Text

Part 2 of 6 - Tech Spec Pages for Amendments 231 and 212 for North Anna, Units 1 & 2. Pages 3.5.3-1 Through 5.7-5
	ML021220166
Person / Time
Site:	North Anna
Issue date:	04/05/2002
From:	; Office of Nuclear Reactor Regulation
To:	;
References
	TAC MB0799, TAC MB0800
	Download: ML021220166 (190)
	v • d • e

ECCS-Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS-Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

APPLICABILITY:

MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Required ECCS train A.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, train to OPERABLE status.

B.

Required Action and B.1 Be in MODE 5.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all In accordance equipment required to be OPERABLE:

with applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8 SR 3.5.2.4 North Anna Units 1 and 2 3.5.3-1 Amendments 231/212,

Intentionally Blank

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RWST boron A.1 Restore RWST to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months concentration not OPERABLE status.

within limits.

OR RWST borated water temperature not within limits.

B.

RWST inoperable for B.1 Restore RWST to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than OPERABLE status.

Condition A.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.5.4-1

RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify RWST borated water temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

_> 40'F and _*

50'F.

SR 3.5.4.2 Verify RWST borated water volume is 7 days

_Ž 466,200 gallons and *_ 487,000 gallons.

SR 3.5.4.3

NOTE---------------

For Unit 2, until the first entry into MODE 4 following the Unit 2 Fall 2002 refueling outage, the RWST boron concentration acceptance criteria shall be

_> 2300 ppm and < 2400 ppm.

Verify RWST boron concentration is 7 days

_ 2600 ppm and *_ 2800 ppm.

North Anna Units 1 and 2 Amendments 231/212, 3.5.4-2

Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Seal Injection Flow LCO

3.5.5 APPLICABILITY

Reactor coolant pump seal injection flow shall be

30 gpm with RCS pressure Ž 2215 psig and

2255 psig and the seal injection hand control valve full open.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow A.1 Adjust manual seal 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limit, injection throttle valves to give a flow within limit with RCS pressure '_

2215 psig and _< 2255 psig and the seal injection hand control valve full open.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.5.5-1

Seal Injection Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.5.1

NOTE---------------

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the Reactor Coolant System pressure stabilizes at A 2215 psig and A 2255 psig.

Verify manual seal injection throttle 31 days valves are adjusted to give a flow within limit with RCS pressure A 2215 psig and

? 2255 psig and the seal injection hand control valve full open.

North Anna Units 1 and 2 Amendments 231/212, 3.5.5-2

BIT 3.5.6 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.6 Boron Injection Tank (BIT)

LCO

3.5.6 APPLICABILITY

The BIT shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

BIT inoperable.

A.1 Restore BIT to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Borate to an SDM 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within the limit provided in the COLR.

AND B.3 Restore BIT to 7 days OPERABLE status.

C.

Required Action and C.1 Be in MODE 4' 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

.Time of Condition B not met.

North Anna Units 1 and 2 3.5.6-1 Amendments 231/212,

BIT 3.5.6 SURVEILLANCE REQUIREMENTS SURVE I LLANCE FREQUENCY SR 3.5.6.1 Verify BIT borated water temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 115 0F.

SR 3.5.6.2 Verify BIT borated water volume is 7 days

> 900 gallons.

SR 3.5.6.3 Verify BIT boron concentration is 7 days

_ 12,950 ppm and _< 15,750 ppm.

North Anna Units 1 and 2 Amendments 231/212, 3.5.6-2

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO

3.6.1 APPLICABILITY

Containment shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Containment A.1 Restore containment to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and In accordance leakage rate testing except for containment with the air lock testing, in accordance with the Containment Containment Leakage Rate Testing Program.

Leakage Rate Testing Program North Anna Units 1 and 2 Amendments 231/212, 3.6.1-1

Intentionally Blank

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 APPLICABILITY:

Two containment air locks shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS NOTES-

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when air lock leakage results in exceeding the overall containment leakage rate.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more NOTES containment air locks

1. Required Actions A.1, A.2, with one containment and A.3 are not applicable air lock door if both doors in the same inoperable, air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 3.6.2-1

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND A.2 Lock the OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock.

