Text

Amend 78 to License DPR-74,extending on one-time Basis, 18-month Surveillance Frequency by 2 Months for Testing Reactor Trip Sys Instrumentation,Containment Sump Level & Flow Monitoring Instrumentation & Electrical Power Sys
	ML17324A608
Person / Time
Site:	Cook
Issue date:	01/28/1986
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17324A611	List: ML17324A608; ML17324A613;
References
	NUDOCS 8602120758
	Download: ML17324A608 (23)
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n +y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON)D. C. 20g55 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 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 December 13, 1985, as supplemented by letter dated December 19, 1985, complies with the standar ds 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 wi'il 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.

DPR-74 is hereby amended to read as follows:

860212075$

860128 PDR ADOCK 05000316 P

PDR

(P)

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

, are hereby incorporated in the license.

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

3.

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:

JAN 2 8 1986 B. J.

Youngblood, Director PWR Project Directorate P4 Division of PWR Licensing-A, NRR PWR 4.

PWR-A DWiggi ton:kab 01/

86 PQ O'DPWR-A MDilncan 01/2f /86 OELD 01 q,g/86 PWR84:DPWR-A BJYoungblood 01/

/86

'P

ATTACHMENT TO LICENSE>AMENDMENT AMENDMENT NO.

78 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:

Remove Pa es 3/4 0-3 3/4 3-1 3/4 3-14 3/4 3-47 3/4 4-14 3/4 4-32 3/4 5-4 3/4 5-8 3/4 6-47 3/4 7-20 3/3 7-40 3/4 8-2 3/4 8-5 3/4 8-8 3/4 8-11 3/4 3-2*

3/4 5-3*

3/4 8-1*

3/4 8-6*

Insert Pa es 3/4 0-3 3/4 3-1 3/4 3-14 3/4 3-47 3/4 4-14 3/4 4-32 3/4 5-4 3/4 5-8 3/4 6-47 3/4 7-20 3/3 7-40 3/4 8-2 3/4 8-5 3/4 8-8 3/4 8-11 3/4 3-2 3/4 5-3 3/4 8-1 3/4 8-6 Included for Convenience Only.

3/-':. 0 APPLICABl'Y i

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SURVrlLLAHCE REQUIRE!'i tiTS b.

Surveillance intervals speci'ied in Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Techn'ical Specifications:

ASthE Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice inspection and testin cri'eria Required frequencies for performing inservice inspection and tes ino activities Meekly Honthly quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspecton and testing act'lvities.

d.

e.

Performance of the above inservice 'inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASHE Boiler and Pressure Vessel Code shall. be construed 0 supersede the requirements of any Technical Specification.

4.0.6 By specific reference to this section, those surveillances which must be performed on or before March 31, 1986, and are designated as 18-month sur-veillances (or required as outage-related surveillances under the provisions of Specification 4.0.5) may be delayed until the end of the refueling outage scheduled to begin on or before February 28, 1986.

For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date estab-lished by the surveillance date during the Unit 2 1986 refueling outage.

D.

C COOK UNIT 2 3/4 0-3 Amendment No. 78

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TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUME4TATION FUNCTIONAL UNIT 1.

Manual

- Reactor Trip

.2.

Power Range, Neutron Flux 3.

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 A.

Startup B.

Shutdown 7.

Overtemperature hT Four Loop Operation Three Loop Operation 8.

Overpower aT Four Loop Operation Three Loop Operation TOTAL NO.

OF CHANNELS 4

2 4

4 CHANNELS TO TRIP 21**

2 NINIMUM CHANNELS OPERABLE 2.

1 3

3 APPLICABLE MODES 1,

2 and

1, 2

1, 2 1,

2 1,

2 and

2 and

3, 4 and 5

1, 2

1, 2 1, 2 ACTION 12 9

INSTRUMENTATION 3/4.3.2 ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONOITION 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 requir'ement 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 inof)erable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.'1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MOOES:and at the frequencies shown in Table 4.3-P'.

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

The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK - UNIT 2 3/4 3-14 Amendment No. 778

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C)

INSTRUMENT t

TABLE 4. 3-10 I

POST"ACCIOENT MONITORING IHSTRUllEHTATIOH SURVEILLANCE RE UIREHEHTS CHANNEL CHECK CHANNEL CALI 0 RATION r

~ 't 1.

Containment Pressure 2.

Reactor Coolant Outlet Temperature -

THOT (Mide Range) 3.

Reactor Coolant Inlet Temperature '-

TCOLO (Mide Range) 4.

Reactor Coolant Pressure

- Wide Range 5.

Pressurizer Mater Level 6.

Steam Line Pressure c

7.

Steam Generator Mater Level - Har row Range 0.

RWST Mater Level 9.

Ooric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate ll.

Reactor Coolant System Subcooling Margin lhonitor g

12.

PORV Position Indicator - Limit Switches 13.

