Text

License Amendment Request to Support 24-month Fuel Cycles, Current Monticello Technical Specification Pages Marked Up with Proposed Changes
	ML042040184
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: ML042040184 (23)
	v • d • e

ENCLOSURE 6 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST TO SUPPORT 24-MONTH FUEL CYCLES CURRENT MONTICELLO TECHNICAL SPECIFICATION PAGES MARKED UP WITH PROPOSED CHANGES 22 PAGES FOLLOW

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 Outage [Interval] - Refueling Operation is any operation when the reactor water temperature is less than 212ºF and movement of fuel or core components is in progress. [Refueling Interval is a designated] For the purpose of designating frequency of testing and [for performing] surveillance[s of once per 24 months.], a refueling outage shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage.

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

9/16/98 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[.] with the exception that, the intervals between tests scheduled for refueling shutdowns shall not exceed two years.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

3.0/4.0 25a 05/31/02 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

b.

High Flow In Main Steam Line

c.

High temp. in Main Steam Line Tunnel

d.

Low Pressure in Main Steam Line (3)

2.

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

a. Low Reactor Water Level

-48 140% rated 200°F

[209°F]

825 psig 7

2 8

8 2

2 2

8 2 of 4 in each of 2 sets 2

2 A

A A

B C

3.2/4.2 49 06/11/02 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*

Core Spray and LPCI Pump Start Low Low Reactor Water Level and

b. i. Reactor Low Pressure Permissive or ii. Reactor Low Pressure Permissive Bypass Timer

c. High Drywell Pressure (1)

Low Reactor Pressure (Valve Permissive)

Loss of Auxiliary Power

-48 450 psig 20+/-1 min

[20+/-2 min]

2 psig 450 psig 2

2 2

2 4(4) 2(4) 1 4(4) 2(4) 2(2) 4 2

1 4

2 2

A.

B.

A.

3.2/4.2 52 06/11/02 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 Oper-able 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)

2.

Loss of Voltage Protection (2) 3915 +/- 18 volts 9 +/- 1 sec 2625 +/- 175 volts

[+/-280 volts]

No intentional delay 1/bus 2/bus 3

2 3

2 A

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.2/4.2 60a 11/27/84 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 Reactor Coolant System Pressure for Opening/

Closing (1)

Discharge Pipe Pressure Inhibit and Position Indication Inhibit Timers 1072 +/- 3 / 992 +/- 3 psig

[+/-14] [+/-14]

1062 +/- 3 / 982 +/- 3 psig

[+/-14] [+/-14]

1052 +/- 3 / 972 +/- 3 psig

[+/-14] [+/-14]

30 +/- 1 psid (3)

[+/- 3 psid]

10 +/- 1 sec

[+/- 2 sec]

2(2) 2(2) 2(2) 2(2) 2 2

2 2

A or B or C A or B or C A or B or C A or B or C 3.2/4.2 60b 3/31/89 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/]Every 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 Once/3 months Once/3 months None Permissive)

5. Undervoltage Emergency Bus Refueling Outage[Interval]

Refueling Outage[Interval]

None

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

7. Loss of Auxiliary Power Refueling Outage[Interval]

Refueling Outage[Interval]

None

8. Condensate Storage Tank Level Refueling Outage[Interval]

Refueling Outage[Interval]

None

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

[Once/]Every Operating Cycle - Transmitter

[Once/]Every 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 Refueling Outage [Once/3 months]

None MAIN STEAM LINE (GROUP 1) ISOLATION

1. Steam Tunnel High Temperature Refueling Outage[Interval]

Refueling Outage[Interval]

None

2. Steam Line High Flow Once/3 months Once/3 Months Once/12 hours 3.2/4.2 61 12/24/98 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)

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

4. Reactor Low Low Water Level Once/3 months (Note 5) [Once/]Every Operating Cycle-Transmitter Once/12 hours 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)

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

2. High RWCU System Flow Once/3 months Once/Operating Cycle-Transmitter Once/12 hours 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 03/07/01 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/]Every Operating Cycle - Transmitter Once/12 hours Once/3 months - Trip Unit

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/12 hours 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 [3 months]

CONTROL ROOM HABITABILITY PROTECTION

1. Radiation Monthly (Note 5) 18 [24] months Daily 3.2/4.2 63 03/07/01 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

3.

