ML17332A903

From kanterella
Revision as of 14:07, 7 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Amends 198 & 183 to Licenses DPR-58 & DPR-74,respectively, Revising SRs & Load Profiles for A,B & N Train Batteries
ML17332A903
Person / Time
Site: Cook  
Issue date: 08/22/1995
From: John Hickman
NRC (Affiliation Not Assigned)
To:
Shared Package
ML17332A902 List:
References
NUDOCS 9508300333
Download: ML17332A903 (32)


Text

~

i

~ 1gfi A500 1

0 Cy ClO o4 c~

e"

~O

+**++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

198 License No.

DPR-58 1.

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

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated December 20,

1993, as supplemented July 19,
1994, and February 28,
1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized 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.

9508300333 950822 PDR ADQCK 050003%5, P

PDR

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:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.1 98

, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 22 i gg5 ohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

198 TO FACILI Y OPERATING LICENSE NO.

DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

J~O~V IX 3/4 8-12 3/4 8-13 3/4 8-14 3/4 8-15 3/4 8-16 3/4 8-17 3/4 8-18 3/4 8-19 3/4 8-20 B 3/4 8-1 B 3/4 8-2 INSERT IX 3/4 8-12 3/4 8-13 3/4 8-14 3/4 8-15 3/4,8-16 3/4 8-17 3/4 8-18 3/4 8-19 B 3/4 8-1 B 3/4 8-2

~

I XHDEK I ITING CO DITIONS 0

0 IO D

S V I CE E

REMENTS 2EHZQE 4

S S

(Continued) 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System..........................

Spray and/or Sprinkler Systems.

Low Pressure C02 Systems......

Halon System.

Fire Hose Stations.

3/4.7.10 FIRE RATED ASSEMBLIES 3/4 7-33 3/4 7-36 3/4 7-40 3/4 7-42 3/4 7-43 3/4 7-45 3 4 8 ELECTRICAL POWER SYST S

3/4.8.1 A.C.

SOURCES Operating.

Shutdown.

3/4 8-1 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating.

~.

A.C. Distribution - Shutdown.

D.C. Distribution - Operating.

D. C. Distribution

- Shutdown..

D.C. Distribution - Operating

- Train N Battery System.

3/4 8.3 ALTERNATIVE A.C.

POWER SOURCES..

3/4 8-10 3/4 8-11 3/4 8-12 3/4 8-15 3/4 8-16 3/4 8-19 3 4.8 9 REFUELING OPERATIONS 3/4.9.1 3/4.9.2 3/4.9.3 3/4.9'.4 3/4.9.5 BORON CONCENTRATION......

~..

INSTRUMENTATION DECAY TIME..

CONTAINMENT BUILDING PENETRATIONS COMMUNICATIONS.

3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4

~

3/4 9-5 COOK NUCLEAR PIANT - UNIT 1 IX AHENDi~lENT NO. ~,~, ] 98

~

4

~ I I

~

V

ki b

l

~

)

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS D.. DISTRIB Tl N -

PERATI IMITI CONDITIO F

R OPERATI N 3.8.2.3 The followingD.C. bus trains shall be energized and OPERABLE with tie breakers between bus trains open:

TRAIN AB consisting of250-volt D.C. bus AB, 250-volt D.C. battery bank No. 1AB, and a full capacity charger, and TRAIN CD consisting of250-volt D.C. bus CD, 250-volt D.C. battery bank No. 1CD, and a full capacity charger.

~ATTON a.

With one 250-volt D.C. bus inoperable, restore the inoperable bus to OPERABLE status within2 hours 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With one 250-volt D.C. battery and/or its charger inoperable, restore the inoperable battery and/or charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following30 hours.

VEILLANCERE UIREMENTS 4.8.2.3.1 Each D.C. bus train shall be determined OPERABLE and energized with tie breakers open at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.3.2 Each 250-volt battery bank and charger shall be demonstrated OPERABLE At least once per 7 days by verifying that:

The electrolyte level of each pilot cell is between the minimum and maximum level indicafion marks, The pilotcell specific gravity, corrected to 77'F, and fullelectrolyte level (fluid at the bottom of the maximum level indication mark), is greater than or equal to 1.200, 4,

The pilot cell voltage is greater than or equal to 2.13 volts, and The overall battery voltage is greater than or equal to 250 volts.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-12 AMENDMENT4& ~,

198

~ I

~

~

I 3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS URVEILL E RE REMENT ontinued b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.

