ML17334B652

Amends 216 & 200 to Licenses DPR-58 & DPR-74,respectively, Revising TS to Increase Min Borated Water Volume in Boric Acid Storage Sys & Decreasing Required Boron Concentration

ML17334B652
Person / Time
Site:	Cook
Issue date:	08/07/1997
From:	John Hickman NRC (Affiliation Not Assigned)
To:
Shared Package
ML17333A980	List: ML17333A979 ML17333A982 ML17334B652
References
NUDOCS 9708150284
Download: ML17334B652 (48)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated February 29,

1996, and supplemented November 15,

1996, and February 4,

1997, 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 f'orth 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; 2.

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.

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:

9708i50284 970807 PDR ADQCK 05000315 P

PDR

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Technical S ecifications 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 216

, are hereby incorporated in the license.

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

This 44cense amendment is effective as of the date of issuance, with full implementation when the required plant modifications are completed, but not later than August 31, '1998.

FOR THE NUCLEAR REGULATORY COMMISSION ohn B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issua'nce:

August 7, 1997 t

ATTACHMENT TO LICENSE AMENDMENT NO. 216 TO FACILITY 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.

REMOVE IV IX 3/4 1-1 3/4 1-3 3/4 1-7 3/4 1-9 3/4 1-10 3/4 1-15 3/4 1-16 3/4 9-1 3/4 10-1 B 3/4 1-2 B 3/4 1-3 INSERT IV IX 3/4 1-1 3/4 1-3 3/4 1-7 3/4 1-9 3/4 1-10 3/4 1-15 3/4 1-16 3/4 9-1 3/4 10-1 8 3/4 1-2 B 3/4 1-3

INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY.

3/4.1 REACTIVITYCONTROL SYSTEMS 3/4 0-1 3/4.1.1 BORATION CONTROL 3/4.1.2 Shutdown Margin - TAVG Greater Than 200'F.

Shutdown Margin - TAVG Less Than or Equal to 200'F Boron Dilution....

Moderator Temperature Coefficient Minimum Temperature for Criticality BORATION SYSTEMS 3/4 1-1 3/4 1-3

.3/4 IP 3/4 1-5 3/4 1-6 3/4.1.3 Flow Paths Sllutdown o

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Flow Paths - Operating...

Charging Pumps - Shutdown

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Charging Pumps - Operating Boric Acid Transfer Pumps - Shutdown Boric Acid Transfer Pumps - Operating Borated Water Sources - Shutdown Borated Water Sources - Operating MOVABLECONTROL ASSEMBLIES 3/4 1-7 3/4 1-9 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 1-16 Group Height

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Position Indicator Channels Rod Drop Time Shutdown Rod Insertion Limit Control Rod Insertion Limits 3/4 1-18 3/4 1-20 3/4 1-21 3/4 1-22 3/4 1-23 COOK NUCLEARPLANT-UNIT1 AMENDMENT~,420,216

INDEX LIMA'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.8 ELECTRICALPOWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating Shutdown 3/4 8-1 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTIONSYSTEMS 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 ALTERNATIVEA.C. POWER SOURCES 3/4.9 REFUELING OPERATIONS

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3/4 8-10 3/4 8-11 3/4 8-12 3/4 8-15 3/4 8-16 3/4 8-19 3/4.9.1 BORON CONCENTRATION

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3/4 9 1

3/4.9.2 INSTRUMENTATION 3/4.9.3 DECAY TIME 3/4.9.4 CONTAINMENTBUILDINGPENETRATIONS 3/4 9.5 COMMUNICATIONS 3/4 9-2 3/4 9-3 3/4 94

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3/4 9-5 COOK NUCLEARPLANT-UNITI AMENDMENTQ3, 4%, ~, IVAN, 408, ~,216

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS, 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - TAVG GREATER THAN 200'F LIMITINGCONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGINshall be greater than or equal to 1.3% Delta k/k.

a

'*'CTION:

With the SHUTDOWN MARGINless than 1.3% Delta k/k, immediately initiate and continue boration at greater than or equal to 34 gpm of a solution containing greater than or equal to 6,550 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCERE UIREMENTS 4.1.1.1.1 The SHUTDOWN MARGINshall be determined to be greater than or equal to 1.3% Delta k/k:

Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGINshall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s).

