Text

Amends 68 & 54 to Licenses NPF-4 & NPF-7,respectively, Reducing Boron Concentration in Boron Injection Tank & Concentrated Boric Acid Sys
	ML20135H378
Person / Time
Site:	North Anna
Issue date:	09/09/1985
From:	Butcher E; Office of Nuclear Reactor Regulation
To:	;
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W UNITED STATES p

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p NUCLEAR REGULATORY COMMISSION 5

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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.68 1

I License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company, et kl., (the licensee) dated March 11, 1985, 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 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 (1) that the activities authorized by this amendment can be conducted without endangering the health

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and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i

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 Comission's regulations and all applicable requirements have been satisfied.

y DR 38 PDR

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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 8, as revised through Amendment No. 68 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1

Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 9, 1985 4

1 l

ATTACHMENT TO LICENSE AMENDMENT NO. 68 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.

Page 3/4 1-1 3/4 1-3 3/4 1-8 3/4 1-9 3/4 1-15 3/4 1-16 3/4 5-7 3/4 5-8 3/4 9-1 3/4 10-1 B 3/4 1-3 B 3/4 5-2 b

e 6

6

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,,,> 200*F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be 1 77% Ak/k.

1 APPLICABILITY: MODES 1, 2*, 3, and 4.

ACTION:

With the SHlTTDOWN MARGIN < 1.77% Ak/k, imediately initiate and continue boration at 1 0 gpm of 12,950 ppm boric acid solution or equivalent l

1 until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be 1 77% Ak/k:

1 a.

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

If the inoperable control rod is imovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the j

immovable or untrippable control rod (s).

b.

When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying j

that control bank withdrawal is within the limits of Specifica-tion 3.1.3.6.

c.

When in MODE 2##, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor

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criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1

With K,ff 1

10

1. With K,ff <1.0 e

NORTH ANNA-UNIT 1 3/4 1-1 Amendment No. 68 g

_ _ - = _. _ _ -. _ _ _ _ -. _. - _

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

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

e.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor coolant system boron concentration, 2.

Control rod position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

1 4.1.1.1.2 The overall core reactivity balance shall be compared to 1

predicted values to demonstrate agreement within + 1% Ak/k at least once This com'arison shall consider 1

per 31 Effective Full Power Days (EFPD).

p at least those factors stated in Specification 4.1.1.1.1.e. above.

The predicted reactivity values shall be adjusted (normalized) to corre-spond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

i t

1 I

i l

l NORTH ANNA-UNIT 1 3/4 1-2 l

l

REACTIVITY CONTROL SYSTEMS avc 200*F SHUTDOWN MARGIN - T LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be > 1.77% Ak/k.

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN < l.77% Ak/k, immediately initiate and continue boration at > 10 gpm of 12.950 ppm boric acid solution or l

equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be > 1.77% Ak/k:

a.

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

If the inoperable control rod is imovable or untrip-pable, the SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the 1 movable or untrippable control rod (s).

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following i

factors:

1.

Reactor coolant system boron concentration, 2.

Control rod position, 3.

Reactor coolant system average temperature.

4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

NORTH ANNA-UNIT 1 3/41-3 Amendment No. 68

REACTIVITY CONTROL SYSTEMS BORON DILUTION REACTOR COOLANT FLOW LIMITING CONDITION FOR OPERATION 3.1.1.3.1 The flow rate of reactor coolant through the reactor coolant system shall be > 3000 gpm whenever a reduction in Reactor Coolant System boron concentratTon is being made.

APPLICABILITY: All MODES.

ACTION:

With the flow rate of reactor coolant through the reactor coolant system

< 3000 gpm, innediately suspend all operations involving a reduction in boron concentration of the Reactor Coolant System.

1 SURVEILLANCE REQUIREMENTS i

i 4.1.1.3.1 The flow rate of reactor coolant through the reactor coolant j

system shall be determined to be > 3000 gpm within one hour prior to the start of and at least once per holir during a reduction in the Reactor

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j Coolant System boron concentration by either:

l a.

Verifying at least one reactor coolant pump is in operation.

l or b.

Verifying that at least one RHR pump is in operation and sup-

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plying >_ 3000 gpm through the reactor coolant system.

l i

l s

i NORTH ANNA-UNIT 1 3/4 1-4 l

REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CON 9tTION FOR OPERATION p

3.1.1.5 The Reactor Coolant System lowest operating loop temperature.

T,yg, shall be > 541*F.

APPLICABILITY: MODES 1 and 2.