The specific gravity, corrected to 77'F, and full electrolyte level (fluid at the bottom of the maximum level indication mark), ofeach connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

C.

At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, The cell-towell and terminal connections are clean, tight, free of corrosion and coated with anti~rrosion material, 3.

The battery charger willsupply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

At least once per 18 months, perform a battery service test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2.

The battery charger will be disconnected throughout the test.

The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this test.

e.

At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating.

When this test is performed in place of a battery service test, a modified performance test shall be conducted.

, Annual perfonnance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. Ifthe battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-13 AMENDMENTuS,m, 198

)

~

4

~

~

I 4

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS

~AB E 4 8-2 BATTERY EMER EN Y L AD AB Batte Loads Minimum Time 5.

6.

Channel IIIstatic inverter Channel IV static inverter East feed pump turbine emergency oil pump Control room emergency lighting Main turbine backup oil pump Isolation valve control Allcontrol circuits 1 hr D Batte a

1.

Channel I static inverter 2.

Channel ll static inverter 3.

BOP static inverter 4.

West feed pump turbine emergency oil pump 5.

Generator hydrogen emergency seal oil pump 6.

Main turbine emergency oil pump 7.

Isolation valves 8.

Annunciators 9.

Allcontrol circuits AC power sources to the inverters shall be turned offat the start of the test and may be turned on at the end of the specified time interval. Inverters may be left in this operating mode for the duration of the discharge test.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-14 AMENDMENT4%,

1 98 I

I I

~

I I

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4,8 ELECTRICALPOWER SYSTEMS D.C. DISTRIB N - SH D WN IMITIN NDITION F R

PERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1 - 250-volt D.C. bus, and 1 - 250-volt battery bank and charger associated with the above D.C. bus.

~ATION:

With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITYwithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

RVEILLANCERE UIREMENT 4.8.2.4.1 The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-15 AMENDMENT4&

] 98

)

~ I

r

~

~

I

~

~

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS D

. DISTRIB TI N -

PERATIN

- TRAIN BATI'ERYSY TEM IMITN DI I NF PER TI N 3.8.2.5 The followingD.C. bus train shall be energized and OPERABLE:

TRAINN consisting of250-volt D.C. bus N, 250-volt D.C. battery bank N, and a full capacity charger.

MODES 1, 2 and 3.

With the Train N battery system inoperable, declare the turbine driven Auxiliary Feedwater Pump inoperable and followthe ACTION statement of Speciflcation 3.7.1.2.

S RVEILLAN E RE REMENTS 4.8.2.5.1 The D.C. bus train N shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.5.2 The 250-volt battery bank and charger shall be demonstrated OPERABLE:

At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks, 2.

The pilot cell specific gravity, corrected to 77'F and fullelectrolyte level (fluid at the bottom of the maximum level indication mark), is greater than or equal to 1.200, The pilot cell voltage is greater than or equal to 2.13 volts, and b.

4.

The overall battery voltage is greater than or equal to 250 volts.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.

The specific gravity, corrected to 77'F and full electrolyte level (fluid at the bottom of the maximum level indication mark), of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-16 AMENDMENT4K, %5,1 9 g

I r

~ ~

I

~

~

~

~

I 3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS URVEILLANCERE IREMENT ntinued At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

2.

The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with antiworrosion material.

3.

The battery charger willsupply at least 10 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

At least once per 18 months perform a battery service test, during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the times specified of Table 4.8-3 with the battery charger disconnected.

The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout the battery service test.

At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating.

When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% from its'capacity on the previous performance test, or is below 90% of the manufacturer's rating. Ifthe battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-17

~ ~

C 4

~

~

I f

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS

~ABLE~4 ATTERY EMER EN Y LOADS Auxiliaryfeedwater turbine control bus FMO-211 valve FMO-221 valve FMO-231 valve FMO-241 valve TDTV valve Minimum Time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-18 AMENDMENT42$,

f 98

t

~

~

~

~

I 3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS

/4.8 Alternative A C P wer urc LIMITIN CONDITION FOR OPERATI N 3.8.3.1 The steady state bus voltage for the manual alternate reserve source shall be greater than or equal to 90% of the nominal bus voltage.

s *': <<>>

'(

w'uses.

ACTION:

With bus voltage less than 90% nominal, adjust load on the remaining buses to maintain steady state bus voltage greater than or equal to 90% limit.

SURVEILLANCERE IREMENTS 4.8.3.1 No additional surveillance requirements other than those required by Specifications 4.8.1.1.1 and 4.8.1.2.

