ML20081F637

Amends 145 & 129 to Licenses NPF-4 & NPF-7,respectively, Revising Tech Specs to Correct Certain Administrative Errors

ML20081F637
Person / Time
Site:	North Anna
Issue date:	06/04/1991
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20081F640	List: ML20081F637 ML20081F641
References
NUDOCS 9106110357
Download: ML20081F637 (21)

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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 License No. NrT 4 1.

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

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated March 18, 1991, complies with the standards and requirements of the Atomic Energy Act of 19F, as amended (the Act), and the Commission's rules and regulativ.s 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 conmon 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.

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' 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145, are hereby incorporated in the license.

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

3.

This Ticense amendment is effective as of the date of issuance and shall be implemented within 30 days.

F THE NUCLEAR REGULATORY COMMISSION

/

14.k H rbert N. Derkow, Director P oject Directorate 11-2 Division of heactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 4. 1991 l

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. _. _. ~ _ _ _ _.. _ _ _

ATTACHMENT TO LICENSE AMENDMENT NO. 145 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.

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

The corresponding overleaf pages are also provided to maintain document completeness.

Pace F 1-16 3/4 8-3c 3/4 9-12 B 3/4 1 4

REACTIVITY CONTROL SYSTEMS E0 RATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2,7 As a minimum, one of the following borated wrter sources shall be OPERABLE:

a.

A boric acid storage system and associated heat tracing with:

1.

A minimum contained borated water volume of 1378 gallons, i

2.

Between 12.950 and 15,750 ppm of boron, and

~

^ einimum solution teeperature of 115*F.

b.

The refueling water storage tank with:

1.

A minimum contained borated water volume of 51,000 gallons, 2.

Between 2300 and 2400 ppr of toron, and l

3.

A minimur solution temperature of 35*F.

?rFL C; :L!'\\:

YDDES 5 and 6.

7.,

,tt te torated water source OPERASLE, suspend all operations involvinc

CRE ALTERATIC',5 or positive reactivity changes until at least one terated water source is restored to OPERABLE status.

5 S.'E : L L 'J: EE : J 1: EME *,T S

!.1.2.7

're a:ove receired Lorated water source shall be demonstrated 0;ERAELE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration of the water, 2.

Verifying the contained borated water volume of the tank, and 3.

Verifying the '.ric 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 RL'5T temperature when it is the source of borated water and the outside air temperature is < 35*F, l

l NDR'n ANNA-U!:IT 1 3/4 1-15 Amendment t'o. 48' gg > 93,

REACTMTYCOM SYSTBAS BORATT.DWATER SOURCES OPERATNG UMmNG CONDmON FOR OPERATON 3.1.2.8 Each of the following borated water sources shall be OPERABLE:

a. A boric acid storage system and associated heat tracing with:

1.

A contained borated water volume of between 6000 and 16,280 gallons, 2.

Between 12.950 and 15,750 ppm of boron, and 3.

A minimum solution temperature of 115'F.

b. The refueling water storage tank with:

1.

A contained borated water volume of between 466,200 and 487,000 ga%ns, l

2.

Between 2300 and 2400 ppm of boron, and 3.

A solution temperature between 40'F and 50'F.

ADDUC AB!UTV. MODES 1,2. 3 and 4.

ACTICW

a. 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 nex 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 1.77%.RK 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. Witn the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour 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 />.

I SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

NORTH ANNA UNIT 1 3/4 1 16 Amendment No. 5,7f of f,93,145,

REFUEL.ING ODERATIONS SPENT FUEL PIT WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever 1rradiated fuel assemblies are in the spent fuel pit.

ACTION:

With the requirements of the specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel pit areas and place the load in a safe condition.

Restore water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The provisions of Specifi-cation 3.0.3 are not applicable.

SU?.E;. A'<E 4L22 RLMEhT5 a.9.l!

The water level in the spent fuel pit shall be determined to be at least at the minimum required depth at least once per 7 day, sher ir-radiated fuel assemblies are in the spent fuel pit.

h0:TW ANNA - UNIT 1 3/4 9-11

1 REFUELING OPERATIONS FUEL BUILDING VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 A fuel building ventilation system shall be OPERABLE and dis-charging through at least one auxiliary building HEPA filter and char-coal adsorber assembly.

APPLICABILITY:

During irradiated fuel movenent within the spent fuel pit, or a.

b.

During crane operation with loads over irradiated fuel in the spent fuel pit.