AND A.3

NOTE------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

North Anna Units 1 and 2 Amendments 231/212, 3.6.2-2

Containment Air ACTIONS Locks 3.6.2 CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more containment air locks with containment air lock interlock mechanism inoperable.

.1 NOTES-----------

1. Required Actions B.1, B.2, and B.3 are not applicable if both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE door is closed in the affected air lock.

AND B.2 Lock an OPERABLE door closed in the affected air lock.

AND B.3

NOTE --------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE door is locked closed in the affected air lock.

North Anna Units 1 and 2 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 24 hours Once per 31 days Amendments 231/212, 3.6.2-3

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more C.1 Initiate action to Immediately containment air locks evaluate overall inoperable for reasons containment leakage other than Condition A rate per LCO 3.6.1.

or B.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months closed in the affected air lock.

AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D.

Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND D.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months North Anna Units 1 and 2 3.6.2-4 Amendments 231/212,

Containment Air SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.2.1

NOTES----------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance cri teri a appl i cable to SR 3.6.1.1.

Perform required air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program.

FREQUENCY

.1.

In accordance with the Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be 24 months opened at a time.

North Anna Units 1 and 2 Locks 3.6.2 Amendments 231/212, 3.6.2-5

Intentionally Blank

Containment Isolation 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO

3.6.3 APPLICABILITY

Each containment isolation valve shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS NOTES

1. Penetration flow path(s) except for 36 inch purge and exhaust valves, 18 inch containment vacuum breaking valve, 8 inch purge bypass valve, and steam jet air ejector suction flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when leakage for a penetration flow path results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE --------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path penetration flow paths by use of at least one with two or more closed and

-containment isolation de-activated automatic valves.

valve, closed manual valve, blind flange, or check valve with One or more flow through the valve penetration flow paths secured.

with one containment isolation valve AND inoperable for reasons other than Condition D.

(continued)

North Anna Units 1 and 2 Valves 3.6.3 Amendments 231/212, 3.6.3-1

Containment Isolation Valves 3.6.3 CONDITION IREQUIRED ACTION COMPLETION TIME A. (continued)

A.2

NOTES------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

i _______________________________

a Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment North Anna Units 1 and 2 ACTIONS Amendments 231/212.

3.6.3-2

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. --------- NOTE --------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path penetration flow paths by use of at least one with two containment closed and isolation valves.

de-activated automatic valve, closed manual valve, or blind One or more flange.

penetration flow paths with two containment isolation valves inoperable for reasons other than Condition D.

C. ---------NOTE --------- C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path penetration flow paths by use of at least one with only one closed and containment isolation de-activated automatic valve and a closed valve, closed manual system.

valve, or blind flange.

One or more penetration flow paths with one containment isolation valve inoperable.

AND (continued)

North Anna Units 1 and 2 3.6.3-3 Amendments 231/212,

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

C.2

NOTES------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D.

Purge valve D.1 Restore leakage within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months penetration leakage limit.

not within limit.

E.

Required Action and E.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND E.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months North Anna Units 1 and 2 Amendments 231/212, 3.6.3-4

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.6.3.1

NOTE---------------

Valves and blind flanges in high radiation areas may be verified by use of administrative controls.

Verify each containment isolation manual valve and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.2

NOTE---------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

FREQUENCY 31 days Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR-3.6.3.3 Verify the isolation time of each automatic In accordance power operated containment isolation valve with the is within limits.

Inservice Testing Program SR 3.6.3.4 Perform leakage rate testing for Prior to containment purge valves with resilient entering MODE 4 seals.

from MODE 5 after containment vacuum has been broken North Anna Units 1 and 2 I

I 3.6.3-5 Amendments 231/212,

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.5 Verify each automatic containment isolation 18 months valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

SR 3.6.3.6 Cycle each weight or spring loaded check 18 months valve not testable during operation through one complete cycle of full travel, and verify each check valve remains closed when the differential pressure in the direction of flow is < 1.2 psid and opens when the differential pressure in the direction of flow is Ž 1.2 psid and < 5.0 psid.