Shared with D.C. Cook Unit 2.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 8-19 198

)

3/4 BASES 3/4.8 ELECTRICALPOWER SYSTEMS The OPERABILITYof the A.C. and D.C power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facilityand 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facilityoperation commensurate with the level ofdegradation.

The OPERABILITYofthe power sources are consistent with the initialcondition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C.

source.

The OPERABILITYof the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facilitycan be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facility status.

The AB and CD station battery s'ystems provide a reliable source of continuous power for supply and control of plant loads such as switchgear and annunciator control circuits, static inveriers, valve control centers, emergency lighting and motor control centers.

The design duty cycles of these batteries are composite load profiles resulting from the combination of the three hour Loss Of Coolant Accident/Loss Of Offsite Power battery load profiles and the four hour Station Blackout battery load profiles.

The train N station bat tery system provides an independent 250 volt DC power supply for power and control of the turbine driven auxiliary feedwater pump train.

The limiting conditions of operation for the train N battery are consistent with the requirements of the auxiliary feedwater system.

The surveillance requirements for the train N battery system are consistent with the requirements of the AB and CD station batteries.

The train N battery loads are derived from equipment in the turbine driven auxiliary feedwater pump train and battery sizing is consistent with the functional requirements ofthese components.

Simulated loads for battery tests are loads equivalent to measured actual loads.

COOK NUCLEAR PLANT-UNIT1 Page B 3/4 8-1 Ai~MENTg6, 1 98

3/4 BASES 3/4.8 ELECTRICALPOWER SYSTEMS Removal of accumulated water as required by 4.8.1.1.2.b.2 is performed by drawing the contents offthe bottom of the tank until acceptable results are obtained for either a tape test or a water and sediment test.

An acceptable result for the water and sediment content is a measured value less than 0.05 percent volume.

The sample specified in 4.8.1.1.2.c.4 is sent offsite for testing. A serious attempt willbe made to meet the 31-day limiton the offsite tests; however, iffor some reason this limitis not met (e.g., ifthe sample is lost or broken or ifthe results are not received in 31 days), the diesel generators should not be considered inoperable. Ifthe sample is lost, broken, or fails the offsite tests and the new oil has already been put into the storage tank, the offsite tests willbe perforined on a sample taken from the storage tank. Ifthe results on the subsequent storage tank sample are not withinspecified limits, the diesel generators should be considered OPERABLE and the outwf-spec properties should be returned to within specification as soon as possible.

If the monthly storage tank sample taken in accordance with Specification 4.8.1.1.2.d fails the particuIate contamination test, the diesel generators should be considered OPERABLE and the contamination level should be restored to below 10 mg/liter as soon as possible.

The precision leak-detection test described in Surveillance Requirement 4.8.1.1.2.f.2 should be performed as described in NFPA (National Fire Protection Association) -329.

As NFPA-329 is revised, the precision leak-detection test may be modified to incorporate changes to the test as described in the revisions to NFPA-329, The minimum required diesel fuel oil volume is 43,240 gallons.

This volume is consistent with operation of one diesel generator continuously for 7 days at rated load, as recommended in Regulatory Guide 1.137, entitled "Fuel Oil Systein for Standby Diesel Generators."

The Technical Specifications require a minimum of 46,000 gallons of fuel. The 46,000 gallons is an indicated volume. This amount includes margin for characteristics such as location of the tank discharge pipes and slope of the tanks.

COOK NUCLEAR PLANT-UNIT1 Page B 3/4 8-2 AMENDMENT4%5, 445-,

1 9 8

~

~

~

~W+~RECy+

~o ClO u)

.p

+0 q9

+w*w+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-me1 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No.

DPR-74 1.

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

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated December 20,

1993, as supplemented July 19,
1994, and February 28,
1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized 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.

L

~

r a

I

~

I l

~

f

~

I 2.

Accdrding1y, 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:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as

. revised through Amendment No. i B3

, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 22, 1995 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

~ ~

~

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE IX 3/4 8-12 3/4 8-13 3/4 8-14 3/4 8-15 3/4 8-16 3/4 8-17 3/4 8-18 3/4 8-19 3/4 8-20 B 3/4 8-1 B 3/4 8-2 INSERT IX 3/4 8-12 3/4 8-13 3/4 8-14 3/4 8-15 3/4 8-16 3/4 8-17 3/4 8-18 3/4 8-19 B 3/4 8-1 B 3/4 8-2

p I

~

~

~

'I ZHEZ LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS Q~C'ION 3 4 S

ST S (Continued)

PAGE 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System.........................,

3/4 7-27 Spray and/or Sprinkler Systems Low Pressure C02 Systems...