ACTION:

With a fuel building ventilation system inoperable, irradiated a.

fuel movement within the storage pool or crane operation with loads over the spent fuel pit Fay proceed provided the fuel building ventilation system is in operation and discharging through at least one train of HEPA filters and charcoal adsorber assemblies.

b.

With no fuel building ventilation system OPERABLE, suspend all operations involving movement of irradiated fuel within the spent fuel pit or crane operation with loads over the spent fuel pit until at least one fuel building ventilation system is restored to OPERABLE status, c.

The provisions of Specifications 3.0.3, 3.0.4 and 4.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel building ventilation system shall be demonstrated OPERABLE and discharging through at least one auxiliary building HEPA filter and charcoal adsorber assembly; At least once per 31 days by initiating flow through the HEPA a.

filter and charcoal adsorber assembly for 15 minutes b.

AL.least once per 18 months during system operation, by verify-ing a 1/8 inch vacuum, water gauge, relative to the outside atmosphere, and t

By performance of the Surveillance Requirements of Specifica-c.

tion 4.7.8.1 b, c, d, e and f.

NORTH ANNA - UNIT 1 3/4 9-12 Arendr.ent No. 145.

i 1

4 ELECTRICAL PCMR SGTEMS SURVEILLANCE REQUIREMENTS t

4,8.1.1.2 (continued) 7.

Verifying the diesel generator operales" for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to an indicated target value of 2950 kw (between 2900 3000 kw)"' and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to an indicated 2500 to 2600 kw."' Within 5 minutes after completing this 24 hout test, perform Surveillance Requirement 4.8.1.1.2.d.4 8.

Verifying that the auto connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3000 kw.

9.

Verifying the diesel generator's capability to:

a)Synchronite with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Proceed through its shutdown sequence.

10. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) Remote Local Selection Switch a) Emergency Stop Switch

e. At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting " both diesel generators simultaneously.

during shutoown, and verifying that both diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds, i

l "This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.

"'This band is meant as guidance to avoid routine overloading of h.a engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variations due to changing bus loads shall not invalidate the test.

NORTH ANNA UNIT 1 3/4 8 3c Amendrnent flo. P3.145 l

REACT]V}TY CONTROL SYSTEMS EASES 3/4.1.2 BORAT10N SYSTEMS (Continued)

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

Allowable out-of-service periods ensure that minor componer.t repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.

The boration capabioity of either system is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.77% ak/k af ter xenon decay and cooldown to 200'F.

This expected boration capability requirement occurs at EOL f rom full power equilibrium xenon conditions and requires 6,000 gallons of 12,950 ppm borated water from the boric acid storage tankt or 54,200 gallens V 2300 rpm bcrated water from the refueling water storage tank.

The limitation for a maximum of one centrifugal charging pump to be lOPERABLEandtheSurveillanceRequirementtoverifyallchargingpumpsexcept

! the required OPERABLE pu' p to be inoperable below 324'F provides assurance l

l that a rass addition pressure transient can be relieved by the operation of a single p0RV.

With the P'S temperature below 200'F, one injection system is acceptable

, f' without single failure consideration on the basis of the stable reactivity ll condition of the reactor and the additional restrictions prohibiting CORE j;ALTE: ATIONS and positive reactivity change in the event the single injection

' system becomes inoperable.

i I!;'

The boron capability recaired below 200*F is sufficient to provide a l l; SHUTDonN MARGIN of 1.77% tn /k af ter xenon decay and cooldown from 200'F i

140:r, 7 tis condition requires either 1378 gallons of 12,950 ppm borated j l water from the boric acid storage tanks or 3400 gallons of 2300 ppm borated il water from the refueling water storage tank.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The OPEPABILITY of one boron injection system during REFUELING insures that this system is available for reactivity control while in MODE 6, l

l NORT" ANNA - UNIT 1 B 3/4 1-3 Amendment No, f, If, f2, N,ll

l REACTMTY CONTROL SYSTB4 iMSES 3/41.2 BORATION SYSTEMS (Continued)

The limits on contained water volume and boron concentration of the RWST ensure a pH value et between 7,7 and 9.0 for the solution recirculated within the containment after a LOCA.

This pH minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress i

corrosion on mechanical systems and components.

At least one charging pump must remain operable at all times when the opposite unit is in MODE 1. 2, 3, or 4.

This is required to maintain the charging pump cross-cont'ect system operational.