North Anna Units 1 and 2 Amendments 231/212, 3.6.3-6

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment air partial pressure shall be Ž 9.0 psia and within the acceptable operation range shown on Figure 3.6.4-1.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Containment air A.1 Restore containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months partial pressure not air partial pressure within limits, to within limits.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment air partial pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within limits.

North Anna Units 1 and 2 3.6.4-1 Amendments 231/212,

Containment Pressure 3.6.4 12.00 11.50 CI) 0=

2 11.00 T 10.50

"* 10.00 (Ui C.

9.50 CD E

9.00 CO o>

8.50 0

8.00 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Service Water Temperature (°F)

Figure 3.6.4-1 (page 1 of 1)

Containment Air Partial Pressure Versus Service Water Temperature North Anna Units 1 and 2 Amendments 231/212, 3.6.4-2

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment

1200 F.

average air temperature shall be Ž 86°F and APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average A.1 Restore containment 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months air temperature not average air within limits, temperature to within limits.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is within limits.

North Anna Units 1 and 2 3.6.5-1 Amendments 231/212,

Intentionally Blank

QS System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Quench Spray (QS) System LCO 3.6.6 Two QS trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One QS train A.1 Restore QS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each QS manual, power operated, and 31 days automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Verify each QS pump's developed head at the In accordance flow test point is greater than or equal to with the the required developed head.

Inservice Testing Program North Anna Units 1 and 2 3.6.6-1 Amendments 231/212,

QS System 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each QS automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.6.4 Verify each QS pump starts automatically on 18 months an actual or simulated actuation signal.

SR 3.6.6.5 Verify each spray nozzle is unobstructed.

10 years North Anna Units 1 and 2 Amendments 231/212, 3.6.6-2

RS System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Recirculation Spray (RS) System LCO 3.6.7 Four RS subsystems OPERABLE.

and a casing cooling tank shall be APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One RS subsystem A.1 Restore RS subsystem 7 days inoperable, to OPERABLE status.

B.

Two RS subsystems B.1 Restore one RS 72 hours inoperable in one subsystem to OPERABLE

train, status.

C.

Two inside RS C.1 Restore one RS 72 hours subsystems inoperable, subsystem to OPERABLE status.

D.

Casing cooling tank D.1 Restore casing cooling 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, tank to OPERABLE status.

E.

Required Action and E.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND E.2 Be in MODE 5.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months North Anna Units 1 and 2 3.6.7-1 Amendments 231/212,

RS System 3.6.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.

One outside RS F.1 Enter LCO 3.0.3.

Immediately subsystem and one inside RS subsystem inoperable and not in the same train.

OR Three or more RS subsystems inoperable.

OR Two outside RS subsystems inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify casing cooling tank temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Ž350F and 5 500F.

SR 3.6.7.2 Verify casing cooling tank contained 7 days borated water volume is Ž 116,500 gal.

SR 3.6.7.3

NOTE---------------

For Unit 2, until the first entry into MODE 4 following the Unit 2 Fall 2002 refueling outage, the casing cooling tank boron concentration acceptance criteria shall be Ž 2300 ppm and

2400 ppm.

Verify casing cooling tank boron 7 days concentration is Ž 2600 ppm and : 2800 ppm.

North Anna Units 1 and 2 Amendments 231/212, 3.6.7-2

RS System 3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.4 Verify each RS and casing cooling manual, 31 days power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.7.5 Verify each RS and casing cooling pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head.

Testing Program SR 3.6.7.6 Verify on an actual or simulated actuation 18 months signal(s):

a. Each RS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position;

b. Each RS pump starts automatically; and

c. Each casing cooling pump starts automatically.

SR 3.6.7.7 Verify each spray nozzle is unobstructed.