PORV Block Valve Position Indicator - Limit Switches*

0 14.

Safety Valve Position Indicator - Acoustic Monitor

The provisions of Specification 4.0.6 are applicable.

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TTM T

3.~.6.1 The folloMin~ Reactor Coolant System le&age detection syst~ shall be OP"-RABLE:

a.

One of the conta'"."ent at"ospher part'culate radioactivity mnito. ii~ channeis (ZRS-2301 or FRS-2401),

b.

The containment sump leve'r"."'c" -"."'tor'"4 J

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Either the containment heidi y monitor or one of the cor. a';="

atmosphere gaseous radioactivity nonitorinc channels

(".RS-2305 cr

-RS-2405).

%DDT Tl ~k?

T~T HOD-S 1

2 3 and 4P~~lt

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4ith orly t~o of the above required leakage detection systems O."-?A:-L"-,

operat'on may continue for up to.30 days provided

-"rab samples of the containment atmosphere are obtained and ara'y"ed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

~hen the r eouired gaseous and/or par ticulzte radioactivity monitorincr c?:anne's are inoperable o her.;>>ise be '.; at 'east HOT STANDBY with'a the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHOTDO'Rf within he folloMir~ 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4-".6.1 The leakage detect'on syst~ sha'l be Ce onstratM Oi"=RA?L? by:

a.

Containment atmssphere particulate and "aseous (if bei."~

sed) aoni or~ay system-performance of CHANN=L CH"=CK, CHANN~

CALTBRAT:ON and CHANNiL FUNCT:ONAL TEST at the frequencies b.

Containment sump level and flcM monitoring, sys ea-performance o.

CHANN"-L CALi9RATEON at least once per 18 mnths,*

c.

Cont icemen huuidi y moni or (if being used) - performance o.".

CHANN:-

CALX RATION at least orce per 18 conths.

1g

The provisions of Specification 4.0.6 are applicable.

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2 3/4 4-14 A lend'?ent

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~ 78

REACTOR COOLANT SYSTEM RELIEF VALVES - OPERATING LIMITIHG CONDITION FOR OPERATION 3.4.11 Three power operator relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a ~

b.

C.

Pith one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) and remove power from the block valve(s); otherwise, 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 SHUTDOW within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

with one or more block valve(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore the block valve(s) to OPERABLE status, or (2) close the block valve(s) and remove power from the block valve(s'), or (3) close the associated PORV(s) and. remove power from the associated solenoid valve(s); otherwise, 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 ."

The provisions'f Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE:

b.

At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and At least once per 18 months by performance of a CHANNEL CALIBRATIOHP*.

">hen ACTION 3.4.11.b. (3) is applied, no report pursuant to Specification 6.9.1.9 is required for the PORV.

- The provisions of Specification 4.0.6 are applicable.

D.C.

COOK - UNIT 2 3/4 4-32 Amendment, No.

78

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T

> 350'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging

pump, b.

One OPERABLE safety injection pump, c.

One OPERABLE residual heat removal heat exchanger, d.

One OPERABLE residual heat removal

pump, and e.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recir-culation phase of operation.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable sub-system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In the event the ECCS is actuated and injects water into the-Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days de cribing the circumstances of the actuation and the total accumulated actuation cycles to date.

D.C.

COOK - UNIT 2 3/4 5-3

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5-3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.*

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months wh'enever the temperature of one or more of the RCS cold legs is less than or equal to 152 F as determined at least once per hour when any RCS cold leg temperature is between 152'F and 200'F.

The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK " UNIT 2 3/4 5-8 Amendment No.

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PL%;T SYSi.u 3/4, 7, 7 SaiUBBERS L

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ZNG CONDZTZON FOR OP RATZON 3.7.7.1 A11 snubbers listed in Table 3;7-9 shall be OPERABLE APPLZCABZLZTYI MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems reguired OpERABLE in those MODES).

ACTZOÃ:

I With one or more snubbers inoperable, vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1c on the supported component or declare the supported system inoperable and follov the appropriate ACTION statement for that system.

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SURVEZLLANCE R

~NTS 4-7 7 1 Each snubber shall be demonstrated OP~LE by per ormance of the folloving augmented insedvice inspec J.on program and the recgxirements of

'pecification 4.0.5. **

I a.

Visual Znsoections The first inservice visual inspection of snubbe s shall be performed after four months but vithin 10 months of c~encing POWFZ OPERATZON and shall include al1 snubbers.listed in Table 3.7-9.

Zf less than (2) snubbers are found inope=able du ing the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25i from the date of the fi"st inspection.

Othervise, subs~ent visual inspections shall be per ormed in accordance vith the folloving schedule:

No. Znoperable Snubbe"s oer Znsnection Pe icd Subs~ent Visual Znsoection Period>>

0

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3,4 5,6,7 8 or more 18 months

'2 months 6 months 124 days 62 days 31 days

~ 25~

+Ca

+

~ 25' 25' 25m i 25t The snubbers may be categorized into two groups:

Those. accessible and those inaccessible during reactor operation.