3'413 MOVABLE CONTROL ASSEVBL!ES The specifications of this section (1) ensure that acceptable power distribution limits are mahtained, (2) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit i

l the potential effects of rod misalignment on associated accident analyses. OPERABILITY of the movable control assemblies is established by observing rod motion and determining that rods are positioned within : 12 steps (indicated position) of the respective demand step counter position. The OPERABILITY of the indrvidual rod position indication system is established by appropriate perode CHANNEL CHECKS, CHANNEL FUNCTIONAL TESTS, and CHANNEL CALIBRATIONS, OPERABILITY of the individual rod position indicators is required to determine control rod position and thereby ensure compliance with the control rod alignment and insenion limits. The OPERABLE cendition for the individual rod position indicators is defined as being l

capable of indicating rod position within : 12 steps of the associated demand position indicator, For power levels below 50 percent of RATED THERMAL POWER, the specifications of this section permit a maximum one hour in every 24 stabilization period (thermal ' soak time") to allow stabilization of known thermal drift in the indtvidual rod position indicator cunrvis during which time the indicated rod positiore may vary from demand position indic4 tion by no more than : 24 steps. This *1 in 24* feature is an upper limit on the frequency of thermal soak allowances and is available both for a continuous one hour period or one consisting of several discrete intervals. During this stabilization period, greater reliance is placed upon the demand position indicators to determine rod position, In addition, the : 24 step / hour limit is not applicable when the control rod position is known to be greater than 12 steps from the rod group step counter demand posrtion indication. Above 50 percent of RATED THERMAL POWER, rod motion is not expected to induce thermal transients of sufficient magnitude to exceed the individual rod position indicator instrument accuracy of : 12 steps. Comparison of the demand position indicators to the bank insertion Umits with venfication of rod position by the individual rod position indicators (after thermal soak following rod motion below 50 percent of RATED THERMAL POWER) is sufficient verification that the control rods are above the insartion

limits, NORTH ANNA UNIT 1 B 3/4 1-4 Amendrent No. If,N,7??,145, i

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Y VIRGINIA ELECTRIC AND POWER COMPAN OLD DOMINION ELECTRIC COOPERATIVE DOCKFT No. 50-339 UNIT NO. 2 NORTH ANNA POWER ST ATION 4

SE AMENDMENT TO FACILITY OPERATING LICE Amendment No.123 License No. NPF 7 (the Commission) has found that:

The Nuclear Regulatory Commissioni ia Electric and Power Company, complies with the The application for amendment by Virg n 1.

18, 1991, ic Energy Act of 1954, as et al., (the licensee) dated March rules and regulations Fet A.

standards and requirements of the Atomamende forth in 10 CFR Chapter I; rules and regulations ofity with the f

The facility will operate in con orm h

the provisions of the Act, and t e B.

activities authorized the Comission; assurance (i) that thed without eridengering the health

) that such activities will be There is reaionab' by this amenwent can be cer.ducteand saf ety of t C.

i s; conducted in ;ompliance be inimical to the comon The issuance 9f this amendment will notlth and safety of t defense and sicurity or to the hea D.

ccordance with 10 CFR Part The issuance of this amendment is in ad all applicable and 51 of the Commission's regulations an E.

have been satisfied.

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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. NPF-7 1.

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

A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated March 18, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without ender.gering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

_ _ _ ~.

_ _ _ _ _ _ _ _ _ _ _ ~

2 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specificatioy The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 129

, are hereby incorporated in the license. The ;icensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION O

k H rbert N. Berkow, Director Project Directorate !!-2 Division of Reactor Pro.iects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 4, 1991 l

l

ATTACHMEf4T TO LICENSE AMENDMENT NO. 129 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendir "A" Technical Specifications with the enclosed pages as indicated.

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

The corresponding overleaf pages are also provided to maintain document

ompleteness.

Paae F1-9 3/4 1-14 3/4 4-E F 3/4 1 4 l

l l

REACTMTY CONTROL SYSTEMS FLOW PATHS. OPERATING UMITING CONDITION FOR OPERATON i

3.1.2.2 At least two of the following three 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.

b. Two flow paths from the refueling water storage tank vial charging pumps to the Reactor Coolant System.

APPL!CABILITY: MODES 1,2. 3, and 4#.

ACTCN:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE. restore at least two boron injection flow paths to the Reactor Coolant 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 and borated to a SHUTD MARGIN equivalent to at least 1.77% delta k/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 at least two flow paths to OPERABLE status within the nex17 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 />.

SURVElLLNCE REQUIREMENTS 4.1.2.2 Ear; cf the above require:: flow patris shall be cemonstrated OPERABLE:

a. At least once per 7 days by ventying that the temperature of the heat traced porton of the tiow path from the boric acid tanks is greater than or equal to 115'F when it is a required water source.

l

• Only one boron injection flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 340*F.