ACTION:

With a Reactor Coolant System operating loop temperature. T,yg, < 541*F, restore T,yg to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE REOUIREMENTS 4.1.1.5 The Reactor Coolant System temperature. T,yg, shall be detemined to be y,541*F:

a.

Within 15 minutes prior to achieving reactor criticality, and b.

At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T is less than 547'F with the Deviation Alam All reset.

T,yg - Tyf 1

With X,ff > 1.0.

e' l

i NORTH ANNA-UNIT 1 3/4 1-7

=. -

REACTIVITY CONTROL SYSTEMS I

j 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN t

LIMITING CONDITION FOR OPERATION 1

3.1.2.1 As a minimum, one of the following boron injection flow paths l

shall be OPERABLE:

4 i

a.

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

The flow path from the refueling water storage tank via a charging j

pump to the Reactor Coolant System if only the refueling water storage tank in Specification 3.1.2.7b is 0PERABLE.

+

APPLICABILITY: MODES 5 and 6.

ACTION:

t With none of the above flow paths OPERABLE, suspend all operations involv-ing CORE ALTERATIONS or positive reactivity changes until at least one 2

1 injection path is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demon-strated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path is > 115'F when a flow l

j path from the boric acid tanks is used.

b.

At least once per 31 days be verifying that each valve (manual, e

power operated or automatic) in the flow path that is not locked.

l sealed, or otherwise secured in position, is in its correct

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position.

NORTH ANNA-UNIT 1 3/41-8 Amendment No. 68

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION r,

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3.1.2.2 Each of the following boron injection flow paths shall be OPERA 8LE:

i 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 l

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b.

The flow path from the refueling water storage tank via a i

j.

charging pump to the Reactor Coolant System.

APPLICA8ILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the flow path from the boric acid tanks inoperable, restore the inoperable flow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAND 8Y and borated to a SHUTDOWN MARGIN equivalent to at least 1.77% Ak/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the flow path to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

}

b.

With the flow path from the refueling water storage tank l

inoperable, restore the flow path to OPERABLE status within one hour or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS i

l l

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 temperature of the heat traced portion of the flow path from the boric acid t

i tanks is > 115'F.

l t

nly one boron injection flow path is required to be OPERABLE whenever 0

the temperature of one or more of the RCS cold legs is less than or equal to 320*F.

I NORTH ANNA-UNIT 1 3/4 1-9 AmendmentNo.ff.68 g

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow psth 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 i

each automatic valve in the flow path actuates to its correct j

position on a safety injection test signal.

L j

4 e

9e e

l NORTH ANNA-UNIT 1 3/4 1-10

,. _, n,,--- - - -,, _,..., _ -. - - - - -,,.., -.

--,,,n--.

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERA 8LE:

a.

A boric acid storage system and associated heat tracing with:

1.

A minimum contained borated water volume of 1378 gallons, l

2.

Between 12,950 and 15,750 ppe of boron, and g

3.

A minimum solution temperature of 115'F.

l

~-

b.

The refueling water storage tank with:

1.

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

Between 2000 and 2100 ppa'of boron, and 3.

A minimum solution temperature of 35'F.

APPLICABILITY: MODES 5 and 6.

ACTION:

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.

SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration of the water.

I 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.

b.

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

temperature is < 35*F.

('.-

NORTH ANNA-UNIT 1 3/4 1-15 Amendment No. 48' 68 8

REACTIViTV CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING l

LIMITING CONDITION FOR OPERATION 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 l

16.280 gallons, 2.

Between 12.950 and 15,750 ppm of boron, and l

3.

A minimum solution temperature of 115'F.

l b.

The refueling water storage tank with:

1.

A contained borated water. volume of between 475,058 and 487.000 gallons, 2.

Between 2000 and 2100 ppm of boron, and 3.

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

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the bor.ic acid storage system inoperable, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least 1.77% Ak/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 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT-DOWN within she following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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. J6,68

= - - - - -. -

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EERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM e

l BORON INJECTION TANK

.. d i

LIMITING CONDITION FOR OPERATION i

i 3.5.4.1 The boron injection tank shall be OPERABLE with:

i a.

A contained borated water volume of at least 900 i

gallons, b.

Between 12,950 and 15,750 ppm of boron, and l

l c.

A minimum solution temperature of 115'F.

l

,l i

APPLICABILITY: MODES 1, 2 and 3.

j j

i ACTION:

With the boron injection tank inoperable, reatore the tank to OPERABLE j

i status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT STAND 6Y arJ borated to a SHUT 00WN i

1 MARGIN equivalent to 1.775 ak/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i SURVEILLANCE REQUIREMENTS l

1 i

4.5.4.1 The boron injection tank shall be demonstrated OPERABLE by a.

Verifying the contained borated water volume at least once per i

7 days, i

l b.

