ML20101D966

Amends 80 to Licenses NPF-37 & NPF-66,revising Action Statements & Allowed Outage Time for Inoperability of One Channel & Both Channels of Source Range Neutron Flux Instrumentation in Shutdown Mode

ML20101D966
Person / Time
Site:	Byron
Issue date:	03/15/1996
From:	Dick G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20101D969	List: ML20101D966 ML20101D972 ML20101F166
References
NPF-37-A-080, NPF-66-A-080 NUDOCS 9603210393
Download: ML20101D966 (8)

Text

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g UNITED STATES S

NUCLEAR REGULATORY COMMISSION E

!j WASHINGTON, o.C. Sosn4001

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-37 1.

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

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 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 (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.

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-37 is hereby amended to read as follows:

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Technical Specificat_tani I

The Technical Specifications contained in Appendix A as revised through Amendment No. 80 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 the facility in accordance with the Technical Specifications and I

the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION b

George F. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

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

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NUCLEAR REGULAY" 1Y COMMISSION E

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4 COMMONWEALTH f,$ SON COMPANY DOCKET NO. ' N 50-455 BYRON STATIO!!, UNIT NO. 2 AMENDMENT TO FACILIT, OPERATING LICENSE Amendment No. 80 License No. NPF-66 1.

The Nuclear Regulatory Commission U he Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated January 11, 1596, complies with the standards and requirements of the Atomic Eaergy Act of 1954, as amended (the Act) and tne 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; 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 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-66 is hereby amended to read as follows:

I -

(2)

Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113),

as revised through Amendment No. 80 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached.o License '.4o. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appandix A which is hereby incorporated into this license.

she 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 of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION b

George F. Dick, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

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

ATTACHMENT TO LICENSE AMENDMENT NOS. 80 AND 80 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Revise.the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Remove 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

5 TABLE 3.3-1 8

REACTOR TRIP SYSTEM INSTRUMENTATION E

MINIMUM Z

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 I

m 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###, 2 2

3.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Positive Rate m

s

[

4.

Power Range, Neutron Flux, 4

2 3

1, 2 2

4 High Negative Rate 5.

Intermediate Range, Neutron Flux 2

1 2

liff, 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

g 8.

Overpower AT 4

2 3

1, 2 6

z E

9.

Pressurizer Pressure-Low 9

(Above P-7) 4 2

3 1

'6 m

5 b

i.

.r i

TABLE 3.3-1 (Continued) i I

TABLE NOTATIONS

• With the Reactor Trip System breakers in the closed position and the 4

Control Rod Drive System capable of rod withdrawal.

i.

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

In this condition, i

j source range function does not provide reactor trip, but does provide input to the Boron Dilution Protection System (Technical Specification 3.1.2.7) i 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.

j ACTION STATEMENTS t

ACTION 1 - With the number of OPERABLE channels one less than the Minimum i

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 />.

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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 l

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 3

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 i

surveillance testing of other channels per Specification j

4.3.1.1; and 4

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 0-6 (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.

8YRON - UNITS 1 & 2 3/4 3-5 AMENDMENT N0. 80

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 4 -' With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

ACTION Sa - 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 within the next hour open the reactor trip breakers. With no channels OPERABLE, immediately open the reactor trip breakers.

ACTION 5b - With no channels OPERABLE, immediately suspend operations involving positive reactivity additions and within I hour verify valves CV-111B, CV-8428, CV-8439, CV-8441, and CV-8435 are closed.

Also, within I hour 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, 4

verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable.

l 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 " tquired 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 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, 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 />.

i i

BYRON - UNITS 1 & 2 3/4 3-6 AMENDMENT NO. 80