Halon System.............

3/4 7-30 3/4 7-34 7-36

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

3/4 Fire Hose Stations...........

~

~

~

~

~

~

~

~

~

~

~

3/4 7-37 3.4,7.10 FIRE RATED ASSEMBLIES........

4 8 ELECTRICAL OWE SYSTEMS 3/4.8.1 A.C.

SOURCES Operating.

hutdown e

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

S 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3/4 7-39 3/4 8-1 3/4 8-9 A.C. Distribution - Operating.

A.C. Distribution - Shutdown..........,..

D.C. Distribution - Operating D.C. Distribution - Shutdown......

N Battery D.C. Distribution - Operating

- Train 3/4.8.3 ALTERNATIVE A.C.

POWER SOURCES.

3 4 9 REFUELING OPERATIONS 3/4 3/4 3/4 3/4 System.

3/4 3/4 8-10 8-11 8-12 8-15 8-16 8-19 3/4.9.1 3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.5 BORON CONCENTRATIONS

INSTRUMENTATION DECAY TIME CONTAINMENT BUILDING PENETRATIONS COMMUNICATIONS 3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 COOK NUCLEAR PIANT - UNIT 2 IX AMENDMENT NO. ~ f~ f f 83

3/4.0 LIMITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS DI IB PE TI LIMITIN NDITI N F R

PERATI 3.8.2.3 The followingD.C. bus trains shall be energized and OPERABLE with tie breakers between bus trains open:

TIVEAB consisting of250-volt D.C. bus AB, 250-volt D.C. battery bank No. 2AB, and a full capacity charger, and TRAINCD consisting of250-volt D.C. bus CD, 250-volt D.C. battery bank No. 2CD, aad a full capacity charger.

PfTlgN a.

With one 250-volt D.C. bus inoperable, restore the inoperable bus to OPERABLE status within2 hours 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With one 250-volt D.C. battery and/or its charger inoperable, restore the inoperable battery and/or charger to OPERABLE status withia 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN withinthe following30 hours.

VEILLAN E RE MENT 4.8.2.3.1 Each D.C. bus traia shall be determined OPERABLE and eacrgized with tie breakers open at least once per 7 days by verifying correct breaker alignment aad indicated power availability.

4.8.2.3.2 Each 250-volt battery bank and charger shall be demonstrated OPERABLE ao At least once per 7 days by verifying that:

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks, 2.

The pilotceil speciQc gravity, corrected to 77'F, and fullelectrolyte level (Quid at the bottom of the maximum level indication mark), is greater than or equal to 1.200, 3.

4, The pilot cell voltage is greater than or equal to 2.13 volts, and The overall battery voltage is greater thaa or opal to 250 volts.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-12 AMENDMENT44.,

1 8

~

~

3/4.0 LlldITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is greater than or equal to 2.13 volts under Qoat charge.

2.

The specific gravity, corrected to 77'F, and full electrolyte level (fluid at the bottom ofthe maximum level indication mark), ofeach connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 Rom the value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

C.

At least once per 18 months by verifying that:

4 1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, The cell-~lland terminal connections are clean, tight, Bee ofcorrosion and coated with anti~rrosion material, 3.

The battery charger willsupply at least 140 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."

At least once per 18 months, perform a battery scrvicc test during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the design duty cycle which is based on the composite load profile. The composite load profile envelopes both the LOCA/LOOP and Station Blackout profiles and provides the basis for the times listed in Table 4.8-2.

The battery charger will be disconnected throughout the test.

The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout this test.

e.

At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating.

When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% fromits capacity on the previous perfonnance test, or is below 90% of the manufacturer's rating. Ifthc battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, perfonnance testing at two year intervals is acceptable until the battery shows signs of degradation.

The provisions of Specification 4.0.9 are applicable to the 2ND battery and charger.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-13 AMENDMENT~ 4A 446 183

~ ~ ii I

3/4.0 LIMITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREMENI'S 3/4.8 ELECTRICALPOWER SYSTEMS

~BLE~4+

ATTE EMER E

Y L AD B Bate ad 1.

Channel HI static inverter 2.

Channel IVstatic inverter 4.

5.

6.

7.

8.