Verifying the boron concentration of the water in the tank at i

least once per 7 days, and c.

Verifying the water temperature at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I l

NORTH ANNA-UNIT i 3/4 5-7 Amendment No. 68 P

i I,_-._...~_._--.

ENERGENCY CORE COOLING SYSTEMS HEAT TRACING j

LIMITING CONDITION FOR OPERATION 1

3.5.4.2 At least two independent channels of heat tracing shall be j

OPERABLE for the boron injection tank and for the heat traced portions of j

the associated flow paths.

1 APPLICABILITY: MODES 1, 2 and 3.

j ACTION:

With only one channel of heat tracing on either the boron injection tank or on the heat traced portion of an associated flow path OPERABLE, operation may continue for up to 30 days provided the tank and flow path l

temperatures are verified to be > 115'F at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; l

l i

otherwise, be in H0T SHUTDOWN wiThin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l i

SURVEILLANCE REQUIREMENTS 1

I l

4.5.4.2 Each heat tracing channel for the boron injection tank and i

associated flow path shall be demonstrated OPERABLE:

a.

At least once per 31 days by energizing each heat tracing i

channel, and l

l b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the tank and flow l

l path temperatures to be > 115'F. The tank temperature l

shall be determined by measurement. The flow path temperature shall be detemined by either measurement or recirculation flow l

until establishment of equilibrium temperatures within the tank.

I NORTH ANNA-UNIT 1 3/4 5-8 Amendment No. 68 r

+

3/4.9 REFUELING OPERATIONS i

e BORON CONCENTRATION LIMITING CONDITION FOR OPERATION i

i i

3.9.1 With the reactor vessel head unbolted or removed, the boron concen-i tration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained unifom and sufficient to ensure that the more restrictive of the following reactivity conditions is met:

j 4

)

servative IIfowance.95 or less, which includes a 11 Ak/k con-Either a K of 0 a.

for uncertainties, or b.

A boron concentration of 12000 ppe, which includes a 50 ppm conservative allowance for uncertainties.

APPLICABILITY: MODE 6*.

1 l

ACTION:

With the requirements of the above specification not satisfied, imedi-l ately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at > 10 gpm of t 12.950 ppm boric acid solution or its equivalent untti I is reduced to l

j

< 0.95 or the boron concentration is restored to > 2000 ppNfwhichever is

}

the more restrictive. The provisions of Specification 3.0.3 are not i

applicable.

SURVEILLANCE REQUIREMENTS l

I 4.9.1.1 The more restrictive of the above two reactivity conditions shall i

be detemined prior to:

I Removing or unbolting the reactor vessel head, and a.

I b.

Withdrawal of any full length control rod located within the reactor pressure vessel, in excess of 3 feet from its fully 1

i inserted position.

i

)

4.9.1.2 The boron concentration of the reactor coolant system and the l

refueling canal shall be detemined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

l I

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

NORTH ANNA - UNIT 1 3/4 9-1 Amendment No. 68 i

i i

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REFUELING OPERATIONS INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment.

APPLICABILITY: MODE 6.

ACTION:

With the requirements of the above specification not satisfied, im-mediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

.4.9.2 Each source range neutron flux monitor shall be demonstrated j

OPERABLE by performance of:

a.

A CHANNEL FUNCTIONAL TEST at lasst once per 7 days, and b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and c.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE AL-TERATIONS.

i l

NORTH ANNA - UNIT 1 3/4 9-2

1 3/4.10 SPECIAL TEST EXCEPTIONS i-i SHUTDOWN MARGIN

)

LIMITING CONDITION FOR OPERATION 2

3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and SHUTDOWN MARGIN provided the readtivity equivalent to at least the highest estimated j

control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY: MODE 2.

i 1

ACTION:

j a.

With any full length control rod not fully inserted and with less i

than the above reactivity equivalent available for trip insertion.

initiate and continue boration at > 10 gpm of at least 12.950 ppm j

i boric acid solution or its equivalint until the SHUTDOWN MARGIN j

required by Specification 3.1.1.1.is restored.

j b.

