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Amend 28 to Licenses NPF-37 & NPF-66 & Amend 17 to Licenses NPF-72 & NPF-77,modifying Tech Spec Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09 Re Reactor Trip Sys Automatic Actuation Using Shunt Trip Coil Attachments
	ML20247J213
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	05/22/1989
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20247J219	List: ML20247J213; ML20247J785;
References
	GL-85-009, NPF-37-A-028, NPF-66-A-028, NPF-72-A-017, NPF-77-A-017 NUDOCS 8906010073
	Download: ML20247J213 (27)
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'l-COMMONWEALTH EDISON COMPANY DOCKET NO. 50-454 BYRON STATION, UNIT 1

' AMENDMENT TO FACILITY OPERATING LICENSE Amendswnt No. 28 License No. NPF-37 1.

The Nuclear Regulatory Comission (the Comission) has-found that:

'A.

The application for amendment by Comonweelth Edison Company (the licensee) dated December, 23,'1987, suppicmented April 3, 1989,.

complies with the standards and requirements'of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.

The issuance of this amendu.ent will nct be inimical to the connon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended.by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby dmended to read as folloWb:

8906010073 890522 6

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1 2-(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 28 and the Environmental Protection Plan contained in Appendix B,.both of which are attached hereto, are hereb,i 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 of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 22, 1989

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e COMMONWEALTH EDISON COMPANY DOCKET N0. 50-455-l BYRON STATION, UNIT 2 AMENDMENT T0' FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-66

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11.

The Nuclear Regulatory Comission (the Comission). has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated December 23, 1987, supplemented April.3, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The iacility will operate in conformity trith the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health ano.

safety _of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical.to the comon 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 Comission's regulations ano all applicable requirements have

'been satisfied.

2.-

Accordingly, the' license-is amended by changes to the Technical Specifications 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:

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(2) Technical Specifications TheTechnicalSpecificationscontained'inAppendixA(NUREG-1113),as revised through Amendment No. 28 and revised by Attachment 2 to NPF-60, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated 'into this license. Attachment 2 contains a revision to Appendix A which is 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'of its issuance.

FOR THE. NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 22, 1989

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ATTACHMENT TO LICENSE' AMENDMENT NOS. 28 AND 28 FACILITY OPERATING LICENSE.NOS. NPF-37 AND NPF-66 1

DOCKET NOS. 50-454 AND 50-455-Revise Appendix A'as.follows:

Remove Pages Insert Pages 2-6 2-6

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TABLE 3.3-1 (Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers in the closed position and the Control Rod Drive System capable of rod withdrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup.

- - These channels also provide inputs to ESFAS.

The Action Statement for the channels in Table 3.3-3 is more conservative and, therefore, controlling.

The. provisions of Specification 3.0.4 are not applicable.

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

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

@Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypass-

.ing 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of 0PERABLE 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

BYRON - UNITS 1 & 2 3/4 3-5 Amendment No. 28 EN

f 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 L 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or within the next hour open the reactor trip breakers, suspend all operations-involving positive reactivity changes, and verify valves CV-111B, CV-8428, CV-8439, CV-8441'and CV-8435 are closed and secured in position.

With no channels OPERABLE verify compliance with the' SHUTDOWN MARGIN

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requirements of Specification 3.1.1.1 or 3.1.'1.2, as applicable, and take the actions stated above within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ard verify compliance at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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, be in at least HOT STANDBY-within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - a.

With one of the diverse trip features (Undervoltage or Shunt Trip attachment) inoperable, restore it to OPERABLE BYRON - UNITS 1 & 2 3/4 3-6 Amendment No. 28

L TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued) 1 status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable

.and apply the requirements of b below..The breaker shall not be-bypassed while one of the diverse trip features is inoperable, except for the time required for performing maintenance and testing to restore the diverse trip feature to OPERABLE status.

b.

With one of the Reactor Trip Breakers otherwise inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;'however, one Reactor Trip Breaker may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other Reactor Trip Breaker is OPERABLE.

ACTION 13 - With the Reactor Trip Bypass Breaker inoperable, restore the Reactor Trip Bypass Breaker to OPERABLE status prior to using the Reactor Trip Bypass Breaker to bypass a Reactor Trip Breaker.

