that one of the two 24V a. Every week the specific gravity and voltage of battery systems is made or found to be inoperable the pilot cell and temperature of adjacent cells for any reason, refer to Specification 3.2 for and overall battery voltage shall be measured.

appropriate action.

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.

3.914.9 203 Amendment No. 3r*4 143

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

2. Performance Requirements 2. Performance Requirement Test

a. Acceptance Criteria - Periodic Requirements The in-place performance testing of HEPA filter banks (1) The results of the in-place DOP tests at 1000 and charcoal adsorber banks shall be conducted in cfm (+/- 10%) shall show < 1% DOP penetration accordance with Sections 10 and 11 of ASME on each individual HEPA filter and shall show N510-1989. The carbon sample test for methyl iodide c0.05% DOP penetration on the combined shall be conducted in accordance with ASTM HEPA filters. D 3803-1989. Sample removal shall be in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, (2) The results of in-place halogenated Revision 2, March 1978.

hydrocarbon tests at 1000 cfm (+/- 10%) shall show < 1% penetration on each individual a. At least once per operating cycle, but not to exceed charcoal adsorber and shall show

• 0.05% 24 months; or following painting, fire, or chemical I penetration on the combined charcoal banks. release while the system is operating that could contaminate the HEPA filters or charcoal adsorbers, (3) The results of laboratory carbon sample perform the following:

analysis shall show *0.5% methyl iodide penetration when tested at 300C and 95% (1) In-place DOP test the HEPA filter banks.

relative humidity.

(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, 112,143

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4" 4.0 SURVEILLANCE REQUIREMENTS

c. The system shall be shown to be operable with: c. At least once per operating cycle, but not to exceed 24 months, the following conditions shall be I (1) Combined filter pressure drop

• 8 inches water. demonstrated for each emergency filtration system train:

(2) Inlet heater power output 5kw+/- 10%. (1) Pressure drop across the combined filters of each train shall be measured at 1000 cfm (3) Automatic initiation upon receipt of a high (+/- 10%) flow rate.

radiation signal.

(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 Requirements 3. Post Maintenance Testing

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

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

b. After any maintenance or testing that could affect the charcoal adsorbers.

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.

3.17/4.17 229x Amendment No. 65, 101, 108, 112,143