Text

Amends 90 & 75 to Licenses DPR-58 & DPR-74,respectively, Revising Tech Specs for Reactor Trip Sys Instrumentation & ESFAS Instrumentation
	ML17321A883
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Site:	Cook
Issue date:	08/26/1985
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
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ML17321A884	List: ML17321A883; ML17321A885;
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.gO License No.

DPR-58 I.

The Nuclear Regu'latory Commission (the Commission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated March 29, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the CormIIission'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 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read as follows:

1 g

4

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 9O

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The change in Technical Specifications is to become effective within 45 days of issuance of the amendment.

In the period between issuance of'he amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

A4g0st 26, 1985 even Va ga, ief Operating Reacto ranch Pl Division of Licensing

UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No.

DPR-74 1.

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

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated March 29, 1985, 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 author ized 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The change in Technical Specifications is to become effective within 45 days of issuance of the amendment.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alterhatives.

4.

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

FOR THE NUCLEAR EGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

A gust 26, 198 even

arga, Chi Operating Reactors B an h ¹I Division of Licensing

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

FACILITY OPERATING LICENSE NO.

DPR-58 AMENDMENT NO.

75 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NOS. 50-315 AND 50-316'evise Appendix A as follows:

Remove Pa es Unit 1

3/4 3-1 3/4 3-9*

3/4 3-10 3/4 3-14 3/4 3-15 3/4 3-16 3/4 3-17 3/4 3-18 3/4 3-20 3/4 3-21 3/4 3-22 3/4 3-23 Insert Pa es 3/4 3-1 3/4 3-9*

3/4'-10 3/4 3-14 3/4 3-15 3/4 3-16 3/4 3-17 3/4 3-18 3/4 3-20 3/4 3-21 3/4 3-22 3/4 3-23 Unit 2 3/4 3-5 3/4 3-6 3/4 3-21

Included for convenience.

No change.

3/4 3-5 3/4 3-6 3/4 3-21

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TABLE 3.3-1 Continued OES I GNAT ION CONDITION AND SETPOINT FUNCTION P-7 With 2 of 4 Power Range Neutron Flux Channels

> illof RATED THERMAL POWER or 1 of 2 Turbine impulse chamber pressure channels

>37 pslg

~

P-7 prevents or defeats the automatic block of reactor trip on:

Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-8 P-10 With 2 of 4 Power Range Neutron Flux channels

> 51K of RATED THERMAL POWER.

With 3 of 4 Power range neutron flux channels ( 9X of RATED THERMAL POWER.

P-8 prevents or defeats

+he au+omatic block of reactor trip on low coolant flow in a

single loop.

P-10 prevents or defeats the manual block of:

Power range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.

Provides input to P-7.

D.

C.

COOK-UNIT 1

3/4 3-9

TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT 1.

Manual Reactor Trip 2.

Power Range, Neutron Flux Power Range, Neutron Flux, High Positive Rate 4.

Power Range, Neutron Flux, High Negative Rate 5.

Intermediate

Range, Neutron Flux 6.

Source

Range, Neutron Flux 7.

Overtemperature hT 8.

Overpower sT 9.

Pressurizer Pressure--Low 10.

Pressurizer Pressure--High 11.

Pressurizer Water Level--High

RESPONSE

TIME NOT'PPLICABLE

< 0.5 seconds*

NOT APPLICABLE

< 0.5 seconds*

NOT APPLICABLE NOT APPLICABLE

< 6.0 seconds*

NOT APPLICABLE

< 1.0 seconds

< 1.0 seconds NOT APPLICABLE

Neutron detectors are exempt from response time testing.

Response

time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

TABLE 4.3-1 Continued NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1)

If not performed in previous.7 days.

(2)

(3)

Heat balance only, above 15 of RATED THERMAL POWER.

~gust channel if absolute difference

> 2 percent.

Compare incore to excore axial imbalance above 15K of RATED THERMAL POWER.

Recalibrate if absolute difference 3 percent.

(4)

Manual ESF functional input check every 18 months.

(5)

Each train tested every other month.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.

D. C.

COOK-UNIT 1

3/4 3-14 Amendment No.

90

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumenta-tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instr'umentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES

RESPONSE

TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific.

ESFAS function as shown in the "Total No. of Channels" Column of Table 3 ~ 3 3 ~

D.

C.

COOK-UNIT 1

3/4 3"1 Amendment No.

gO

r

~

CD TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUHENTATION n

CD 7C TC FUNCTIONAL UNIT TOTAL NO.

OF CNANHELS CflANNELS TO TRIP (11 NIHUt1 CHANNELS OPERABLE APPLICABLE MOOES ACTIOM 1.

SAFETY INJECTION; TURBINE.TRIP, FEEDMATER ISOLATION, AND HOTOR DRIVEN FEEDMATER PUtlPS 0

b.

Cr e.

Automatic Actuation Logic Containment Pressure-High Pressurizer Pressure

- Low Differential Pressure Between Steam Lines - Nigh Four Loops Operating Three Loops Operating a.

tianual Initiation 3/steam line 2/steam line 2/steam line

~ any steam line 3/operating 1

/steam 2/operating steam line line, any '.

steam line operating steam. line 1,2,3,4 1,2,3,4 1,2,3 1, 2, 38 1, 2, 3H 18 13 14*

14*

15

I (

~

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION n

CD CD 7CI 5

C4 CI Q

0 FUNCTIONAL UNIT f.

Steam Flow in Two Steam lines-High Four Loops Operating Three Loops Operating COINCIDENT WITH EITHER T

--Low-Low Four Loops Operating Three Loops Operating TOTAL NO.