With all full length control rods inserted and the reactor sub-t critical by less than the above reactivity equivalent, imediately i

initiate and continue boration at > 10 gym of at least 12.950 ppm l

boric acid solution or its equivalint until the SHUTDOWN MARGIN i

j required by Specification 3.1.1.1 is restored.

i l

SURVEILLANCE REQUIREMENTS l

4.10.1.1 The position of each full length rod either partially or fully i

withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod that is not fully inserted shall be demonstrated capable of full insertion when tripped from at least 50%

withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTOOWN MARGIN

{

to less than the limits of Specification 3.1.1.1.

l I

i i

L NORTH ANNA - UNIT 1 3/4 10-1 Amendment No.Mi' 63 4

l

SPECIAL TEST EXCEPTIONS GROUP HEIGHT INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6. 3.2.1 and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:

The THERMAL POWER is maintained < 85% of RATED THERMAL POWER, a.

and b.

The limits of Specifications 3.2.2 and 3.2.3 are maintained and detennined at tha frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE 1.

ACTION:

With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6 3.2.1 and 3.2.4 are suspended, either:

) i-Reduce THERMAL POWER sufficient to satisfy the ACTION require-a.

ments of Specifications 3.2.2 and 3.2.3, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be detennined to be < 85% of RATED THERMAL POWER at least once per hour during PHYSICS TEITS.

4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be performed at the following frequencies during PHYS!CS TESTS:

a.

Specification 4.2.2 - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Specification 4.2.3 - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NCRTH ANNA - UNIT 1 3/4 10-2 Amendment No. 16 x

l REACTIVITY CONTROL SYSTEMS BASES r

t 3/4.1.2 BORATION 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 i

minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures l

during the repair period.

The boration capability of either system is sufficient to provide a SIRITDOWN MARGIN from expected operating conditions of 1.77% Ak/k after xenon decay and cooldown to 200'F. This expected boration capability requirement occurs at E0L from full power equilibrium menon conditions and requires 6000 gallons of 12.950 ppm borated water from the boric l

acid storage tanks or 70,000 gallons of 2000 ppm borated water from the refueling water storage tank.

The linitation for a maximum of one centrifugal charging pep to be OPERA 8LE and the Surveillance Requirement to verify all charging i

pumps except the required OPERABLE pump to be inoperable below 320 F i

provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

With the RCS temperature below 200*F. one injection system is acceptable without single failure consideration on the basis of the stable reactivity condLtion of the reactor and the additional restric-tions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The boron capability required below 200*F is sufficient to provide i

a SHUTDOWN MARGIN of 1.775 Ak/k after xenon decay and cooldown from 200*F to 140'F. This condition requires either 1378 gallons of 12,950 ppm l

borated water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated water from the refueling water storage tank.

i The contained water volume limits include allowance for water not available because of discharge line location and other physical character-istics. The OPERABILITY of one boron injection system during REFUELING insures that this system is available for reactivity control while in j

90DE 6.

NORTH ANNA - UNIT 1 8 3/4 1-3 Amendment No. 5.M*68

REACTIVITY CONTROL SYSTEMS i..

BASES

~

j

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3/4.1.2 80 RATION SYSTEMS (Continued)

The limits on contained water volume and boron concentration of the

.I RWST also ensure a pH value of between 8.5 and 11.0 for the solution f

recirculated within the containment after a LOCA. This pH minimizes the l

i evolution of iodine and minimizes the effect of chloride and caustic 4

i stress 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 i

charging pump cross-connect system operational.

I j

3/4.1. 3 M0VABLE CONTROL ASSEM8 LIES The specifications of this section ensure that (1) acceptable power i

distribution limits are maintained. (2) the minimum SHUTDOWN MARGIN is j

maintained, and (3) limit the potent.ial effects of rod misalignment on j

associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby j

e ensure compliance with the control rod alignment and insertion limits.

l The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires j

measurement of peaking factors or a restriction in THERMAL POWER; either j

of these restrictions provides assurance of fuel rod integrity during continued operation.

In addition those accident analyses affected by

}

a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

i t

i Control rod positions and OPERA 81LITY of the rod position indicators

[

i are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with i

more frequent verifications required if an automatic monitoring channel j

is inoperable.

These verification frequencies are adequate for assuring i

i that the applicable LCO's are satisfied.

The maximum rod drop time restriction is consistent with the assumed roddgoptimeusedintheaccidentanalyses. Measurement with T

2. 500 F and with all reactor coolant pumps operating ensures thaP9 the measured drop times will be representative of insertion times j

j experienced during a reactor trip at operating conditions.

I NORTH ANNA UNIT 1 83/41-4 Amendment No. M. 24 1l l

l

3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES p

3/4.5.1' ACCUMULATORS The OPERABILITY of each RCS accumulator ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.