When in MODE 1 or MODE 2 with Keffgreater than or equal to 1.0, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdrawal is within the limits of Specification 3.1.3.5.

C.

When in MODE 2 with Keff less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticalityby verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.5.

Prior to initialoperation above 5% RATEDTHERMALPOWER af'ter each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limitof Specification 3.1.3.5.

~See Special Test Exception 3. 10.1.

COOK NUCLEARPLANT-UNIT1 Page 3/4 1-1 AMENDMENTV4, 420, 448, 244, 216

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS SHUTDOWN MARGIN - TAVG LESS THAN OR E UALTO 200'F LIMITINGCONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGINshall be greater than or equal to 1.0% Delta k/k.

APPLICABILITY:

MODE 5.

ACTION:

With the SHUTDOWN MARGINless than 1.0% Delta k/k, immediately initiate and continue boration at greater than or equal to 34 gpm of a solution containing greater than or equal to 6,550 ppm boron or equivalent until the required SHUTDOWN MARGINis restored.

SURVEILLANCERE UIREMENTS 4.1.1.2 The SHUTDOWN MARGINshall be determined to be greater than or equal to 1.0% Delta k/k:

Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGINshall be verified acceptable with an increased allowance for the withdrawn worth ofthe immovable or untrippable control rod(s).

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

2.

3.

Reactor coolant system boron concentration, Control rod position, Reactor coolant system average temperature, Fuel burnup based on gross thermal energy generation, Xenon concentration, and Samarium concentration.

COOK NUCLEARPLANT-UNIT1 Page 3/4 1-3 AMENDMENT~, 448, 216

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN IMITINGCONDITION FOR OPERATION As a minimum, one of the following boron injection flow paths shall be OPERABLE:

A flowpath from the boric acid tanks via a boric acid transfer pump and charging pump to the Reactor Coolant System ifonly the boric acid storage tank in Specification 3.1.2.7a is OPERABLE, or The fiowpath from the refueling water storage tank via a charging pump to the Reactor Coolant System if only the refueling water storage tank in Specification 3.1.2.7b is OPERABLE.

'*'ODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE, suspend all operations'involving CORE ALTERATIONS or positive reactivity changes* until at least one injection path is restored to OPERABLE status.

SURVEILLANCERE UIREMENTS At least one of the above required flow paths shall be demonstrated OPERABLE:

At least once per 7 days by verifying that the temperatures of the areas containing the flow path components from the boric acid tank to the blending tee are greater than or equal to 63'F when a flow path from the boric acid tanks is used.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

<<For purposes of this specification, addition of water from the RWST does not constitute positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 1-7 AMENDMENT4A, 444, 216

3/4 LIMH'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS FLOW PATHS - OPERATING LIMITINGCONDITION FOR OPERATION 3.1.2.2 Each of the following boron injection flow paths shall be OPERABLE:

a.

The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System, and The flowpath from the refueling water storage tank via a charging pump to the Reactor Coolant System.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:'0 With the flowpath from the boric acid tanks inoperable, restore the inoperable flowpath to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBYand borated to a SHUTDOWN MARGIN equivalent to at least 1% hk/k at 200'F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the flowpath to OPERABLE status within the'next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the flowpath from the refueling water storage tank inoperable, restore the flowpath to OPERABLE status within one hour 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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCERE UIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperatures of the areas containing the flow path components from the boric acid tank to the blending tee are greater than or equal to 63'F.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on an RWST sequencing signal.

d.

