Text

Amends 74 & 74 to Licenses NPF-72 & NPF-77,respectively, Revising TSs for Plant to Implement Ten of Line Item TS Improvements Included in GL 93-05, Line Item TSs Improvements to Reduce Surveillance Requirements..
	ML20101R545
Person / Time
Site:	Byron, Braidwood
Issue date:	04/10/1996
From:	Assa R; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20101R531	List: ML20101R529; ML20101R545; ML20101R552;
References
	GL-93-05, GL-93-5, NUDOCS 9604160347
	Download: ML20101R545 (17)
	v • d • e

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UNITED STATES y

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30086 0001 i

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C0f910NWEALTH EDISON COMPANY i

DOCKET NO. STN 50-456 2

i BRAIDWOOD STATION. UNIT NO....I i

AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 74 j

License No. NPF-72 f.

1.

The Nuclear Regulatory Commission (the Commission) has found that:

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A.

The application for amendment by Commonwealth Edison Company (the licensee) dated October 3, 1995, as supplemented February 21, 1996, and April 2, 1996, complies with the standards and j

requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in i

10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the i

provisions of the Act, and the rules and regulations of the i

Commission; i

L C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;

)

and j

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l 2.

Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment, and i

paragraph 2.C.(2) of Facility upcrating License No. NPF-72 is hereby i

amended to read as follows:

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9604160347 960410 PDR ADOCK 05000454

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. (2)

Technical Soecifications i

The Technical Specifications contained in Appendix A as revised l

through Amendment No. 74 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate l

the facility in accordance with the Technical Specifications and l

the Environmental Protection Plan.

1 1

3.

This license amendment is effective as of the date of its issuance.

1 FOR THE NUCLEAR REGULATORY COMISSION l

l 1

Ramin R. Assa, Project Manager l

Project Directorate III-2 l

Division of Reactor Projects - III/IV i

Office of Nuclear Reactor Regulation l

Attachement:

Changes to the Technical Specifications Date of Issuance: April 10, 1996 1

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4

4 UNITED STATES j

j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. h4864001

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COP 910NWEALTH EDISON COMPANY DOCKET NO. STN 50-457 i

BRAIDWOOD STATION. UNIT NO. 2 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-77 1.

The Nuclear Regulatory Commission (the Commission) has found that:

l l

A.

The application for amendment by Commonwealth Edison Company (the l

licensee) dated October 3,1995, as supplemented February 21, 1996, and April 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations :st forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized l

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

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i D.

The issuance of this amendment will not be inimical to the common l

defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-I cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-77 is hereby amended to read as follows:

i

. (2)

Technical Snecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 74 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this

)

license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date if its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

Ramin R. Assa, Project Manager 4

Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Recctor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 10, 1996 i

f e

i ATTACHMENT TO LICENSE AMENDMENT NOS. 74 AND 74 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 i

DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Pages indicated by an asterisk are provided for convenience only.

i Remove Paaes Insert Paaes 3/4 1-15 3/4 1-15 3/4 3-42 3/4 3-42 1

3/4 4-11 3/4 4-11 3/4 4-22 3/4 4-22 3/4 5-2 3/4 5-2 3/4 6-13 3/4 6-13

)

3/4 6-25 3/4 6-25 3/4 6-26 3/4 6-26 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5

3/4 7-6

3/4 7-6 3/4 11-3 3/4 11-3

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) c)

A power distribution map is obtained from the movable within their limits wil(hin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; andZ) and FL are verified to incore detectors and F d)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these 1

conditions; c.

With more than one full-length rod trippable but inoperable due to causes other than addressed by ACTION a. above, or misaligned from its group step counter demand height by more than 12 steps (indicated position), POWER OPERATION may continue provided that:

1.

Within I hour, the remainder of the rods in the group (s) with the inoperable rods are aligned to within 12 steps of the inoperable rods while maintaining the rod sequence and insertion limits of Figure 3.1-1.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and

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2.

The inoperable rods shall be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

)

i SURVEILLANCE RE0VIREMENTS 4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.

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BRAIDWOOD - UNITS 1 & 2 3/4 1-15 AMENDMENT NO. 74

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TABLE 4.3-3 RADIATION MONITORING INSTRLMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS DIGITAL i

CHANNEL CHANNEL CHANNEL OPERATIONAL MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATION TEST SURVEILLANCE IS REQUIRED 1.

Fuel Building Isolation-Radioactivity-High and Criticality (ORE-AR055/56)

S R

Q I

2.