The accumulator power operated isolation valves are considered to be

" operating bypasses" in the context of.IEEE Std. 279-1971 which requires that bypasses of a protective function be removed automatically whenever I

permissive conditions are not met.

In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limits for operation with an accumulator inoperab'le for any reason except an isolation valve closed minimizes the time exposure of the i

plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS l

The OPERASILITY of two independent ECCS subsystems ensures that suf-i ficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the l

accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all post-ulated break sizes ranging from the double ended break of the largest l

RCS cold leg pipe downward.

In addition, each ECCS subsystem provides l

l long term core cooling capability in the recirculation mode during the 3

accident recovery period.

NORTH ANNA - UNIT 1 8 3/4 5-1

EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 350*F. one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirments.

The limitation for a maximum of one centrifugal charging pump and one low head safety injection pump to be OPERABLE and the Surveillance i

Requirement to verify all charging pumps and low head safety injection pumps excepi, the required OPERA 8LE pump to be inoperable below 320*F provides assurance that a mass addition pressure transient can be

.j relieved by the operation of a single PORV..

l The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem 0PERABILITY is maintained.

3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the boron injection system as part of the ECCS i

ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.

l The limits on injection tank minimum contained volume and boron concentra-j tion ensure that the assumptions used in the steam line break analysis are met.

l The OPERABILITY of the redundant heat tracing channels associated with the beron injection system ensure that the solubility of the boron solution will be maintained above the solubility limit of 111*F at 15,750 ppm l

l boron.

NORTH ANNA - UNIT 1 8 3/4 5-2 Amendment No. Me 68 i

i i

..,___....~,---,,_m,___,

-.---,__,-r_

UNITED STATES NUCLEAR REGULATORY COMMISSION D

WASHINGTON, D. C. 20655 j

i VIRGINIA ELECTRIC AND POWER COMPANY I

OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 i

NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE d

I Amendment No. 54 License No. NPF-7 l

i j

1.

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

1 l

A.

The application for amendment by Virginia Electric and Power Company,

{

et al., (the licensee) dated March 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, 4

as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application.

l the provisions of the Act, and the rules and regulations of l

the Consission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorized 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 Comission's regulations; i

D.

The issuance of this amendment will not be inimical to the comon l

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 j

have been satisfied.

L i

k l

I-1

~

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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COP 911SSION Edward J. Butcher, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 9,1985 e

i e

h

l 4

=

ATTACHMENT TO LICENSE AMENDMENT NO.54 i

TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 i

i 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.

N 3/4 1-1 3/4 1-3 3/4 1-8 3/4 1-9 3/4 1-13 3/4 1-14 4

3/4 5-8 3/4 5-9 3/4 9-1 3/4 10-1 8 3/4 1-3 e

B 3/4 5-2 1

I l

l I

,!,,_-_...~.-

i 4

3/4.1 REACTIVITY CONTROL SYSTEMS l

3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T GREATER THAN 200'F avo i

LIMITING CONDITION FOR OPERATION e,

3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77% Ak/k.

APPLICABILITY: MODES 1, 2*, 3, and 4.

ACTION:'

With the SHUTDOWN MARGIN less than 1.77% delta k/k, imediately initiate and i

continue boration at greater than or equal to 10 gpm of a solution containing

' 1 greater than or equal to 12.950 ppe boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS c

4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal i

to 1.771 delta k/k:

i a.

Within one hour after detection of an inoperable control rod (s) and j

i at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is imovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least l

equal to,the withdrawn worth of the insnovab,le or untrippable control l

7 rod (s) 1 b.

When in M00E 1 or MODE 2 with K,ff greater than cr equal to 1.0, l

< at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6.

When in MODE 2 with K,ff less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to c.

achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1 i

NORTH ANNA - UNIT 2 3/4 1-1 Amen'dment No. 54

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.._____,_________,,,,___,.-,_,,..._._m._,

= _.

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, hy consideration of the factors of a below, with the control banks at the maximum insertion limit of Specification 3.1.3.6.

e.

When in MODES 3 or 4. at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months hy consideration of the following factors:

1.

Reactor coolant system boron concentration.

2.

Control rod position.

3.

Reactor coolant system average temperature.

4.

Fuel burnup based on gross thermal energy generation.

5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 11 Ak/k at least once per 31 Effective Full Power Days (EFPD). This compariso'n shall consider et least those factors stated in Specification 4.1.1.1.1.e. above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

l NORTH ANNA - UNIT 2 3/4 1-2

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,yg LESS THAN OR EQUAL TO 200'F SURVEILLANCE REQUIREMENTS 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1.77% delta k/k.