At least once per 18 months during shutdown by verifying that the flowpath required by specification 3.1.2.2.a delivers at least 34 gpm to the Reactor Coolant System.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 1-9 AMENDMENT444, 216

THIS PAGE INTENTIONALLYLEFT BLANK COOK NUCLEAR PLANT-UNIT1 Page 3/4 1-10 AMENDMENT444, 216

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

I A boric acid storage system with:

1.

A minimum usable borated water volume of 5000 gallons, 2.

Between 6,550 and 6,990 ppm of boron, and 3.

A minimum solution temperature of 63'F.

1.

2.

3.

The refueling water storage tank with:

A minimum usable borated water volume of 90,000 gallons, A minimum boron concentration of 2400 ppm, and A minimum solution temperature of 70'F.

APPLICABILITY:

ACTION:

MODES 5 and 6.

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONSor positive reactivity changes~ until at least one borated water source is restored to OPERABLE status.

SURVEILLANCERE UIREMENTS

'.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by 1.

2.

3.

Verifying the boron concentration of the water, Verifying the water level volume of the tank, and Verifying the boric acid storage tank solution temperature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water.

~For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

COOK NUCLEARPLANT-UNIT1 Page 3/4 1-15 AMENDMENT&, 444, 244, 216

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITINGCONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:

ao A boric acid storage system with:

1.

A minimum usable borated water volume of 8,500 gallons,~

2.

Between 6,550 and 6,990 ppm of boron, and 3.

A minimum solution temperature of 63'F.

The refueling water storage tank with:

1.

A minimum contained volume of 350,000 gallons of water, 2.

Between 2400 and 2600 ppm of boron, and 3.

A minimum solution temperature of 70'F.

MODES 1, 2, 3 and 4.

ACTION:

With the boric acid storage system inoperable, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGINequivalent to at least 1% hk/k at 200'F; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour 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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCERE UIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

~Not required when borated water is injected into the RCS to meet SHUTDOWN MARGINrequirements of MODES 3 and 4.

COOK NUCLEARPLANT-UNIT1 Page 3/4 1-16 AMENDMENT40, ~, Rk4, 216

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3/4 LIMIT'INGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIIMMENTS 3/4.9 REFUELING OPERATIONS ORO CONCENTRATION LIMITINGCONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

ao b.

Either a~ of0.95 or less, which includes a 1% hldk conservative allowance for uncertainties, or A boron concentration of grcatcr than or equal to 2400 ppm, which includes a 50 ppm conservative allowance for uncertainties.

~CTION:

With the requirements ofthc above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 34 gpm of 6,550 ppm boric acid solution or its equivalent until~ is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm, whichever is thc more restrictive.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCERE UIREMENTS 4.9.1.1 The morc restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position, 4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by chemical analysis at least 3 times per 7 days with a maximum time interval between samples of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Thc reactor shall bc maintained in MODE 6 when thc reactor vessel head is unbolted or removed.

For purposes of this specification, addition of water f'rom the RWST docs not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2,7.b.2.

COOK NUCLEAR PLANT-UNIT1 Page 3/4 9-1 AMENDMENT440, 216

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREKKNTS 3/4.10 SPECIAL TEST EXCEFHONS SHUTDOWN MARGIN IMITING ONDITIO FOR OPER TION 3.10.1 The SHUTDOWN MARGIN requirement'f Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod(s).

~CTION:

aO With the reactor critical~ R 1.0) and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at R 34 gpm of 6,550 ppm boric acid solution or its equivalent until the SHUTDOWNMARGINrequired by Specification 3.1.1.1 is restored, b.

With the reactor subcritical ~ ( 1.0) by less than the above reactivity equivalent, immediately initiate and continue boration at 2 34 gpm of6,550 ppm boric acid solution or its equivalent until the SHUTDOWN MARGINrequired by Specification 3.1.1.1 is restored.