Each group may be inspected, independently in accordance vith the above schedule.

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, '**The provisions of Specification 4.0.6 are applicable.

The provisions of Specification 4.0.2 are not applicable.

DC Cook-Unit 2 3/4 7 20 Amendment Ho.

PLANT SYSTE.'fS SURV ILLAÃCS REQUIREMENTS (Continued) b.

At least once per 18 months:*

1.

By performing a system functional test vhich includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the floM path actuate to their correct positions on a test signal and b)

Cycling each valve in the floM path that is not testable during plant operation through at least one complete cycle of full travel.

2.

By inspection of deluge and preaction system spray headers to verify their integrity.,

3.

By inspection of each open head deluge nozzle to ver'fy no bloc kage.

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At least once per 3 years by performing an air floM test through each open head deluge header and verifying each open head deluge nozzle is unobstructed.

The provisions of Specification 4.0.6 are applicable.

D. C.

COOK -UNIT 2 3/4 7-40 Amendment 'No.

78

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite trans-mission network and the onsite Class lE distribution system, and b.

Two separate and independent diesel generators each with:

1.

A day fuel tank containing a minimum volume of 70 gallons of fuel, 2.

A separate fuel storage system containing a minimum volume of 42,000 gallons of fuel, and 3.

A separate fuel transfer pump.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

b.

With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8. l.l.l.a and 4;8.1.1.2.a.4 within'ne hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least two'offsite circuits and two diesel generators 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D. C.

COOK - UNIT 2 3/4 8-1

( ~ 'C ~

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ELECTRICAL POWER SYSTEMS ACTION Continued c.

With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 .

With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss 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 .

d.

'With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.l.l.l.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 .

Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss. or be in 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 .

SURYEII LANCE RE UIRENENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:*

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:*

.a.

In accordance with the frequency specified in Table 4.8-1 on a

STAGGEREO TEST BASIS by:

l.

Verifying the fuel level in. the day fuel tank.

2.

Verifying the fuel level in the fuel storage tank.

The provisions of Specification 4.0.6 are applicable.

D. C.

COOK - UNIT 2 3/4 8-2 Amendment No. 78 b.

Demonstrated OPERABLE at least once per 18 months by trans-ferring the unit power source automatically from the normal auxiliary source to the preferred reserve source and by trans-ferring manually to the alternate reserve source.

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ELECTRICAL POWER SYSTEMS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE and ener-gized with tie breakers open between redundant busses:

4160 volt Emergency Bus ¹ T21A and T21B 4160 volt Emergency Bus ¹ T21C and T21D 600 volt Emergency Bus ¹ 21A and 21B 600 volt Emergency Bus ¹ 21C and 21D 120 volt A.C. Vital Bus ¹ Channel I

120 volt A.C. Vital Bus ¹ Channel II 120 volt A.C. Vital Bus ¹ Channel III 120 volt A.C. Vital Bus ¹ Channel IV APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.8.2.1 The specified A.C. busses shall be determined OPERABLE with tie breakers open between redundant busses at least once per 7 days by verify-ing correct breaker alignment and indicated power availability.

D. C.

COOK - UNIT 2 3I4 8-6

'5

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-CTRICAL PCvER SYST~'lS D.C. DISTRIBUTION OPERA ING

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LZHZTZNG CONDITION FOR OPERATIOH 3 8-2.3 The folloving D.C. bus trains'shall be energi=ed and OPERABLE vith tie breakers betveen bus trains open:

.RAIN AB consisting of 250-volt D.C. bus AB, 250-volt D.C. battery bank No.

2 AB, and a full capacity charge TRAIN CD consisting of 250-volt D.C. bus CD, 250-volt D.C. battery bank No.

2 CD, and a full capacity charger.

APPLICABILITY: MODES 1. 2, 3 and 4.

AC ZOM a., Pith one 250-volt D.C. bus inoperable, restore the inoperable bus to OPERABLE status vithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT ST sDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOtl4 v'thin the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Mith one 250-volt D.C. battery and/or its charger inope able, restore the i.noperable batte~ and/or charger to OPERABLE status vithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY vit.".in the next 6

hours and in COLD SHUTDOWN virhln the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEZLLAHCE RE UZRE&KHTS 4-8.2-3.1 ach D.C. bus train shall be determined OPERAB~ and erergi=ed vith the breakers open at least once per 7'ays by veri yirg correct breaker alignment and indicated pove availability.

4-8.2.3.2 Each 250-volt battery bank and charge= shall be demonstrated GP ERABLEa At least once per 7 days by veri ying that:

1.

The electrolyte level of each pilot cell is betveen the minimum and maximum level indication marks,

The provisions of Specification 4.0.6 are applicable.

D C

COOK UNIT 2 3/4 8-8 Amendment No.

78

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