10 years North Anna Units 1 and 2 Amendments 231/212, 3.6.7-3

Intentionally Blank

Chemical Addition System 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Chemical Addition System LCO

3.6.8 APPLICABILITY

The Chemical Addition System shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Chemical Addition A.1 Restore Chemical 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months System inoperable.

Addition System to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 5.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify each Chemical Addition System 31 days manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.8.2 Verify chemical addition tank solution 184 days volume is Ž 4800 gal and

5500 gal.

SR 3.6.8.3 Verify chemical addition tank NaOH solution 184 days concentration is Ž 12% and

13% by weight.

North Anna Units 1 and 2 Amendments 231/212, 3.6.8-1

Chemical Addition System 3.6.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.4 Verify each Chemical Addition System 18 months automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.8.5 Verify Chemical Addition System flow from 5 years each solution's flow path.

North Anna Units 1 and 2 Amendments 231/212, 3.6.8-2

Hydrogen Recombiners 3.6.9 3.6 CONTAINMENT SYSTEMS 3.6.9 Hydrogen Recombiners LCO 3.6.9 Two hydrogen recombiners shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One hydrogen A.1 Restore hydrogen 30 days recombiner inoperable.

recombiner to OPERABLE status.

B.

Two hydrogen B.1 Verify by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recombiners administrative means inoperable, that the hydrogen AND control function is maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.1 Perform a system functional test for each 18 months hydrogen recombiner.

North Anna Units 1 and 2 3.6.9-1 Amendments 231/212,

Hydrogen Recombiners 3.6.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.2 Visually examine each hydrogen recombiner 18 months enclosure and verify there is no evidence of abnormal conditions.

SR 3.6.9.3 Perform a resistance to ground test for 18 months each heater phase.

North Anna Units 1 and 2 Amendments 231/212, 3.6.9-2

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO

3.7.1 APPLICABILITY

Five MSSVs per steam generator shall be OPERABLE.

MODES 1, 2, and 3.

ACTIONS NOTE Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more steam A.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with one to less than or equal MSSV inoperable and to 52% RTP.

the Moderator Temperature Coefficient (MTC) zero or negative at all power levels.

B.

One or more steam B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months generators with one to less than or equal MSSV inoperable and to the Maximum the MTC positive at Allowable % RTP any power levels, specified in Table 3.7.1-1 for the

,OR number of OPERABLE MSSVs.

One or more steam generators with two or AND more MSSVs inoperable.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 3.7.1-1

MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2

NOTE------

Only required in MODE 1.

Reduce the Power Range 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Neutron Flux-High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND OR C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators with greater than or equal to 4 MSSVs inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1

NOTE---------------

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance Table 3.7.1-2 in accordance with the with the Inservice Testing Program. Following Inservice testing, lift setting shall be within +/-1%.

Testing Program North Anna Units 1 and 2 Amendments 231/212, 3.7.1-2

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM ALLOWABLE POWER PER STEAM GENERATOR

% RTP 4

52 3

37 2

21 North Anna Units 1 and 2 3.7.1-3 Amendments 231/212,

MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings STEAM GENERATOR

1

2

3 LIFT SETTING Unit 1 VALVE NUMBER (psig +/- 3%)

MS-SV-1O1A MS-SV-1O1B MS-SV-101C 1085 MS-SV-102A MS-SV-102B MS-SV-102C 1095 MS-SV-103A MS-SV-103B MS-SV-103C 1110 MS-SV-104A MS-SV-104B MS-SV-104C 1120 MS-SV-105A MS-SV-105B MS-SV-105C 1135 Unit 2 VALVE NUMBER MS-SV-201A MS-SV-201B MS-SV-201C 1085 MS-SV-202A MS-SV-202B MS-SV-202C 1095 MS-SV-203A MS-SV-203B MS-SV-203C 1110 MS-SV-204A MS-SV-204B MS-SV-204C 1120 MS-SV-205A MS-SV-205B MS-SV-205C 1135 North Anna Units 1 and 2 3.7.1-4 Amendments 231/212,

MSTVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Trip Valves (MSTVs)

LCO

3.7.2 APPLICABILITY

Three MSTVs shall be OPERABLE.