SURVEILLANCERE UIREMENTS 4.10.1.1 4.10.1.2 The position ofeach fulllength rod either partially or fullywithdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Each fulllength rod not fullyinserted shall be demonstrated OPERABLE by verifying its rod drop time to be 6 2.4 seconds within7 days priorto reducing the SHUTDOWN MARGINto less than the limits of Specification 3.1.1.1.

COOK NUCLEARPLANT-UNIT1 Page 3/4 10-1 AAKNDBKNTV4, 4Q, 216

3/4 BASES 3/4.1 REACITVITYCONTROL SYSTEMS

/41.1.4 MODERATOR TEMPERATURE COEFFICIENT TC Continued concentration associated with fuel burnup. Thc confirmation that thc measured and appropriately compeasated MTC value is within the allowable tolerance ofthe predicted value pmvides additional assurances that the coefficieat will be maintained within its limits during intervals between mcastiictaent.

/4.1.1.5 MINIMUMTEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolaat System average temperature less than 541'F. This limitationis required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentatioa is within its normal operating range, and 3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RTicn temperature.

Administrative procedures willbe established to ensure the P-12 blocked functions are unblocked before tahng the reactor critical.

/4 1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation, The componeats required to perform this function include 1) borated water sources, 2) charging pumps,

3) separate flow paths, 4) boric acid transfer pumps, aad 5) an emergency power supply from OPERABLE diesel geacrators.

Withthe RCS average temperature above 200'F, a minimum oftwo separate and redundant boron injectioa systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable.

Allowable outwf-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety fmm injection system failures during the repair period.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to,verify all charging pumps and safety injection pumps except the required OPERABLE charging pump, to be inoperable below 152'F, unless the reactor vessel head is removed, provides assuraacc that a mass addition pressure transient can be relieved by the operation of a single PORV.

The boration capability of either system is sufficient to pmvide the required SHUTDOWN MARGIN fmm all operating conditions after xenon decay and cooldown to 200'F. The maximum expected boration capability, usable volume requirement, is 8500 gallons of 6550 ppm borated water from the boric acid storage tanks for pmviding required SHUTDOWN MARGINafter xenon decay and cooldown to 547'F and additional borated water from a second boric acid tank, or hatching tank, or refueling water storage tank for further cooldown to.200'F. With the refueling water storage tank as the only source, based on conservative calculations, a maximum of 99598 gallons of2400 ppm borated water is required.

The minimum contained RWST volume is based on ECCS considerations.

See Section B 3/4.5.5.

COOK NUCLEAR PLANT-UNIT1 Page B 3/4 1-2 AMENDMENT4A, 447, 216

3/4 BASES 3/4.1 REACTIVITYCONTROL SYSTEMS

/4.1.2 BORATION SY MS ontinucd With the RCS average tctnperature above 200'F, one injection system is acceptable without single failure consideration on the basis ofthe stable reactivity condition of thc reactor and the additional restrictions prohibiting CORE ALTERATIONSand positive reactivity change in the event the single injection system becomes inoperable.

The boration capability required below 200'F is sufficient to provide a SHUTDOWN MARGINof 1% 6 k/kafter xenon decay and cooldown fmm 200'F to 140'F. This condition requires either 900 gallons of 6,SSO ppm boratcd

- water fmm the boric acid storage tanks or 3265 gallons of2400 ppm boratcd water fmm the refueling water storage tank. The boric acid storage tank boration source volume ofTechnical Specification 3.12.7 has been conservatively increased to 5,000 gallons. 'Ihe charging Qowpath ofUnit 1 required for Unit2 shutdown support ensures that flow is available to Unit 2 and atidresses the requirements of 10 CFR 50 Appendix R.

The Qowpath consists of a charging pump powered from an electrical bus and associated water supplies and delivery system.

Fire watches posted in the affected opposite unit areas (i.c., Unit2 areas requiring use ofthc Unit 1 charging system in the event ofa fire) may serve as the equivalent shutdown capability specified inthe action statements ofSpecification 3.1.2.3.