NORTH ANNA UNIT 2 3/4 19 AmendmentMo. H

129, l

_ _ _ - - - _. - _ - _. _ _ _ _ _ _.._. _ _. - _ _ _. _ _ _ _ _. _ _ _ _. _ -. ~.

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQb!REMENTS (Continued) 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, At least once per 18 months during shutdown by verifying that each c.

automatic valve in the flow path actuates to its correct position ori a safety injection test signal.

NORTH ANNA - UNIT 2 3/4 1-10

REACTIVITY CONTROL SYSTEMS BOR/.TED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

A boric acid storage system and at least one associated heat tracing a.

system with:

1.

A minimum contained borated water volume of 1378 gallons, 2.

Between 12.950 and 15,750 ppm of boron, and 3.

A minimum solution temperature of Il5'F.

b.

The refueling water storage tank with:

1.

A minimum contained borated water volume of 51,000 gallons, 2,

Setween 2300 and 2000 ppm of boron, and 3.

A minimum solution temperature of 35*F.

APPLICABILITY: MODES 5 and 6.

A_C T I C'c With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one borated water source is restored to OPERABLE status.

i SURVEILLANCE REQU,IREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

At least once per 7 days by:

a.

1.

Verifying the boron concentration of the water, i

l 2.

Verifying the contained borated water volume of the tank, and 3.

Verifying the boric acid storage tank solution temperature when it is the source of borated water, t

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 and the outside air temperature is l

less than 35'F.

NDRTH ANNA - UNIT 2 3/4 1-13 Amendment No. 54, 78 l

I F.EM T!v!T( CONTRDL SYSTEMS BORATED WATER SOURCES - 0FERATING LIMITING CONDITION FOR OPERATION l

3.1.2.8 As a minimu5 the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:

A boric acid storage system and at least one associated heat tracing a.

system with:

1.

A contained borated water volume of between 6000 and 16.280

gallons, 2.

Between 12,950 and 15,750 ppm of boron, and 3.

A minimu" solution temperature of 115'F.

t.

The refueling water storage tank with:

1.

A contained borated water volume of between 466,200 and 487,000

gallons, 2.

Between 2300 and 2 0 0 ppm of boron, and 3.

A solution temperature between 40'F and 50'F.

A,2? l:AM LITY:

MODES 1, 2, 3 and 4 i

A: TIN a.

Witn the beric acid storage system inoperable and being used as one of the above required berated water sources, restore the storage syste-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 HDT STANDEY 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 e;uivalent to at least 1.771 tk/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 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 />.

NORTH ANNA - UNIT 2 3/4 1-14 Amendment No. 54, 3 129,

REACTOR COOLANTSWmiM ISOLATED LOOP STARTUP UMITING CONDrDON FOR OPERATION 3.4.1.5 A reactor coolant loop cold leg stop valve shall remain closed until:

a. The isolated loop has been operating on a recirculatbn flow greater than or equal to 125 gpm for at least 90 minutes and the temperature at the cold leg of the isolated loop is within 20'F of the highest cold leg temperature of the operating

loops,

b. The reactor is suberitical by at least 1.77 percent akA.

ADDUCA9fuTV. ALL MODES.

ACTION With the requirements of the above specification not satisfied, suspend startup of the isolated loop.

SURVElLLANCE REQUIREMENTS 4.4.1.5.1 The isolated loop cold leg temperature shall be determined to be within 20'F of the highest cold leg temperature of the operating loops within 30 minutes prior to opening the cold leg stop vatve.

4.4.1.5.2 The reactor shall be determir ed to be subcritical by at least 1.77 percent ak/k within 30 minutes prior to opening the colC leg stop valve.

l NORTH ANNA UNIT 2 3/8 45 Amendment No. 129 1

REACTOR COOL 4U SYST9A SAEETY VALVES SHL7DOWN UMrTING. CONDITION FOR ODERATION 1

3.4.2 A innmnum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 PSIG 3.1%*

APPLICABlUTY: MODE 4.

I ACTOJ:

With no pressurizer code safety valve OPERABLE,immediately suspend all operations involving positive reactivity changes and place an OPERABLE RHR loop into operation.

