ML20101F166

Amends 72 to Licenses NPF-72 & NPF-77,revising Action Statements & Allowed Outage Time for Inoperability of One Channel & Both Channels of Source Range Neutron Flux Instrumentation in Shutdown Modes 3-5

ML20101F166
Person / Time
Site:	Byron, Braidwood
Issue date:	03/15/1996
From:	Assa R NRC (Affiliation Not Assigned)
To:
Shared Package
ML20101D969	List: ML20101D966 ML20101D972 ML20101F166
References
NUDOCS 9603250371
Download: ML20101F166 (8)

Text

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[pacua oq UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20666 4001 g

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COMMONWEALTH EDIS0N COMPANY DOCKET N0. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. NPF-72 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licr.nsee) dated January 11, 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 set 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 i

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 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-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:

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It.phnical Soecifications The Technical Specifications contained in Appendix A as revised' i

through Amendment No. 72 and the Environmental Protection Plan i

contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate-the facility in accordance with the Technical' Specifications and the Environmental Protection Plan.

l 3.

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

FOR THE NUCLEAR REGULATORY COMISSION

[C -

Ramin

. Assa, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV i

Office of Nuclear Reactor Regulation

Attachment:

-Changes to the Technical Specifications Date of Issuance: March 15,1996

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UNITED STATES E

NUCLEAR REGULATORY COMMISSION I

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WASHINGTON, D.C. 20666 4 001

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[QMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 2

BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT T0 FACILITY OPERATING LICENSE l

Amendment No. 72 License No. NPF-77 l

1.

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

1 A.

The application for amendment by Commonwealth Edison Company (the licensee) dated January 11, 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 set forth in 10 CFR Chapter 1; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 3

C.

.There is reasonable assurance (1) 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 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 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-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:

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Technical Soecifications i

The Technical Specifications contained in Appendix A as revised through Amendment No. 72 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 Ramin R. Assa, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Techriical Specifications Date of Issuance: March 15, 1996 1

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tJ.f/,CHMENT TO LICENSE AMENDMENT NOS. 72 AND 72 FACJiITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the follmi.ilg pages of the Appendix "A" Technical Specifications with the attached pages The revised pages are identified by amendment number and contain vertical 11 es indicating the area of change.

[bamove Paaes Insert Paaes 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6

TABLE 3.3-1 REACTOR TRIP-SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 1

2 1

2 3*, 4*, 5*

10 2.

Power Range, Neutron Flux a.

High Setpoint 4

2 3

1, 2 2

b.

Low Setpoint 4

2 3

1##f, 2 2

3.

Power Range, Neutron Flux 4

2 3

1, 2 L

High Positive Rate 4.

Power Range, Neutron Flux, 4

2 3

1, 2 2

High Negative Rate 5.

Ir".ermediate Range, Neutron Flux 2

1 2

l###, 2 3

6.

Source Range, Neutron Flux a.

Startup 2

1 2

2ff 4

b.

Shutdown

• 2 1

2 3*, 4*, 5*

Sa c.

Shutdown **

2 N/A 1

3**, 4**, 5**

Sb 7.

Overtemperature AT 4

2 3

1, 2 6

8.

Overpower AT 4

2 3

1, 2 6

9.

Pressurizer Pressure-Low (Above P-7) 4 2

3 1

6 BRAIDWOOD - UNITS 1 & 2 3/4 3-2 AMENDMENT NO. 72

5 TABLE 3.3-UContinued)

]

TABLE HOTATIONS

• With the Reactor Trip System breaker-in the closed position and the Control Rod Drive System capable of 4 3d withdrawal.

• • With Reactor Trip System Breakers in the open position.

In this condition, source range function does not provi a reactor trip, but does provide input to the Boron Dilution Protection System (Technical Specification 3.1.2.7) and indication.

1. 1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

9Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypassing a Reactor Trip Breaker.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1; and c.

Either, THERMAL POWER is restricted to less than or equal to 75%

of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

BRAIDWOOD - UNITS 1 & 2 3/4 3-5 AMENDMENT NO. 72

TABLE 3.3-1 (Continued).

ACTION STATEMENTS (ContinuM1 ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend ill operations involving positive reactivity changes.

ACTION Sa - With the number of OPERABLE channels v.s less than the Minimum Channels OPERABLE requirement, resto:e che inoperable channel to OPERABLE statts within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or within the next hour open the reactor trip 'oreakers. With no channch OPERABLE, immediately open the reactor trip breakers.

ACTION 5b - With no channels OPERABLE, immediately suspend operations involving positive reactivity additions and withia 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify valves CV-111B, CV-8428, CV-3439, CV-8441, and CV-8435 are closed. Also, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - Deleted ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for j

up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, i

provided the other channel is OPERABLE.

ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

BRAIDWOOD - UNITS 1 & 2 3/4 3-6 AMENDMENT N0. 72 j