If the Reactor Trip Bypass Breaker is racked in and closed for.

bypassing a Reactor Trip Breaker and it becomes inoperable, be in-at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore ~the Bypass Breaker to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Bypass Breaker within the following hour.

1 1

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l BYRON - UNITS 1 & 2 3/4 3-6a Amendment No. 28

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TABLE NOTATIONS (10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall be performed such that each train is tested at least every 62 days on a STAGGERED TEST BASIS and following maintenance or adjustment of the Reactor Trip Breakers and shall include independent verification of the OPERABILITY of the Undervoltage and Shunt Trip Attachments of the Reactor Trip Breakers.

(12) At least once per 18 months during shutdown verify that on a simulated Boron Dilution Doubling test signal CVCS valves 1120 and E open and 1128 and C close within 30 seconds.

(13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

(14) Verify that the appropriate signals reach the Undervoltage 'a'nd Shunt Trip Relays, for both the Reactor Trip and Bypass Breakers from the Manual Trip Switches.

Initial performance of this surveillance requirement for the Reactor Trip Bypass Breakers is to be completed prior to the startup following the third refueling outage for Unit 1 and the second refueling outage for Unit 2.

(15) Manual Shunt Trip prior to the Reactor Trip Bypass Breaker being racked in and closed for bypassing a Reactor Trip Breaker.

(16) Automatic Undervoltage trip.

Initial performance of this surveillance requirement is to be completed prior to the startup following the third refueling outage for Unit 1 and the second refueling outage for Unit 2.

BYRON - UNITS 1 & 2 3/4 3-12a AMENDMENT NO. 28

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COMMONWEALTH EDISON COMPANY;,

LDOCKET NO. 50-456

'BRAIDWOOD STATION, UNIT 1 b

AMEf4DMENT TO FACILITY OPERATING LICENSE y

Amendment No.17 License No. hPF-72 1.-

The Nuclear Regulatory Connission (the Coninission) has found that:

A.

The application for amendment by Connonwealth Edison Company (the licensee) dated December 23, 1987, supplemented April 3, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.(the Act) and the Concission'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 Consission; C.

Thereisreasonableassurance(i)th6ttheactivitiesauthorizedby 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 Comniission's regulations; U.

The issuance of this amendment will not be inimical to the connon defense and security or to the health ano safety of the public; and E.

The issuance of this amenduent is in accordance with 10 CFR Part 51 of the Consission's regulations ano all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tion 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:

1

2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.17 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 the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION M

Daniel R. Muller, Director i

Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

May-22, 1989 i

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. 3-UNITED STATES.

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- NUCLEAR REGULATORY COMMISSION 7,

4j WASHINGTON, D. C. 20555 -

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j-t C0lWONWEALTH EDIS0N COMPANY DOCKET-NO. 50-457-

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BRAIDWOOD STATION. UNIT 2;

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-AMENDMENT TO FACILITY OPERATING LICENSE' i

Amendment No. 17 j

License No.'NPF-77.

l

.1.

The Nuclear Regulatory Comission (the Comission) has found that:-

A.

.The application for amendment by Commonwealth Edison Company (the licensee) dated December 23, 1987, supplemented April 3, 1989,-

complies with the standards and' requirements of the. Atomic. Energy Act L of 1954,-as amendeo (the Act) and the Comission'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 L

Comission; C.

'There'isreasonableassurance(1)thattheactivitiesauth'orizedby 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 Consnission's regulations;

&~

D.

The issuance of this amendment will not be inimical to the comon defense and _ security or to the health and safety of the public; and E.

. The issuance of this ainendment is in accordance with 10 CFR Part 51

of the Comission's regulations and all applicable requirements have

'been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tion as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:

i

o. l i

I J

2 i

(2) Technical Specifications The_ Technical Specifications contained in Appendix A as revised through Artendment No.17 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 of its issuance.

FOR THE NUCLEAR REGULATORY C0ftlISSION M

L Daniel R. Nuller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to_the Technical Specifications Date of Issuance:

May 22, 1989

--_m____.___.____.____

___________m__

_m

ATTACHMENT TO LICENSE AMENDMENT NOS.17-AND 17-AND FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. 50-456 AND 50-457 Revise Appendix A as follows:

Remove Pages Insert Pages 2-6 2-6 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 5 6 3/4 3-6 3/4 3-6a 3/4 3-9 3/4 3-9 3/4 3-11 3/4.3-11

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TABLE'3.3-1'(Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers in the closed position and the Control' Rod Drive System capable of rod withdrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup.