MODE 1, MODES 2 and 3 except when all MSTVs are closed and de-activated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One MSTV inoperable in A.1 Restore MSTV to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MODE 1.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met.

C. ---------NOTE ---------

C.1 Close MSTV.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Separate Condition entry is allowed for AND each MSTV.

C.2 Verify MSTV is closed.

Once per 7 days One or more MSTVs inoperable in MODE 2 or 3.

D.

Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C AND not met.

D.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.7.2-1

MSTVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1

NOTE--------------

Only required to be performed in MODES 1 and 2.

Verify isolation time of each MSTV is In accordance

5 seconds.

with the Inservice Testing Program SR 3.7.2.2

NOTE Only required to be performed in MODES 1 and 2.

Verify each MSTV actuates to the isolation 18 months position on an actual or simulated actuation signal.

North Anna Units 1 and 2 Amendments 231/212, 3.7.2-2

MFIVs, MFPDVs,

MFRVs, and MFRBVs 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs),

Main Feedwater Pump Discharge Valves (MFPDVs),

Main Feedwater Regulating Valves (MFRVs),

and Main Feedwater Regulating Bypass Valves (MFRBVs)

LCO 3.7.3 Three MFIVs, three MFPDVs, three MFRVs, and three MFRBVs shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3 except when MFIV,

MFPDV, MFRV, or MFRBV is closed and de-activated or isolated by a closed manual valve.

ACTIONS NOTE -----------------

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more MFIVs A.1 Close or isolate MFIV.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND A.2 Verify MFIV is closed Once per 7 days or isolated.

B.

One or more MFRVs B.1 Close or isolate MFRV.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

AND B.2 Verify MFRV is closed Once per 7 days or isolated.

C.

One or more MFRBVs C.1 Close or isolate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months i noperabl e.

MFRBV.

AND C.2 Verify MFRBV is closed Once per 7 days or isolated.

North Anna Units 1 and 2 3.7.3-1 Amendments 231/212,

MFIVs, MFPDVs, MFRVs, and MFRBVs 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more MFPDV D.1 Close or isolate 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

MFPDV.

AND D.2 Verify MFPDV is closed Once per 7 days or isolated.

E.

Two valves in the same E.1 Isolate affected flow 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path inoperable.

path.

F.

Required Action and F.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the isolation time of each MFIV, In accordance

MFRV, and MFRBV is 6.98 seconds and the with the isolation time of each MFPDV is Inservice

_ 60 seconds.

Testing Program SR 3.7.3.2 Verify each MFIV,

MFPDV, MFRV, and MFRBV 18 months actuates to the isolation position on an actual or simulated actuation signal.

North Anna Units 1 and 2 3.7.3-2 Amendments 231/212,

SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs)

LCO

3.7.4 APPLICABILITY

Three SG PORV lines shall be OPERABLE.

MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required SG PORV A.1 Restore required SG 7 days line inoperable.

PORV line to OPERABLE status.

B.

Two or more required B.1 Restore all but one SG SG PORV lines PORV line to OPERABLE inoperable, status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND C.2 Be in MODE 4 without 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reliance upon steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV.

18 months SR 3.7.4.2 Verify one complete cycle of each SG PORV 18 months manual isolation valve.

North Anna Units 1 and 2 Amendments 231/212, 3.7.4-1

Intentionally Blank

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO

3.7.5 APPLICABILITY

Three AFW trains shall be OPERABLE.

NOTE--

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.

MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One steam supply to A.1 Restore affected 7 days turbine driven AFW equipment to OPERABLE pump inoperable, status.

AND OR 10 days from discovery of

-NOTE failure to meet Only applicable if the LCO MODE 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

B.

One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, OPERABLE status.

2 or 3 for reasons AND other than Condition A.

10 days from discovery of failure to meet the LCO North Anna Units 1 and 2 Amendments 231/212, 3.7.5-1

AFW System 3.7.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4.

18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months OR Two AFW trains inoperable in MODE 1, 2, or 3.