Containment Isolation-Containment Radioactivity-High a) Unit 1 (IRE-ARoll/12)

S R

Q All b) Unit 2 (2RE-AR0ll/12)

S R

Q All 3.

Gaseous Radioactivity-RCS Leakage Detection i

a) Unit 1 (IRE-PR0llB)

S R

Q 1, 2, 3, 4 b) Unit 2 (2RE-PR0llB)

S R

Q 1, 2, 3, 4 4.

Particulate Radioactivity-RCS Leakage Detection a) Unit 1 (IRE-PR0llA)

S R

Q 1, 2, 3, 4 b) Unit 2 (2RE-PR0llA)

S R

Q 1, 2, 3, 4 5.

Main Control Room Isolation-Outside Air Intake-Gaseous Radioactivity-High a) Train A (ORE-PR031B/328)

S R

Q All i

b) Train B (ORE-PR0338/348)

S R

Q All l

With new fuel or irradiated fuel in the fuel storage areas or fuel building.

BRAIDWOOD - UNITS 1 & 2 3/4 3-42 AMENOMENT NO. 74

o EEAC,TARl00LANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with at least two groups of pressurizer heaters each having a capacity of at least 150 kW and a water level of less than or equal to 92%.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With less than two groups of pressurizer heaters OPERABLE, restore at least two groups of pressurizer heaters to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in i

HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor trip breakers open within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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SURVEILLANCE RE0VIREMENTS 4.4.3.1 The pressurizer water level shall be determined to be within its limit 4

l at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I 4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified by energizing the heaters and measuring circuit current at least once each refueling interval.

4.4.3.3 The cross-tie for the pressurizer heaters to the ESF power supply shall be demonstrated OPERABLE at least once per 18 months by energizing the heaters.

'l BRAIDWOOD - UNITS 1 & 2 3/4 4-11 AMENDMENT N0. 74

l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6 2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the contain:aent atmosphere gaseous and particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; b.

Monitoring the reactor cavity sump discharge, and the containment floor drain sump discharge and inventory at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; i

c.

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 i 20 psig at least once per 31 days with the modulating valve fully open. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and e.

Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months, b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, c.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and d.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve except for valves RH 8701 A and B and RH 8702 A and B.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

BRAIDWOOO - UNITS 1 & 2 3/4 4-22 AMENDMENT NO. 74

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l i

b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 70 gallons by verifying the boron concentration of the accumulator solution. This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that the RWST boron concentration is within the accumulator boron concentration limit.

At least once per 31 days when the RCS pressure is above 1000 psig by c.

verifying that the MCC compartment for each accumulator isolation valve is open and tagged out of service.

4.5.1.2 Each accumulator water level and pressure channel shall be demonstrated OPERABLE at least once per 18 months by the performance of a l

CHANNEL CALIBRATION.

l BRAIDWOOD - UNITS 1 & 2 3/4 5-2 AMENDMENT NO. 74 f

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I CONTAINMENT SYSTEMS l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM 1

i LIMITING CONDITION FOR OPERATION 1

3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

1 With one Containment Spray System inoperable, restore the inoperable Spray i

System to OPERABLE status within 7 days or be in at least HOT STANDBY within

'the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f SURVElllANCE RE0VIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

3 a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.

By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 265 psig when tested pursuant to Specification 4.0.5; c.

At least once per 18 months during shutdown, by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Spray Actuation test signal, and 2)

Verifying that each spray pump starts automatically on a Containment Spray Actuation test signal.

d.

At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

BRAIDWOOO - UNITS 1 & 2 3/4 6-13 AMENDMENT NO. 74

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CONTAllMENT SYSTEMS l

3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS i

j LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen monitors shall be OPERABLE.*

APPLICABILITY: M00ES I and 2.

ACTION:

a.

With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT STANDBY j

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

-b.

With both hydrogen monitors inoperable, restore at least one monitor to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY j

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

L i

SURVEILLANCE REQUIREMENTS l

j 4.6.4.1 Each hydrogen monitor shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK and a check that the monitor is in standby mode at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an ANALOG CHANNEL OPERATIONAL TEST at least once per 92 days, and at least once each refueling interval by performing a CHANNEL l

i CALIBRATION using five gas samples which shall cover the range from zero i

volume percent hydrogen (100% N ) to greater than 20 volume percent hydrogen, 2

4 balance nitrogen.

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The monitors must be in standby mode to meet the r quirement in NUREG-0737, e

4 Item II.F.1.6.

BRAIDWOOD - UNITS 1 & 2 3/4 6-25 AMENDMENT NO.