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 1.77% delta k/k, immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 12,950 ppm boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS

~

4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.77% 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s).

b.

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

1.

Reactor coolant system boron concentration, 2.

Control rod position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thernal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

s NORTH ANNA - UNIT 2 3/4 1-3 Amendment No.54 l

REACTIVITY CONTROL SYSTEMS BORON DILUTION VALVE POSITION LIMITING CONDITION FOR OPERATION 3.1.1.3 The following valves shall be locked, sealed or otherwise secured in the closed position except during planned boron dilution or makeup activities:

a.

2-CH-140 or b.

2-CH-160, 2-CH-156 FCV-2114B and FCV-21138.

APPLICABILITY _: MODES 3, 4, 5, and 6.

ACTION:

~

With the above valves not locked, sealed or otherwise secured in the closed position: 1) suspend all operations involving positive reactivity changes or CORE ALTERATIONS, 2) lock, seal or otherwise secure the valves in the closed position within 15 minutes, and 3) verify that the SHUTDOWN MARGIN is greater than or equal to 1.77% delta k/k within 60 minutes.

SURVEILLANCE REQUIREMENTS 4.1.1.3 The above listed valves shall be verified to be locked, sealed or i

otherwise secured in the closed position within 15 minutes after a planned l

boron dilution or makeup activity.

l 1

il' NORTH ANNA - UNIT 2 3/4 1-4

-. =

REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.5 The Reactor Coolant System lowest operating loop temperature T,yg, shall be greater than or equal to 541*F.

APPLICA8ILITY: MODES 1 and 2 ".

ACTION:

With a Reactor Coolant System operating loop temperature. T,yg, less than 541*F, restore T,yg to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.1.1.5 The Reactor Coolant System temperature. T,yg, shall be determined to be greater than or equal to 541*F:

a.

Within 15 minutes prior to achieving reactor criticality, and b.

At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T,yg is less than 547'F, with the T,yg - Tref Deviation Alann not reset.

With K,ff greater than or equal to 1.0.

See Special. Test Exception 3.10.3.

l NORTH ANNA - UNIT 2 3/4 1-7

REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTDOWN

_ LIMITING CONDITION FOR OPERATION 1

3.1. 2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE:

A flow path from the boric acid tanks via a boric acid transfer pump a.

through a 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 flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if only the refueling water storage tank in Specification,3.1.2.7.b. is OPERABLE.

APPLICABILITY: MODES 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 C

path is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS l

l 4.1. 2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

~

a.

At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path is greater than or equal to 115'F l l

when a flow path from the boric acid tanks is used.

l 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.

NORTH ANNA - UNIT 2 3/4 1-8 Amendment No.

54 l

i i

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 2

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 via charging pumps to the Reactor Coolant System.

APPLICABILITY: MODES 1. 2, 3 and 4.

ACTION:

l 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN I

equivalent to at least 1% delta k/k at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; i

restore at least two flow paths to OPERABLE status within the next 7 days er be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l SURVEILLANCE REQUIREMENTS 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 temperature of the heat traced portion of the flow path from the boric acid tanks is greater than or equal to 115'F when it is a required water source.

l

nly one boron injection flow path is required to be OPERABLE whenever 0

the temperature of one or more of the RCS cold legs is less than or equal to 340*F.

i' NORTH ANNA - UNIT 2 3/41-9 Amendment No. 54

.n-,

,,..---n_

REACTIVITY CONTROL SYSTEMS

_ SURVEILLANCE REQUIREMENTS (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.

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 safety injection test signal.

O e

O

- N*

NORTH ANNA - UNIT 2 3/4 1-10 l

l

I>

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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources si.all be OPERABLE:

a.

A boric acid storage system and at least one associated heat tracing system with:

1.

A minimum contained borated water volume of 1378 gallons, 1

2.

Between 12.950 and 15,750 ppm of boron, and g

3.

A minimum solution temperature of 115*F.

l b.

The refueling water storage tank with:

1.

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

~

2.

Between 2000 and 2100 ppm of boron, and 3.

A minimum solution temperature of 35'F.

APPLICABILITY: MODES 5 and 6.

ACTION:

l 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.

SURVEILLANCE REQUIREMENTS 4.1.2.7 l

The above required borated water source shall be demonstrated OPERABLE:

l a.

At least once per 7 days by:

l l

1.

Verifying the boron concentration of the water, 2.

Verifying the contained borated water volume of the tank, and i

1 3.

Verifying the boric acid storage tank solution temperature when C

it is the source of borated water.

~

b.

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

1ess than 35"F.