In thc affected areas, either establish continuous fire watches or verify the OPERABILITYof fire'detectors per Specification 4.3.3.7 and establish hourly fire watch patrols. 'Ihe required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfillingits intended Appendix R alternate safe shutdown function have been established and are included in a plant pmccdure.

An additional plant procedure details how the above noted fire watches willbe implenicnted.

The limitson contained water volume and bomn concentration ofthe RWST also ensure a pH value ofbetween 7.6 and 9.5 for the solution recirculated withincontainment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on meciianical systems and components.

L S E LIES

'Ihe OPERABILITYof bomn injection system during REFUEUNG ensures that this system is available for reactivity control while in MODE 6.

/4.1.

OV BLE 0 The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGINis maintained, and (3) the potential effects of md ejection accident arc COOK NUCLEARPLANT-UNIT1 Page B 3/4 1-3 AMENDMENTSS, 440. 484; 216

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2OO License No. DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated February 29,

1996, and supplemented November 15,

1996, and February 4,

1997, 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 2.

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.

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:

Technical S ecifications 3.

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 200

, are hereby incorporated in the license.

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

This license amendment is. effective as of the date of issuance, with full implementation when the required plant modifications are completed, but not later than August 31, 1998.

FOR THE NUCLEAR REGULATORY COMMISSION ohn B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance.

Augus~ 7, 1997

ATTACHMENT TO LICENSE AMENDMENT NO, 200 FACIL'ITY 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 IV IX 3/4 1-1 3/4 1-3 3/4 1-8 3/4 1-9 3/4 1-10 3/4 1-15 3/4 1-16 3/4 9-1 3/4 10-1 B 3/4 1-2 B 3/4 1-3 INSERT

'IV IX 3/4 1-1 3/4 1-3 3/4 1-8 3/4 1-9 3/4'1-10 3/4 1-15 3/4 1-16 3/4 9-1 3/4 10-1 B 3/4 1-2 B 3/4 1-3

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INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY..

3/4 0-1 3/4.1 REACTIVITYCONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - TAVG Greater Than 200'F....

Shutdown Margin - TAVG Less Than or Equal to 200'F Boron Dilution Moderator Temperature Coefficient Minimum Temperature for Criticality..

3/4.1.2 BORATION SYSTEMS 3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-7 Flow Paths - Shutdown Flow Paths - Operating Charging Pumps - Shutdown...

Charging Pumps - Operating...

Boric Acid Transfer Pumps - Shutdown Boric Acid Transfer Pumps - Operating Borated Water Sources - Shutdown Borated Water Sources - Operating 3/4.1.3 MOVABLECONTROL ASSEMBLIES 3/4 1-8 3/4 1-9 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 1-16 Group Height Position Indicator Channels - Operating Rod Drop Time..

Shutdown Rod Insertion Limit.

Control Rod Insertion Limits..

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3/4 1-18 3/4 1-21 3/4 1-23 3/4 1-24 3/4 1-25 COOK NUCLEARPLANT-UNIT2 AMENDMENT$Q, 4%, 404, 200

INDEX LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.8 ELECTRICALPOWER SYSTEMS 3/4.8.1, A.C. SOURCES Operating Shutdown 3/4.8.2 ONSITE POWER DISTRIBUTIONSYSTEMS 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 8-1 3/4 8-9 3/4 8-10 3/4 8-11 3/4 8-12 3/4 8-15 3/4 8-16 3/4.8.3 ALTERNATIVEA.C. POWER SOURCES 3/4 8-19 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4.9.2 INSTRUMENTATION 3/4.9.3 DECAY TIME.

3/4.9.4 CONTAINMENTBUILDINGPENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4 9-1 3/4 9-2 3/4 9-3 3/4 94 3/4 9-5 COOK NUCLEAR PLANT-UNIT2 AMENDMENT448, 486, 4N, 492> 200

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN T v GREATER THAN 200 F LIMITINGCONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGINshall be greater than or equal to 1.3% Delta k/k.