D. Three AFW trains D.1

NOTE-----

inoperable in MODE 1, LCO 3.0.3 and all 2, or 3.

other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to Immediately restore one AFW train to OPERABLE status.

E.

Required AFW train E.1 Initiate action to Immediately inoperable in MODE 4.

restore AFW train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

North Anna Units 1 and 2 Amendments 231/212, 3.7.5-2

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.2

NOTE-------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after Ž 1005 psig in the steam generator.

Verify the developed head of each AFW pump In accordance at the flow test point is greater than or with the equal to the required developed head.

Inservice Testing Program SR 3.7.5.3

NOTE---------------

Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW automatic valve that is not 18 months locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4

NOTES-------------

1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after Ž 1005 psig in the steam generator.

2. Not applicable in MODE 4 when steam generator is relied upon for heat removal.

Verify each AFW pump starts automatically 18 months on an actual or simulated actuation signal.

SR 3.7.5.5 Verify proper alignment of the required AFW Prior to flow paths by verifying flow from the entering MODE 3, emergency condensate storage tank to each whenever unit steam generator.

has been in MODE 5, 6, or defueled for a cumulative period > 30 days North Anna Units 1 and 2 3.7.5-3 Amendments 231/212,

Intentionally Blank

ECST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Emergency Condensate Storage Tank (ECST)

LCO

3.7.6 APPLICABILITY

The ECST shall be OPERABLE.

MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

ECST inoperable.

A.1 Verify by 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months administrative means OPERABILITY of AND Condensate Storage Tank.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND A.2 Restore ECST to 7 days OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND B.2 Be in MODE 4, without 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the ECST contains ; 110,000 gal.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 3.7.6-1 Amendments 231/212,

Intentionally Blank

Secondary Specific Activity 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Secondary Specific Activity LCO

3.7.7 APPLICABILITY

The specific activity of the secondary coolant shall be

0.10 pCi/gm DOSE EQUIVALENT 1-131.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the specific activity of the 31 days secondary coolant is

0.10 yCi/gm DOSE EQUIVALENT 1-131.

North Anna Units 1 and 2 Amendments 231/212, 3.7.7-1

Intentionally Blank

SW System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Service Water (SW)

System LCO

3.7.8 APPLICABILITY

Two SW System loops shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SW pump A.1 Throttle SW System flow 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable, to Component Cooling (CC) heat exchangers.

B.

Two SW pumps B.1 Throttle SW System flow 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, to CC heat exchangers.

AND B.2 Restore one SW pump to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

North Anna Units 1 and 2 Amendments 231/212, 3.7.8-1

SW System 3.7.8 ACTIONS CONDITION IREQUIRED ACTION COMPLETION TIME C.

One SW System loop inoperable for reasons other than Condition A.

C.1 Restore SW System loop to OPERABLE status.

NOTE -----

72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time only required if criteria allowing 7 day Completion Time are not met.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND NOTE -----

Only applicable if:

1. SW loop inoperability is part of SW System upgrades, and

2. Three SW pumps are OPERABLE from initial Condition entry (one SW pump allowed to not have automatic start capability),

and

3. Two auxiliary SW pumps are OPERABLE from initial Condition entry.

7 days North Anna Units 1 and 2 L __________________________________

L 3.7.8-2 Amendments 231/212,

SW System 3.7.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Actions and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Times of Conditions A, AND B or C not met.

D.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E.

Two SW System loops E.1 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable for reasons other than only two SW AND pumps being OPERABLE.

E.2 Initiate actions to be 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months in MODE 5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1

NOTE---------------

Isolation of SW flow to individual components does not render the SW System inoperable.

Verify each SW System manual, power 31 days operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.2 Verify each SW System automatic valve in 18 months the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.3 Verify each SW pump starts automatically on 18 months an actual or simulated actuation signal.

North Anna Units 1 and 2 3.7.8-3 Amendments 231/212,

Intentionally Blank

UHS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)

LCO

3.7.9 APPLICABILITY

The UHS shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

UHS inoperable.

A.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of the Service Water 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Reservoir is Ž 313 ft mean sea level.