NORTH ANNA - UNIT 2 3/4 1-13 Amendment No. 54 l

-l

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 As a minimum, the following borated water source (s) shall be OPERABLE l

as required by Specification 3.1.2.2:

a.

A boric acid storage system and at least one associated heat tracing system with:

1.

A contained borated water volume of between 6000 and 16,280 l

gallons.

2.

Between 12,950 and 15,750 ppm of boron, and l

3.

A minimum solution temperature of 115'F.

b.

The refueling water storage tank with:

i 1.

A contained borated water volume of between 475,058 and 487,000 i

gallons, 2.

Between 2000 and 2100 ppm of boron, and 3.

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

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the boric acid storage system inoperable and being used as one of the above required borated water sources, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN l

equivalent to at least 1.77% Ak/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 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l l

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following l

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

,-.-s

.w.

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T,yg LESS THAN 350*F SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE pumps, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 340*F by verifying that the control switch is in tne pull to lock position.

9 e

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NORTH ANNA - UNIT 2 3/4 5-7

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EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK LIMITING CONDITION FOR OPERATION 3.5.4.1 The boron injection tank shall be OPERABLE with:

a.

A contained borated water volume of at least 900

gallons, b.

Between 12.950 and 15,750 ppm of boron, and g

c.

A minimum solution temperature of 115'F.

g APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With the boron injection tank inoperabit, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 1.77% ak/k at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.4.1 The baron injection tank shall be demonstrated OPERABLE by:

l a.

Verifying the contained borated water volume at least once per 7 l

days, b.

Verifying the baron concentration of the water in the tank at least i

once per 7 days, and c.

Verifying the water temperature at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l

~

NORTH ANNA - UNIT 2 3/4 5-8

. Amendment No. 54 l

5

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l l

EMERGENCY CORE COOLING SYSTEMS HEAT TRACING LIMITING CONDITION FOR OPERATION 3.5.4.2 At least two independent channels of heat tracing shall be OPERABLE for the boron injection tank and for the heat traced portions of the associated flow paths.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With only one channel of heat tracing on either the boron injection tank or on the heat traced portion of an associated flow path OPERABLE, operation may continue for up to 30 days provided the tank and flow path temperatures are verified to be greater than or equal to ll5'F at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; otherwise, be in HOT SHUTDOWN within 12. hours.

SURVEILLANCE REQUIREMENTS 4.5.4.2 Each heat tracing channel for the boron injection tank and associated flow path shall be demonstrated OPERABLE:

a.

At least once per 31 days by energizing each heat tracing channel and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the tank and flow path temperatures to be greater than or equal to 115'F. The tank tempera-l ture shall be determined by measurement. The flow path temperature shall be determined by either measurement or recirculation flow until establishment of equilibrium temperatures within the tank.

1 NORTH ANNA - UNIT 2 3/4 5-9 Amendment No. 54 1

i

%s EMERGENCY CORE COOLING SYSTEMS REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:

a.

A contained borated water volume of between 475,058 and 487,000 gallons.

b.

Between 2000 and 2100 ppm of boron, and c.

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

l APPLICABILITY: MODES 1, 2, 3 and 4.

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ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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-h SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:

l a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank, and 2.

Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature.

e NORTH ANNA - UNIT 2 3/4 5-10 I

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3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concen-tration 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:

Either a K of 0.95 or less, which includes a 15 delta k/k conser-a.

vative a11Nnce for uncertainties, or b.

A boron concentration of greater than orrequal to 2000 poc, which includes a 50 ppm conservative allowance for uncertainties.

APPLICABILITY: N)DE 6*.

ACTION:

With the requirements of the above specification not sat'sfied, imediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 12,950 ppm baron or its l

equivalent until K,ff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2000 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

t a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length control rod located within the reactor pressure vessel, 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 detamined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

g.

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

n NORTH ANNA.- UNIT 2 3/4 9-1 Amendment No. 54 f

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REFUELING OPERATIONS INSTRUMENTATION

. _ LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment.

APPLICABILITY: MODE 6.

ACTION:

a.

With one of the above required monitors inoperable, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b.

With both of the above required monitors inoperable, determine the boron concentration of the reactor coolant system at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to th'e initial start of CORE ALTERATIONS, and c.

A CHANNEL FUNCTIONAL TEST at least once per 7 days.

l

. S.

NORTH ANNA - UNIT 2 3/4 9-2 5

s.

3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION t

3.10.1 The SHUTDOWN MARGIN requirement of 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).

. APPLICABILITY: MODE 2.