OF CHANNELS 2/steam line 2/operating steam line 1 T

/loop 1T/

operating loop CHANNELS TO TRIP 1/steam line any 2 steam lines operating steam line 2 T any loops 1

T in

¹¹¹ any operating loop MINIMUM CHANNELS OPERABLE 1/steam line 1/operating steam line 1

T any 3 loops 1T in any two operating loops APPLICABLE MODES 3¹¹ ACTION 14*

15 14*

15

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V TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT OR, COINCIDENT WITH Steam Line Pressure-Low TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES 3A'CTION Four Loops Operating Three Loops Operating 2.

CONTAINMENT SPRAY a.

Manual b.

Automatic Actuation Logic f pr essure/

loop 1 pressure/

operating loop 2 pressures any loops 1

pressure in any oper-ating loop 1 pressure any 3 loops 1 pressure in any 2

operating loops 15 1, 2, 3, 4

18 1, 2, 3, 4

13 c.

Containment Pressure--

High-High 1, 2, 3

16

inwit. ~.~-3 Continued ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 4.

STEAM LINE ISOLATION TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION a.

Manual b.

Ci d.

Automatic Actuation Logic Containment Pressure--

High-High Steam Flow in Two Steam LinesHigh 2

1,2,3 3ff 1/steam line 1/steam line 1/operating 1, 2, 3

steam line 1

1, 2, 3

18 13 16 Four Loops Operating Three Loops Operating 2/steam line 2/operating steam line 1/steam line any 2 steam lines 1PEf/

operating steam line 1/steam line 1/operating steam line 14+

15

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUHENTATIOH FUNCTIOHAL UHIT I

TOTAL NO.

CHANNELS OF CHANNELS TO TRIP HIHIHUM CHANHELS OPERABLE APPLICABLE NODES ACTION COINCIDENT MITH EITHER Tay LOH Low Four Loops Operating Three Loops Operating OR, COINCIDENT WITH Steam Line Pressure-Low 1 T

/loop 1 Tay /oper-ating loop 2 T any loops any operating loop 1 T any 3 loops 1 T in any two operating loops 15 Four Loops Operating Three Loops Operating 5.

TURBINE TRIP 8

FEEDWATER ISOLATION 1 pressure/

2 pressures loop any loops 1 pressure/

1 pressure operating loop in any oper-ating loop 1 pressure any 3 loops 1 pressure in any 2 oper-ating loops 15 a.

Steam Generator Water Level--

iiigh-Nigh 3/loop 2/loop in any oper-ating loop 2/loop in each oper-ating loop 1, 2, 3

TABLE 3.3-3 Continued TABLE NOTATION

'Trip function may be bypassed in this MODE below P-ll.

'Trip function may be bypassed in this MODE below P-12.

Jl P 4

'-The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Total Number of Channels, be i'n HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within: the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 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 4.3.2. 1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 15 - With a channel associated with an operatina loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDO!IN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

however, one channel associated with an operating loop 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 Speci fi ca tion 4.3.2. 1.1.

ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condttien and the Minimum Channels OPERABLE requirement is met; one

~

additional 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 4.3.2.1.1.

D.

C.

COOK-UNIT 1

3/4 3-22 Amendment No.

90

TABLE 3.3-3 Continued)

ACTION 17 - With less than the tlinimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, 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 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 COLO SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTIOn 19 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the folloAing conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The ~1inimum Channels OPERABLE requirements is met; however, one additional 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 4.3.2.1.

ENGINEERED SAFETY FEATURES INTERLOCKS

'ES I GNAT ION P-11 P-12 CONDITION AND SETPOINT With 2 of 3 pressurizer pressure channels

> 1915 Psi9

~

With 3 of 4 T channels

> 544'F.

With 2 of 4 Tav channels c 540'F.

FUNCTION P-11 prevents or de fea ts manual block of safety injecti on actua tion on 1 ow pressurizer pressure.

P-12 prevents or defeats manual block of safety injection actuation high steam line flow and low steam line pressure.

Allows manual block of safety injection actua-tion on high steam line flow and low steam line pressure.

Causes steam line isolation on high steam flow.

Affects steam dump blocks.

D.

C.

COOK-UNIT 1

3/4 3-23 Amendment no.

90

TABLE 3.3-1 (Continued TABLE NOTATION Kith the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

~The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop. shall be placed in the tripped condition.

gThe provisions of Specification 3.0.4 are not applicable, fNHigh voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in 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 4.3.1.1.1.

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 inonerable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable 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 4.3.1.1.1.

c.

Either, THERMAL POWER is restricted to ~

75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to ~

85% of RATED THERMAL POWER v ithin 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.c.

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

D. C.

COOK - UNIT 2 3/4 3-5 Amendment No. 75

TABLE 3. 3-1 Continued a.

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

b.

Above P-6 but below 5X of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5X of RATED THERMAL POWER.

c.

Above 5X of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

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

b.

Above P-6, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement; verify compliance with the SHUTDOWN MARGIN requirements of Specification

3. l.l. 1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met;

however, the inoperable 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 of the other channels per Specification 4.3.1.1.1.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D.

C.

COOK - UNIT 2 3/4 3-6 Amendment No.

75

TABLE 3.3-3 Continued TABLE NOTATION Trip function may be bypassed in this MODE below P-ll.

Trip function may be bypassed in this MODE below P-12.

The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

ACTION 13-ACTION 14-ACTION 15-ACTION 16-ACTION STATEMENTS With the number of OPERABLE Channels One less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ;

however, one channel may be bypassed for op to a bours for.

su< veillance testing per Specification 4.3.2.1.1.

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

however, one channel associated with an operating loop 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 4.3.2. 1.1.

With the number of OPERABLE.Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met ; one additional 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 4.3.2.1.1.

D.

C.

COOK UNIT 2 3/4 3-21 pmgndpgLLt. No. 75

ML17321A883

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