APPLICABILITY:

MODES 1, 2~, 3, and 4.

ACTION:

With the, SHUTDOWN MARGINless than 1.3% Delta k/k, immediately initiate and continue boration at greater than or equal to 34 gpm of a solution containing greater than or equal to 6,550 ppm boron or equivalent until the required SHUTDOWN MARGINis restored.

SURVEILLANCERE UIREMENTS 4.1.1.1.1 The SHUTDOWN MARGINshall be determined to be greater than or equal to 1.3% Delta k/k:

Within one hour after detection of an inoperable control rod(s) and at least onc'e per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGINshall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s).

b.

When in MODE 1 or MODE 2 with K,>> greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6.

C.

When in MODE 2 with K,>> less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticalityby verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6.

Prior to initial operation above 5% RATEDTHERMALPOWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limitof Specification 3.1.3.6.

~See Special Test Exception 3.10.1.

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3/4 LIMITINGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIIKMIMIS 3/4.1 REACITVI'IYCONTROL SYSTEMS OWN MARGIN-ESS TH R

L 2

'F IMITINGCONDITION FOR OPER N

3.1.1.2 Ihe SHUTDOWN MARGINshall be greater than or opaI to 1.0% Delta k/k.

LQEE With the SHUTDOWN MARGINless than 1.0% Delta k/k, hnnediately hitiate and continue boration at greater than or equal to 34 gpm of a solution containing greater than or equal to 6+50 ppm boron or etpivalent until the xeguited SHUTDOWN MARGiNis restored.

4.1.1.2 The SHUTDOWN MARGINshall be detetnnned to be greater than or apal to 1.0% Delta k/k:

a Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the md(s) is inopetible.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGINshall be verified acceptable with an increased allowance for the withdrawn worth ofthe immovable or untrippable control sod(s).

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration ofthe following factors:

2.

3.

4.

5.

6.

Reactor coolant system boron concentration, Control md position, Reactor coolant system average temperature, Fuel burnup based on gross thermal energy generation, Xenon concetttruion, and Samarium concentration.

COOK NUCLEARPLANT-UNIT2 Page 3/4 1-3 AMENDMENTS2,$ 7, 8$ >~, 200

0 3/4 LIMH'INGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCOYIROL SYSTEMS

/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN IMITINGCONDITION FOR OPERATION'.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE:

a.

A flowpath from the boric acid tanks via a boric acid transfer pump and charging pump to the Reactor Coolant System if only the boric acid storage tank in Specification 3.1.2.7.a is OPERABLE, or b.

The flowpath from the refueling water storage tank via a charging pump to the Reactor Coolant System ifonly the refueling water storage tank in Specification 3.1.2.7.b is OPERABLE.

~CTION:

With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.

SURVEILLANCERE UIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

aO At least once per 7 days by verifying that the temperatures of the areas containing the flow path components &om the boric acid tank to the blending tee are greater than or equal to 63'F when a flowpath fmm the boric acid tanks is used.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

For purposes of this specification, addition of water from the RWST does not constitute positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

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3/4 LI14GTING CONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REAC'IIVH'YCONTROL SYSTEMS FLOW PATHS - OPERATING LIMITINGCONDITION FOR OPERATION 3.1.2.2 Each of the following boron injection flow paths shall be OPERABLE:

The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System, and The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System.

APPLICABILITY:

ACTION:

MODES 1, 2,'3 and 4.

With the flowpath from the boric acid tanks inoperable, restore the inoperable flowpath to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBYand borated to a SHUTDOWN MARGIN equivalent to at least 1%.hk/k at 200'F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the flowpath to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the flowpath from the refueling water storage tank inoperable, restore the flowpath to OPERABLE status within one hour 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'following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCERE UIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperatures of the areas containing the flow path components from the boric acid tank to the blending tee are greater than or equal to 63'F.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a RWST sequencing signal.

d.