NOTE: Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 1120 psig and 950 psig, the HPCI pump

b. One RHR pump may be inoperable for 30 days, can develop a flow rate 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 165 psig, the HPCI pump

d. One of the two LPCI injection paths may be can develop a flow rate 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,

4.

Perform the following tests:

or Item Frequency

f.

Both of the LPCI injection paths may be ADS Valve Each Operating inoperable for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or Operability Cycle

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

h. One ADS valve may be inoperable for 14 days, or ADS Inhibit Each Operating Switch Operability Cycle

i.

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

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 Low] reactor required to be operable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

water level) 3.5/4.5 102 08/01/01 Amendment No. 77, 79, 104, 122

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Reactor Core Isolation Cooling System (RCIC) shall after reactor steam pressure and flow are adequate be operable whenever irradiated fuel is in the to perform the test.

reactor vessel and reactor pressure is greater than 150 psig, except during reactor vessel hydrostatic or

a. Demonstrate, quarterly, with reactor pressure leakage tests.

1120 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a

2. RCIC may be inoperable for 14 days, provided system head corresponding to reactor pressure, HPCI is operable.

when tested in accordance with the Inservice Testing Program.

3. The controls for the automatic transfer of the pump suction may be inoperable for 30 days, if the pump

b. Demonstrate, once per operating cycle, with suction is aligned to the suppression pool.

reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a

4. If the requirements or conditions of 3.5.D.1, 2 or 3 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

2. Perform a simulated automatic actuation test condition in which the affected equipment is not (including transfer to suppression pool and required to be operable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

automatic restart on subsequent low [Low Low]

reactor water level) each refueling outage [interval].

3.5/4.5 105 08/01/01 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or be in Hot Shutdown within the the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 outage [interval] in and temperature is greater than 345°F the safety accordance with the Inservice Testing Program.

valve function (self actuation) of seven safety/relief valves shall be operable (note: Low-Low Set and

b. At least two of the safety/relief valves shall be ADS requirements are located in Specification disassembled and inspected each refueling 3.2.H. and 3.5.A, respectively).

outage [interval].

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 345°F

2.

Low-Low Set Logic surveillance shall be performed or less within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

in accordance with Table 4.2.1.

3.6/4.6 127 06/11/02 Amendment No. 30, 62, 76, 92, 93, 114, 122, 128

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 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.

1. Visual inspections:

2. With one or more snubbers made or found to be inoperable for any reason when Operability is Snubbers are categorized as inaccessible or required, within 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s:

accessible during reactor operation. Each of these categories (inaccessible or accessible) may be

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

b. Determine through engineering evaluation that types of snubbers shall be established at 18 [24] months the as-found condition of the snubber had no

+25%.

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.

3.6/4.6 129 08/01/01 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 18 [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 08/01/01 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 18 [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 3/13/86 Amendment No. 9, 39

3.0 LIMITING 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 :

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

containment.

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

a. The suppression chamber water temperature either the reactor water temperature is greater than shall be checked once per day.

212°F or work is being done which has the potential to drain the vessel, the following requirements shall

b. Whenever there is indication of relief valve be met, except as permitted by Specification operation which adds heat to the suppression 3.5.E.2:

pool, the pool temperature shall be continually monitored and also observed and logged every 5

a. Water temperature during normal operating minutes until the heat addition is terminated.

shall be 90°F.

b. Water temperature during test operation which

c. A visual inspection of the suppression chamber adds heat to the suppression pool shall be interior including water line regions and the 100°F and shall not be >90°F for more than interior painted surfaces above the water line 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

shall be made at each refueling outage [interval].

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.

3.7/4.7 156 7/12/95 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation; or once per operating cycle, but not (1) The results of the in-place DOP tests at to exceed 18 [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 30°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.