- - These channels also provide inputs to ESFAS.

The Action Statement for the channels in-Table 3.3-3 is more conservative and, therefore, controlling.

The provisions of Specification 3.0.4 are not applicable.

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

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

@Whenever the Reactor Trip Bypass Breakers are racked in and closed for by-passing'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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1; and Either, THERMAL POWER is restricted to less than or equal c.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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. 17

yy 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 5 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or within the next htur open the reactor trip breakers, suspend all operations involving positive reactivity changes, and verify valves CV-1118, CV-8428, CV-8439,

.CV-8441 and CV-8435 are closed and secured in position.

With no channels OPERABLE verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, and take.the actions stated above within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and verify compliance at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 a.

With one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE BRAIDWOOD - UNITS 1 & 2 3/4 3-6 Amendment No. 17

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' TABLE 3.3-1 (Continued).-

t ACTION STATEMENTS (Continued) p status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply the requirements of b.below.

The breaker.shall-o not be bypassed while one of the diverse trip features is inoperable,.except. for the time required for performing,

maintenance.and testing to restore the diverse trip feature to OPERABLE status, b.

With one of the" Reactor Trip Breakers otherwise inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one Reactor Trip-Breaker may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance. testing per Specification 4.3.1.1, provided the l

other Reactor Trip Breaker is OPERABLE.

ACTION 13 -

With the Reactor Trip Bypass Breaker inoperable, restore

'the Reactor. Trip Bypass Breaker'to OPERABLE status ~ prior to' l

using the Reactor Trip Bypass Breaker to bypass a Reactor Trip Breaker.

If the Reactor. Trip Bypass Breaker is 1

racked in and closed for bypassing a Reactor Trip Breaker and it becomes inoperable, be in at least HOT STANDBY.

4 within 6. hours.

Restore the Bypass Breaker to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the. Bypass Breaker within~the following hour.

l l

BRAIDWOOD - UNITS 1 & 2 3/4 3-6a Amendment No. 17 l

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~ TABLE 4.3-1 (Continued) i l

TABLE NOTATIONS

With the Reactor Trip System breakers closed and the Control Rod Drive l

System capable of rod withdrawal.

- These channels also provide inputs to ESFAS.

The Operational Test Frequency for these channels in Table 4.3-2 is more conservative and, therefore, controlling.

The specified 18 month interval may be extended to 32 months for cycle 1 only.

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

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

(1)

If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(Sa) Initial plateau curves shall be measured for each detector.

Subsequent plateau curves shall be obtained, evaluated and compared to the initial curves.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(5b) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector.

Sub-sequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.

(9) Surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives F-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

Surveil-lance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

(10) Setpoint verification is not applicable.

1 BRAIDWOOD - UNITS 1 & 2 3/4 3-12 Amendment No. 17

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p.

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' TABLE 4.3-1 (Continued)

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TABLE NOTATIONS (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall be performed such that each train is tested at least every 62 days on a STAGGERED TEST BASIS and following maintenance or adjustment of the Reactor Trip-Breakers and shall:

include independent verification of the OPERABILITY of the Undervoltage and Shut Trip Attachments of the Reactor Trip Breakers.

(12) At least once per 18 months during shutdown verify that on a simulated Boron Dilution Doubling test signal CVCS valves 1120 and E open and 112B and C close within 30 seconds.

(13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

(14) Verify that the appropriate signals reach the Undervoltage and Shunt Trip relays', for both the. Reactor Trip and Bypass Breakers from the Manual Trip Switches.

Initial performance of this surveillance requirement is to be completed prior to the Startup following the Unit 1 Cycle 1 Refuel Outage. -

(15) Manual Shunt Trip prior to the Reactor Trip Bypass Breaker being racked in and closed by bypassing a Reactor Trip Breaker.

(16) Automatic undervoltage trip.

Initial performance of this surveillance requirement is to be completed prior to the startup following the Unit 1 Cycle 1 Refuel Outage.

BRAIDWOOD - UNITS 1 & 2 3/4 3-12a Amendment No. 17 1

ML20247J213

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