ACTION:

With any full length control rod not fully inserted and with less than a.

the above reactivity equivalent available for trip insertion, initiate and continue boration at greater than or equal to 10 gpm of a solution containing at least 12.950 ppm boron or its equivalent until the SHUTDOWN l

I MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full length control rods inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing

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at least 12,950 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specift;ation 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each control rod that is not fully inserted shall be demonstrated capable of full. insertion when tripped from at least 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

I NORTH ANNA - UNIT 2 3/4 10-1 Amendment No. 54 l'

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i SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 4

LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1 and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE 1.

ACTION:

With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1 and 3.2.4 are suspended, either:

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a.

Reduce THERMAL POWER sufficient to satisfy the ACTION require-l ments of Specifications 3.2.2 and 3.2.3, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be less than or equal to 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 The Surveillance Requirements of the below listed Specifications shall be performed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during PHYSICS TESTS.

a.

Specification 4.2.2.2 and 4.2.2.3.

b.

Specification 4.2.3.1 and 4.2.3.2.

o A

NORTH ANNA - UNIT 2 3/4 10-2

l REACTIVITY CONTROL SYSTEMS BASES j

3/4.1.2 80 RATION 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, 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 boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operation conditions of 1.6% delta k/k after xenon decay

~

and cooldown to 200*F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 6000 gallons of 12.950 ppe borated water from the boric acid storage tanks l

or 70,000 gallons of 2000 ppm borated water from the refueling water storage tank.

I With the RCS 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 ALTERATIONS and positive reactivity change in the event the single injection j

system becomes inoperable.

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

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OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 340*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1.77 delta k/k after xenon decay and cooldown from 200*F i

i to 140*F. This condition requires either 1378 gallons of 12.950 ppm borated l

l water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated t

water from the refueling water storage tank.

l

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NORTH ANNA - UNIT 2 B 3/4 1-3 Amendment No. 54 e

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ll REACTIVITY CONTROL SYSTEMS i

BASES 3/4.1.2 BORATION SYSTEMS (Continued)

The contained water volume limits include allowance for water not avail-j able because of discharge line location and other physical characteristics.

L i

The OPERABILITY.of one boron injection system during REFUELING insures that l

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 8.5 and 11.0 for the-solution re-circulated within the containment after a LOCA. This pH mininitzes the evolution of iodine and minimizes the effect of chloride and caus. tic stress j

corrosion on mechanical systems and components.

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

This is required to maintain the

't charging pump cross-connect system operational.

3/4.1.3 MOVABLE CONTROL ASSEM8 LIES

=

2 The specifications of this section ensure that (1) acceptable power l

distribution limits are maintained (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod aligreent and insertion limits.

l The ACTION statements which permit limited variations from the basic j

requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provides assurance of fuel rod integrity during I

continued operation.

In addition those accident analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

i Control rod positions and OPERABILITY of the rod position indicatars l

are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

4 The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with T than or equal to 500*F and with all reactor coolant pumps operat@ greater ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

NORTH ANNA - UNIT 2 B 3/4 1-4 Amendment No. 5

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l 3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES w.

l 3/4.5.1 ACCUMULATORS The OPERABILITY of each RCS accumulator ensures that a sufficient volume of borated water will be innediately forced into the reactor core through i

each of the cold legs in the event the RCS pressure falls below the pressure of the accumulators. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety i

analysis are met.

l The accumulator power operated isolation valves are considered to be

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" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be innediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.

r l

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that suf-ficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single. failure i

consideration. Either subsystem operating in conjunction with the i

accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all post-ulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.

In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.

l NORTH ANNA - UNIT 2 B 3/4 5-1

EMERGENCY CORE COOLING SYSTEMS BASES l

With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

l The limitation for a maximum of one centrifugal charging pump and one low head safety injection pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and low head safety injection pumps except the required OPERABLE pump to be inoperable below 340'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single c

j PORV.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met i

and that subsystem 0PERABILITY is maintained. Surveillance requirements for l

throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection i

point is necessary to:

(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration (2) provide the proper flow split between injection p(oints in accordance with the assumptions used in the ECCS-LOCA analyses, and 3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 BORON INJECTION SYSTEM l

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The OPERABILITY of the boron injection system as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.

l The limits on injection tank minimum contained volume and boron concentration ensure that the assumptions used in the steam line break analysis are met.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

The OPERABILITY of the redundant heat tracing channels associated with the boron injection system ensure that the solubility of the boron solution will be maintained above the solubility limit of 111*F at 15,750 ppm boron.

.i NORTH ANNA - UNIT 2 B 3/4 5-2 Amendment No. 54 e

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