~ -At least once per 18 months during shutdown by verifying that the flowpath required by specification 3.1.2.2.a delivers at least 34 gpm to the Reactor Coolant System.

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0 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS THIS PAGE INTENTIONALLYLEFT BLANK COOK NUCLEARPLANT-UNIT2 Page 3/4 1-10 AMENDMENT 200

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REAC'IIVHYCONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITINGCONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

b.

APPLICABILITY:

A boric acid storage system with:

l.

A minimum usable borated water volume of 5,000 gallons, 2.

Between 6,550 and 6,990 ppm of boron, and 3.

A minimum solution temperature of 63'F.

The refueling water storage tank with:

l.

A minimum usable borated water volume of 90,000 gallons, 2.

A minimum boron concentration of 2400 ppm, and 3.

A minimum solution temperature of 70'F.

MODES 5 and 6.

~CTION:

With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONSor positive reactivity changes until at least one borated water source is restored to OPERABLE status.

SURVEILLANCERE UIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

At least once per 7 days by:

2.

Verifying the boron concentration of the water, Verifying the contained borated water volume, and Verifyingthe boric acid storage tank solution temperature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water.

'For purposes of this specification, addition of water from the RWST does not constitute a dilution activity provided the boron concentration in the RWST is greater than or equal to the minimum required by Specification 3.1.2.7.b.2.

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.1 REACTIVITYCONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITINGCONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:

a.

boric acid storage system with:

1.

A minimum contained borated water volume of 8500 gallons,~

2.

Between 6,550 and 6,990 ppm of boron, and 3.

A minimum solution temperature of 63'F.

The refueling water storage tank with:

1.

A minimum contained borated water volume of 350,000 gallons of water, APPLICABILITY:

2.

Between 2400 and 2600 ppm of boron, and 3.

A minimum solution temperature of 70'F.

MODES 1, 2, 3 and 4.

ACTION:

ae With the boric acid storage system inoperable, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 1% Delta k/k at 200'F; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour 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 following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCERE UIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

~Not required when borated water is injected into the RCS to meet SHUTDOWN MARGINrequirements of MODES 3 and 4.

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIIMHENTS 3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITINGCONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained unifotm and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

ae Either a~ of 0.95 or less, which includes a 1% dddk consetvative allowance foruncertainties, 01'.

A boron concentration of greater than or equal to 2400 ppm, which includes a 50 ppm conservative allowance for uncertainties.

MODE 6.

~CTION:

With the requirements ofthe above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 34 gpm of 6,550 ppm boric acid solution or its equivalent until~ is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2400 ppm; whichever is the more restrictive.

The provisions of Specification 3.0.3 are not applicable.

URVEILLANCERE UIREMENTS 4.9.1.1 aO The more restrictive of the above two reactivity conditions shall be determined prior to:

Removing or unbolting the reactor vessel head, and b.

Withdrawal ofany fulllength control rod in excess of3 feet from its fullyinserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration ofthe reactor coolant system and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The reactor shall be maintained in MODE 6 when the reactor vessel head is unbolted or removed.

"For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

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3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.10 SPECIAL TEST EXCEFIIONS SH OWN MARGIN IMITINGCONDITION FOR OPERATION 3.10.1

'Ihe SHUTDOWN MARGINrequirement of Specification 3.1.1.1 may be suspended for measurement of contml rod worth and shutdown margin provided the reactivity equivalent to at least the highest estimated contml rod worth is available for trip insertion for OPERABLE control rod(s).

~CT~IN:

ao b.

With any full length control rod not fully inserted and with less than the above reactivity equivalent availablc for trip insertion, immediately initiate and continue boration at R 34 gpm of 6,550 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

With all full length control rods inserted and thc reactor subcritical by less than thc above reactivity equivalent, immediately initiate and continue boration at R 34 gpm of6,550 ppm boric acid solution or its equivalent until the SHUTDOWN MARGINrequired by Specificatio 3.1.1.1 is restored.