74 i

j CONTAIMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent Hydrogen Recombiner Systems shall be OPERABLE.

j APPLICABILITY: MODES I and 2.

ACTION:

i With one Hydrogen Recombiner System inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STAND 8Y within the j

next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE:

l a.

At least once each refueling interval by verifying, during a Recombiner System functional test that the minimum heater sheath temperature increases to greater than or equal to 1200*F within 90 minutes.

Upon reaching 1200*F, increase the temperature controller to maximum setting for 2 minutes and verify that the power is greater than or equal to 38 kW, and I

b.

At least once per 18 months by:

1)

Performing a CHANNEL CALIBRATION of all recombiner instrumen-tation and control circuits, s

2)

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners enclosure (i.e., loose wiring or structural connections, j

deposits of foreign materials, etc.), and 3)

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

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v BRAIDWOOD - UNITS 1 & 2 3/4 6-26 AMEN 0 MENT NO. 74

i PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

4 a.

One motor-driven auxiliary feedwater pump capable of being powered from an ESF Bus, and b.

One direct-driven diesel auxiliary feedwater pump capable of being powered from a direct-drive diesel engine and an OPERABLE Diesel Fuel Supply System consisting of a day tank containing a minimum of 420 gallons of fuel.

j

. APPLICABILITY: MODES 1, 2, and 3.

' ACTION:

a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I b.

With both auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I i

SURVEILLANCE RE0VIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1)

Verifying that each valve (manual, power-operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 92 days on a STAGGERED TEST BASIS by:

i 1)

Verifying that the pump develops a differential pressure of greater than or equal to 1825 psid at a flow of greater than or equal to 85 gpm on the recirculation flow when tested pursuant to Specification 4.0.5; BRAIDWOOD - UNITS 1 & 2 3/4 7-4 AMENDMENT NO. 74

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) c.

At least once per 18 months during shutdown by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an Auxiliary Feedwater Actuation test signal, and 2)

Verifying that the motor-driven pump and the direct-driven diesel pump start automatically upon receipt of each of the following test signals:

3 a)

Sl or b)

Steam Generator Water Level low-Low from one steam 4

generator, or c)

Undervoltage on Reactor Coolant Pump 6.9 kV Buses (2/4), or d)

ESF Bus 141 for Unit I (Bus 241 for Unit 2) Undervoltage (motor-driven pump only).

4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying normal flow to each steam generator.

4.7.1.2.3 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:

At least onca per 31 days by verifying the fuel level in its day a.

tank; b.

At least once per 92 days by verifying that a drain sample of diesel fuel from its day tank, obtained in accordance with ASTM-D4057-1981 is within the acceptable limits specified in Table 1 of ASTN-D975-1977 when checked for viscosity, water, and sediment; and At least once per 18 months, during shutdown, by subjecting the c.

diesel to an inspection in accordance with its manufacturer's recommendations for this class of service.

4 BRAIDWOOO - UNITS 1 & 2 3/4 7-5 AMENDMENT NO. 74

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PLANT SYSTEMS l

CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION i

j 3.7.1.3 The condensate stora water level of at least 405 ge tank (CST) shall be OPERABLE with a contained 1

APPLICA8ILITY:

MODES 1, 2, and 3.

ACTION:

With the CST inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a Restore the CST to OPERABLE status or be in at least NOT STAND 8Y a.

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or b.

Demonstrate the OPERABILITY of the Essential Service Water System as a backup supply to the auxiliary feedwater pumps and restore the j

CST to OPERABLE status within 7 days or be in at least HOT STAN06Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 4

l 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 i

SURVEILLANCE REQUIREMENTS 1

I 4.7.1.3.1 The CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water level is within its limits when the tank is the supply source for the auxiliary feedwater pumps.

4.7.1.3.2 The Essential Service Water System shall be demonstrated OPERABLE at j

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by performing the surveillance specified in Specifica-tion 4.7.4a. whenever the Essential Service Water System is the supply source for the auxiliary feedwate. pumps.

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I BRAIDWOOD - UNITS 1 & 2 3/4 7-6 h

4 RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity pontained in each gas decay tank shall be limited to less than or equal to 5x10 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

j b.

The provisions of-Specification 3.0.3 are not applicable.

i SURVEILLANCE RE0VIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added to the tank, and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary coolant system degassing operation.

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BRAIDWOOD - UNITS 1 & 2 3/4 11-3 AMENDMENT NO. 74 9

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ML20101R545

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