BOP static inverter East feed pump turbine emergency oil pump Control room emergency lighting Main turbine east emergency oil pump Isolation valve control Allcontrol circuits I hr D Batte ad Channel I static inverter Channel II static inverter 3.

4, 6.

7.

West feed pump turbine emergency oil pump Generator hydrogen emergency seal air-oil pump Main turbine west emergency oil pump Isolation valves Annunciators Allcontrol circuits I

AC power sources to the inverters shall be turned offat the start of the test aud may be turned on at the end of the specified time interval.

Inverters may be left in this operating mode for the duration of the discharge test.

COOK NUCLEARPLANT-UNIT2 Page 3/4 8-14 AMENDMENTS, <83

(

~, ~P

~ e

~

~

'I 3/4.0 LIMITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREM2i'IS 3/4.8 ELECTRICALPOWER SYSTEMS Dl IB R

PE 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1 - 250-volt D.C. bus, and 1 - 250-volt battery bank and charger associated with the above D.C. bus.

~*

~T~IN:

With less than the above complement of D.C. equipment and bus OPERABLE, establish CONTAINMENT INTEGRITYwithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

VEILLAN E RE EMENT 4.8.2.4.1 The above required 250-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.

The provisions of Speci6cation 4.0.9 are applicable to the Surveillance Requirements 4.8.2.3.2.c.3 and 4.8.2.3.2.d for the 2ND battery and charger.

COOK NUCLEARPLANT-UNIT2 Page 3/4 8-15 mIENDMENTau,~,~ g p]

~ ~

~

~ ~

~

~

~

7 3/4.0 LIIVIITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS Dl B

N -

PERATIN

- TRAIN N B RY Y LIMITIN CONDITI N F R

PERATION 3.8.2.5 The followingD.C. bus train shall be energized and OPERABLE:

TRAINN consisting of250-volt D.C. bus N, 250-volt D.C. battery bank N, and a fullcapacity charger.

~*'CTI

)N With the Train N battery system inoperable, declare the turbine driven Auxiliary Feedwater Pump inoperable and follow the ACTION statement of Specification 3.7.1.2.

URVEILLAN E RE UIREMENT 4.8.2.5.1 The D.C. bus train N shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.5.2 The 250-volt battery bank and charger shall be demonstrated OPERABLE:

At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks, 2.

The pilotcell specific gravity, corrected to 77'F and fullelectrolyte level (fluidat the bottom of the maximum level indication mark), is greater than or equal to 1.200, 3.

The pilot cell voltage is greater than or equal to 2.13 volts, and 4.

The overall battery voltage is greater than or equal to 250 volts.

At least once per 92 days by verifying that:

The voltage of each connected cell is greater than or equal to 2.13 volts under float charge.

The specific gravity, corrected to 77'F and full electrolyte level (fluid at the bottom ofthe maximum level indication mark), ofeach connected cell is greater than or equal to 1.200 and has not decreased more than 0.03 from the value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the top of the minimum level indication mark and the bottom of the maximum level indication mark.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-16 AKIENDMENT~'~

I 183

3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS VEILLAN E E

IREMENTS ntinued C.

At least once per 18 months by verifying that:

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with antiworrosion material.

3.

The battery charger willsupply at least 10 amperes at greater than or equal to 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

At least once per 18 months perform a battery service test, during shutdown (MODES 5 or 6), by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status the actual or simulated emergency loads for the times specified of Table 4.8-3 with the b'attery charger disconnected.

The battery terminal voltage shall be maintained greater than or equal to 210 volts throughout the battery service test.

At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying that the battery capacity is at least 80% of the manufacturer's rating.

When this test is performed in place of a battery service test, a modified performance test shall be conducted.

Annual performance tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is below 90% of the manufacturer's rating. Ifthe battery has reached 85% of service life, delivers a capacity of 100% or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-17 AMENDMENTS,VO, 183

)

,', r II 3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS

~BLE~4 BATTERY EMER EN Y LOADS N" Ba te ad Auxiliaryfeedwater turbine control bus FMO-211 valve FMO-221 valve FMO-231 valve FMO-241 valve TDTV valve inimum Time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours COOK NUCLEAR PLANT-UNIT2 Page 3/4 8-18 AMENDMENT4N, 1 83

t t

3/4.0 LIMITINGCONDITIONFOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.8 ELECTRICALPOWER SYSTEMS

/4 l

'v>>

IM N

F R

PERA 3.8.3.1

'Ihe steady state bus voltage for the manual alternate reserve source shall be greater than or equal to 90% of the nominal bus voltage.