SURVEILLANCERE UIREMENTS 4.10.1.1

'Ihe position ofeach fulllength rod either partially or fullywithdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 Each fulllength rod not fullyinserted shall be demonstrated capable offuu insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGINto less than the limits of Specification 3.1.1.1.

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3/4 BASES 3/4.1 REACIIVITYCONTROL SYSTEMS 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT T

The limitations on MTC are provided to ensure that the value of this coefficient retnains within the limiting conditions assumed for this parameter in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification ofMTCvalues at conditions other than those explicitlystated willrequire extrapolation to those conditions in order to permit an accurate comparison.

It is confirmed by cycle specific neutronic analyses that the value ofthe MTCat EOC, HZP (Allrods in) is greater than thc value at EOC, HFP (Allrods out), thus assuring that the surveillance at the latter condition is adequate to maintain MTC within safety analysis assumptions.

The surveillance requirements for measurement of thc MTC at the beginning and near thc end of each fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly duc principally to thc reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.5 MINIMUMTEMPERATURE FOR CRITICALITY

'Ms specification ensures that thc reactor will not be made critical with the Reactor Coolant System average temperature less than 541'F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is capable ofbeing in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT~ temperature.

Administrative procedures willbe established to ensure the P-12 blocked functions arc unblocked before taking the reactor critical.

3/4 1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.

The components required to perform this function include 1) borated water sources, 2) charging pumps,

3) separate flow paths, 4) boric acid transfer pumps, and 5) an emergency power supply from OPERABLE diesel generators.

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3/4 BASES 3/4.1 REACTIVITYCONTROL SYSTEMS

/4.1.2 BORATION SYSTEMS Continued With the RCS average temperature above 200'F, a minimum oftwo separate and redundant boron injection systems are provided to ensure single functional capability in the event aa assumed failure renders one of the systems inoperable.

Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facilitysafety fmm injection system failures during thc repair period.

The limitationfor maximum ofone centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verif all charging pumps and safety injection pumps, except the required OPERABLE charging pump, to be inoperable below 152'F, unless the reactor vessel head is removed, provides assurance that a mass addition pressure transient caa be relieved by the operation of a single PORV.

The boration capability ofeither system is sufficient to provide the required SHUTDOWN MARGINfmm expected operating conditions after xenon decay and cooldown to 200'F. Thc maximum expected boration capability, usable volume requirement, is 8500 gallons of 6550 ppm borated water from the boric acid storage taaks for providing required SHUTDOWN MARGINafter xenon decay and cooldown to 547'F aad additional borated water from a second boric acid tank, or batching tank, or refueling water storage tank for further cooldown to 200'F. With the refueling water storage taak as the only source, based on conservative calculations, a maximum of 69215 gallons of2400 ppm borated water is required. The minimum RWST boron concentration required by the post-LOCA long-term cooling analysis is 2400 ppm. The minimum contained RWST volume is based oa ECCS considerations.

See Section B 3/4.5.5.

With thc RCS average temperature below 200'F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONSand positive reactivity change in the event the single injection system becomes inoperable.

The boron capability required below 200'F is sufficien to provide the required MODE 5 SHUTDOWN MARGIN after xenon decay and cooldown fmm 200;F to 140'F. This condition requires usable volumes ofeither 900 gallons of 6,550 ppm borated water from the boric acid storage tanks or 3265 gallons ofbotated water from the refueling.

water storage tank.

The boration source volumes of Technical Specification 3.1.2.7 have been conservatively increased to 5,000 gallons from the boric acid storage tanks and 90,000 gallons fmm thc refueling water storage tank.

The limits on contained water volume and boron concentration ofthe RWST also ensure a pH value ofbetween 7.6 aad 9.5 for the solution recirculated within containment af'ter a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

'Ihe OPERABILITYof boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

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