SR 3.7.9.2 Verify average water temperature of the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Service Water Reservoir is

95°F.

North Anna Units 1 and 2 Amendments 231/212, 3.7.9-1

Intentionally Blank

MCR/ESGR EVS-MODES 1, 2, 3, and 4 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Main Control Room/Emergency Switchgear Room (MCR/ESGR)

Emergency Ventilation System (EVS)-MODES 1, 2, 3, and 4 LCO 3.7.10 APPLICABILITY:

The following MCR/ESGR EVS trains shall be OPERABLE:

a. Two MCR/ESGR Emergency Ventilation System (EVS) trains; and

b. One MCR/ESGR EVS train on the other unit.

NOTE The MCR/ESGR boundary may be opened intermittently under administrative control.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required A.1 Restore MCR/ESGR EVS 7 days LCO 3.7.10.a or train to OPERABLE LCO 3.7.10.b MCR/ESGR status.

EVS train inoperable.

B.

Two or more required B.1 Restore MCR/ESGR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO 3.7.10.a or boundary to OPERABLE LCO 3.7.10.b MCR/ESGR status.

EVS trains inoperable due to inoperable MCR/ESGR boundary.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months North Anna Units 1 and 2 3.7.10-1 Amendments 231/212,

MCR/ESGR EVS-MODES 1, 2, 3, and 4 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Two or more required D.1 Enter LCO 3.0.3.

Immediately LCO 3.7.10.a or LCO 3.7.10.b MCR/ESGR EVS trains inoperable for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each required MCR/ESGR EVS train 31 days for Ž 10 continuous hours with the heaters operating.

SR 3.7.10.2 Perform required MCR/ESGR EVS filter In accordance testing in accordance with the Ventilation with VFTP Filter Testing Program (VFTP).

SR 3.7.10.3 Verify each LCO 3.7.10.a MCR/ESGR EVS train 18 months actuates on an actual or simulated actuation signal.

SR 3.7.10.4 Verify each required MCR/ESGR EVS train can 18 months on a maintain a positive pressure of STAGGERED TEST

Ž 0.04 inches water gauge, relative to the BASIS adjacent areas, during the pressurization mode of operation at a makeup flow rate of g900 cfm and

1100 cfm.

North Anna Units 1 and 2 Amendments 231/212, 3.7.10-2

MCR/ESGR ACS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Main Control Room/Emergency Switchgear Room (MCR/ESGR)

Air Conditioning System (ACS)

LCO 3.7.11 Two MCR/ESGR ACS subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and During movement of 4,

recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore MCR/ESGR ACS 30 days MCR/ESGR ACS subsystem subsystem to OPERABLE inoperable, status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.

Required Action and C.1 Place OPERABLE Immediately associated Completion MCR/ESGR ACS subsystem Time of Condition A in operation.

not met during movement of recently OR irradiated fuel assemblies.

C.2 Suspend movement of Immediately recently irradiated fuel assemblies.

D.

Less than 100% of the D.1 Suspend movement of Immediately MCR/ESGR ACS cooling recently irradiated equivalent to a single fuel assemblies.

OPERABLE MCR/ESGR ACS subsystem available during movement of recently irradiated fuel assemblies.

North Anna Units 1 and 2 3.7.11-1 Amendments 231/212,

MCR/ESGR ACS 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

Less than 100% of the E.1 Enter LCO 3.0.3.

Immediately MCR/ESGR ACS cooling equivalent to a single OPERABLE MCR/ESGR ACS subsystem available in MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each required MCR/ESGR ACS chiller 18 months on a has the capability to remove the assumed STAGGERED TEST heat load.

BASIS North Anna Units 1 and 2 Amendments 231/212, 3.7.11-2

ECCS PREACS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Emergency Core Cooling System (ECCS)

Pump Room Exhaust Air Cleanup System (PREACS)

LCO 3.7.12 Two ECCS PREACS trains shall be OPERABLE.

NOTE -------------

The ECCS pump room boundary openings not open by design may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One ECCS PREACS train A.1 Restore ECCS PREACS 7 days inoperable, train to OPERABLE status.