~*:

(

Vt" buses.

Q~lgN:

With bus voltage less than 90% nominal, adjust load on the remaining buses to maintain steady state bus voltage greater than or equal to 90% limit.

VEILLAN E RE E

E 4.8.3.1 No additional surveillance requirements other than those required by Specifications'4.8.1.1.1 and 4.8.1.2.

Shared with Cook Nuclear Plant Unit 1.

COOK NUCLEARPLANT-UNIT2 Page 3/4 8-19 mlENDMENTm,m, 183

)

3/4 BASES 3/4.8 ELECTRICALPOWER SYSTEMS The OPERABILITYof the A.C. and D.C power sources and associated distribution systems during operatioa ensures th'at sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facilityand 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facilityoperation commensurate with the level ofdegradation.

The OPERABILITYofthe power sources are consistent with the initialcondition assumptions of the accident analyses and are based upon maintaining at least one of each of the onsite A.C. aad D.C. power sources and associated distribution systems OPERABLE duriag accident conditions coincident with an assumed loss of offsite power and single failure of the other oasite A.C.

The OPERABILITYof the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facilitycan be maintained in the shutdowa or refueling condition for extended time periods and 2) sufficient instrumentation and coauol capability is available for monitoring and maintaining the facilitystatus.

The AB and CD station battery systems provide a reliable source of continuous power for supply and control of plant loads such as switchgear and annunciator control circuits, static inverters, valve control centers, emergency lighting and motor control centers.

The desiga duty cycles of these batteries are composite load profiles resulting

&om the combination of the three hour Loss Of Coolant Accident/Loss Of Offsite Power battery load p'rofiles and the four liour Station Blackout battery load profiles.

The train N station battery system provides aa indepeadent 250 volt DC power supply forpower and control of the turbine driven auxiliary feedwater pump train.

The limitiag conditions of operatioa for the train N battery are consistent with the requirements of the auxiliary feedwater system.

The surveillance requirements for the train N battery system are consistent with the requirements of the AB and CD station batteries.

The train N battery loads are derived from equipmeat in the turbine driven auxiliary feedwater pump train and battery sizing is consistent with the functional requirements of these components.

Simulated loads for battery tests are loads equivalent to measured actual loads.

COOK NUCLEAR PLANT-UNIT2 Page B 3/4 8-1 AMENDMENT&,

1 83

i IL 1

3/4 BASES 3/4,8 ELECTRICALPOWER SYSTEMS Removal of accumttiated water as required by 4.8.1.1.2.b.2 is performed by drawing the contents offthe bottom of the tank until acceptable results are obtained for either a tape test or a water and sediment test.

An acceptable result for the water and sediment content is a measured value less than 0.05 percent volume.

The sample specified in 4.8.1.1.2.c.4 is sent offsite for testing. A serious attempt willbe made to meet the 31'imit on the offsite tests; however, iffor some reason this limitis not met (e.g., ifthe sample is lost or broken or ifthe results are not received in 31 days), the diesel generators should not be considered inoperable. Ifthe sample is lost, broken, or fails the offsite tests and the new oil has already been put into the storage tank, the offsite tests willbe performed on a sample taken from the storage tank. Ifthe results on the subsequent storage tank sample are not withinspecified limits, the diesel generators should be considered OPERABLE and the outwf-spec properties should be returned to withinspecification as soon as possible.

If the monthly storage tank sample taken in accordance with Specification 4.8.1.1.2.d fails the particulate contamination test, the diesel generators should be considered OPERABLE and the contamination level should be restored to below 10 mg/liter as soon as possible.

The precision leak-detection test described in Surveillance Requirement 4.8.1.1.2.f.2 should be performed as described in NFPA (National Fire Protection Association) -329.

As NFPA-329 is revised, the precision leak-detection test may be modified to incorporate changes to the test as described in the revisions to NFPA-329.

The minimum required diesel fuel oil volume is 43,240 gallons.

This volume is consistent with operation of one diesel generator continuously for 7 days at rated load, as recommended in Regulatory Guide 1.137, entitled "Fuel Oil Systein for Standby Diesel Generators.

The Technical'Specifications require a minimum of 46,000 gallons of fuel. The 46,000 gallons is an indicated volume. This amount includes margin for characteristics such as location of the tank discharge pipes and slope of the tanks.

COOK NUCLEAR PLANT-UNIT2 Page B 3/4 8-2 AMENDMENTm, m