3.7/4.7 167 8/18/00 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:

b. At least [O]once per operating cycle, but not to exceed 18 months [quarter], the following conditions (1) Combined filter pressure drop 6 inches water.

shall be demonstrated for each standby gas treatment system: [demonstrate that the]

(2) Inline heater power output 18kW.

(1) Pressure drop across the combined filters of each

c.

The system shall be shown to be operable with standby gas treatment system circuit shall be automatic initiation upon receipt of the following measured at 3500 cfm (+/-10%) flow rate.

inputs:

(a) Low Low Reactor Water Level, or (2) Operability of inline heater at nominal rated power shall be verified.

(b) High drywell pressure, or

[c. Once per operating cycle the operability of the (c) Reactor building ventilation plenum high radiation, or inline heater at nominal rated power shall be verified for each standby gas treatment system.]

(d) Refueling floor high radiation

[d.] c. At least once per operating cycle, automatic

3. Post Maintenance Requirements initiation of each standby gas treatment system circuit shall be demonstrated.

a.

After any maintenance or testing that could affect the HEPA filter or HEPA filter mounting

3.

Post Maintenance Testing frame leak tight integrity, the results of the in-place DOP tests at 3500 cfm (+/-10%) on

a. After any maintenance or testing that could HEPA filters shall show 1% DOP penetration.

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 charcoal adsorber leak tight integrity,

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

hydrocarbon tests on the charcoal absorbers.

3.7/4.7 168 10/2/95 Amendment No. 94

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 4,000 scfm, shall be

a. The reactor is subcritical and Specification demonstrated at each refueling outage 3.3.A is met.

[interval] prior to refueling. If calm wind conditions do not exist during this testing,

b. The reactor water temperature is below 212°F.

test data is to be corrected to calm wind conditions.

c. No activity is being performed which can reduce the shutdown margin below that specified in

b. Verification that each automatic damper Specification 3.3.A actuates to its isolation position shall be performed:

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

(1) Each refueling outage[interval].

3. With an inoperable secondary containment isolation (2) After maintenance, repair or replacement damper, restore the inoperable damper to operable work is performed on the damper or its status or isolate the affected duct by use of a closed associated actuator, control circuit, or damper or blind flange within eight hours.

power circuit.

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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Alterations of the 3.7/4.7 169 10/2/95 Amendment No. 3, 63, 76, 94

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

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 212°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 outage [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

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.

3.9/4.9 203 3/24/86 Amendment No. 3, 41

3.0 LIMITING CONDITIONS FOR OPERATION 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 and charcoal adsorber banks shall be conducted in (1)

The results of the in-place DOP tests at 1000 accordance with Sections 10 and 11 of ASME cfm (+/-10%) shall show 1% DOP penetration N510-1989. The carbon sample test for methyl iodide on each individual HEPA filter and shall show shall be conducted in accordance with ASTM 0.05% DOP penetration on the combined D 3803-1989. Sample removal shall be in accordance HEPA filters.

with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978.

(2)

The results of in-place halogenated hydrocarbon tests at 1000 cfm (+/-10%) shall

a. At least once per operating cycle, but not to exceed show 1% penetration on each individual 18 [24] months; or following painting, fire, or chemical charcoal adsorber and shall show 0.05%

release while the system is operating that could penetration on the combined charcoal banks.

contaminate the HEPA filters or charcoal adsorbers, perform the following:

(3)

The results of laboratory carbon sample analysis shall show 0.5% methyl iodide (1) In-place DOP test the HEPA filter banks.

penetration when tested at 30°C and 95%

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 8/18/00 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:

c. At least once per operating cycle, but not to exceed 18 [24]months, the following conditions shall be (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 (3) Automatic initiation upon receipt of a high each train shall be measured at 1000 cfm radiation signal.

(+/-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

3. Post Maintenance Requirements

(+/-10%).

a. After any maintenance or testing that could affect

3. Post Maintenance Testing the HEPA filter or HEPA filter mounting frame leak tight integrity, the results of the in-place DOP tests

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

show 0.05% DOP penetration on the combined HEPA filters.

b. After any maintenance or testing that could affect the leak tight integrity of the charcoal adsorber

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

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 8/18/00 Amendment No. 65, 101, 108, 112

ML042040184

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