SURVE!LLANCE REO'J:RE? !ENTS 4.4.2 No aditional Sur<e; nan:e Requirements other than those required by Specification 4.0.5.

i

• The hh setting pressure shall correspond to ambient condition of the vatve at nominal operating temperature and pressure.

l NORTH ANNA UNIT 2 3/4 46 Amencment No. 124, l

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t REACTIVITY CONTROL SYSTE*S BASES 3/4.1.2 ECUT10h SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required toperformthisfunctioninclude1)boratedwatersources,2)chargingpumps,

3) separate flo. paths, 4) boric acid transfer pumps, 5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200'F, a minimum of two boren injection flow patts a e re;,,, ired to ensure single functional capability in the event an assunec failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN MRSIN from expected operation conditions of 1.771 delta k/k after xenon decay l

and cooldoon to 200'F. The maximum expected boration capability requirement occurs at EOL frem full power equilibrium xenon conditions and requires g.,

6000 gallers of 12.950 ppm borated water from the boric acid storage tanks or 5*,20; gallons of 2300 ppm berated water from the refueling water l

stora;e tank.

With the RCS temperature below 200'F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity ccnditiet of the reactor and the additional restrictions prohibiting CORE ALTERATION 5 and positive reactivity change in the event the single injection system becomes inoperatie.

The lirritatien for a maximum. of one centrifugal charging pump to be OPERAh! and the Surveillance Requirement to verify all charging pumps except the re::vited OPERABLE pump to be inoperable below 340'F provides assurance that a mass ad::ition pressure transient can be relieved by the operation of a single PORV.

The baron capability required below 200'F is sufficient to provide a SHUTDOWN MAR 3IN of 1.77 delta k/k after xenon decay and cooldown from 200'F to 140'F. This condition requires either 1378 gallons of 12.950 ppm berated water from the beric acid storage tanks or 3400 gallons of 2300 ppm borated water from the refueling water storage tank.

NORTH ANNA - UNIT 2 B 3/4 1-3 Amendment No. S'd,76 t

l APR '.41SE i

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REACTMTY CONTROL SYSTEMS IMSES 3 4 il BORATION SYSTEMS f Connnuem The contained water volume limrts include allowance for water not available because et discharge line locaten and other physical characteristes. The OPERABILITY of one boron injection system dunno REFUELING insures that this system is available for reactivity control while in MODE 6.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.7 and 9.0 for the solution recirculated within the containment after a l

LOCA. This pH minimizes the evoluton of cdine and minimizes the effect of chlorde and caustic stress corrosion on meenancal systems and components.

At least one charging Pump must remain operable at all times when the opposite Unit is in l

MODE 1, 2, 3, or 4.

This is required to maintain the charging pump Cross connect system operational.

1411 MOVABLE CONTROL ASSEM9UES The specificatens of this secten (1) ensure that acceptable power distribution limits are maintained, (2) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident anatyses. OPERABILITY of the movable control assemblies is established by observing rod motion and determining that rods are positioned within : 12 steps (indicated positen) of the respective demand step counter position. The OPERABILITY of the individual rod position indication system is established by appropriate penodic CHANNEL CHECKS, CHANNEL FUNCTIONAL TESTS, and CHANNEL CAllBRATIONS. OPERABILITY of the indrvidual red positen indcators is required to determine control rod positen and thereby ensure compliance with the control rod alignment and insertion limits. The OPERABLE conditen for the individual rod posttion indicators is defined as being capable of indicating rod positen within : 12 steos of the associated demand position indcator.

For power levels below 50 percent of RATED THERMAL POWER. the specifications of this section permit a maximum one hour stabilization in every 24 period (thermal

• soak time') to allow stabilization of known thermal drift in the individual rod position indicator channels dunng whch time the indcated rod position may vary from demand position indcation by no more than : 24 steps, This *1 in 24' feature is an upper limit on the frequency of thermal soak allowances and is available both for a continuous one hour period or one consisting of i

several discrete intervals. Dunng this stabilizaten penod, greater reliance is placed upon the demand pos4 tion indicators to determine rod position. in addition, the : 24 step / hour limit is not appicable when the control rod position is known to be greater than 12 steps from the rod j

group step counter demand position indcaton. Above 50 percent of RATED THERMAL POWER.

i rod motion is not expected to induce thermal transients of sufficient magnitude to exceed the j

indtvidual rod position indcator instrument accuracy of 12 steps Comparison of the demand position indicators to the bank insertion limits with verification of rod positen by the individual rod position indicators (after thermal soak following rod motion below 50 percent of, a

RATED THERMAL POWER) is sufficient venfcation that the control rods are above the insenen limits.

j NORTH ANNA UNIT 2 B 3/4 14 Amendment No. 122.129, l

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