B.

Two ECCS PREACS trains B.1 Restore ECCS pump room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to boundary to OPERABLE inoperable ECCS pump status.

room boundary.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ECCS PREACS train for 31 days

Ž 10 continuous hours with the heaters operating.

North Anna Units 1 and 2 3.7.12-1 Amendments 231/212,

ECCS PREACS 3.7.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.2 Actuate each ECCS PREACS train by aligning 31 days Safeguards Area exhaust flow and Auxiliary Building Central exhaust flow through the Auxiliary Building HEPA filter and charcoal adsorber assembly.

SR 3.7.12.3 Perform required ECCS PREACS filter testing In accordance in accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.12.4 Verify Safeguards Area exhaust flow is 18 months diverted and each Auxiliary Building filter bank is actuated on an actual or simulated actuation signal.

SR 3.7.12.5 Verify one ECCS PREACS train can maintain a 18 months on a negative pressure relative to adjacent STAGGERED TEST areas during post accident mode of BASIS operation.

North Anna Units 1 and 2 Amendments 231/212, 3.7.12-2

MCR/ESGR Bottled Air System 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Bottled Air System LCO 3.7.13 Three MCR/ESGR bottled air system trains shall be OPERABLE.

NOTE--

The MCR/ESGR boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, 3, and 4, During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required MCR/ESGR A.1 Restore MCR/ESGR 7 days bottled air system bottled air system train inoperable, train to OPERABLE status.

B.

Two or more required B.1 Restore MCR/ESGR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months MCR/ESGR bottled air boundary to OPERABLE system trains status.

inoperable due to inoperable MCR/ESGR boundary in MODE 1, 2, 3, or 4.

C.

Two or more required C.1 Restore at least two 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months MCR/ESGR bottled air MCR/ESGR bottled air system trains system train to inoperable in MODE 1, OPERABLE status.

2, 3, or 4 for reasons other than Condition B.

North Anna Units 1 and 2 Amendments 231/212, 3.7.13-1

MCR/ESGR Bottled Air System 3.7.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B AND or C not met in MODE 1, 2, 3, or 4.

D.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E.

Required Action and E.1 Suspend movement of Immediately associated Completion recently irradiated Time of Condition A fuel assemblies.

not met during movement of recently irradiated fuel assemblies.

OR Two or more required MCR/ESGR bottled air system trains inoperable during movement of recently irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify each required MCR/ESGR bottled air 31 days bank is pressurized to Ž 2300 psig.

SR 3.7.13.2 Verify each required MCR/ESGR bottled air 31 days bank manual valve not locked, sealed, or otherwise secured and required to be open during accident conditions is open.

SR 3.7.13.3 Verify each required MCR/ESGR bottled air 18 months system train actuates on an actual or simulated actuation signal.

North Anna Units 1 and 2 3.7.13-2 Amendments 231/212,

MCR/ESGR Bottled Air System 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.4 Verify two required MCR/ESGR bottled air 18 months on a system trains can maintain a positive STAGGERED TEST pressure of Ž 0.05 inches water gauge, BASIS relative to the adjacent areas at a makeup flow rate of Ž 340 cfm for at least 60 minutes.

North Anna Units 1 and 2 3.7.13-3 Amendments 231/212,

Intentionally Blank

MCR/ESGR EVS-During Movement of Recently Irradiated Fuel Assemblies 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Main Control Room/Emergency Switchgear Room (MCR/ESGR)

Emergency Ventilation System (EVS)-During Movement of Recently Irradiated Fuel Assemblies LCO 3.7.14 Two MCR/ESGR EVS trains shall be OPERABLE.

NOTE -------------

The MCR/ESGR boundary may be opened intermittently under administrative control.

APPLICABILITY:

During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required MCR/ESGR A.1 Restore train to 7 days EVS train inoperable.

OPERABLE status.

B.

Required Action and B.1 Suspend movement of Immediately associated Completion recently irradiated Time of Condition A fuel assemblies.

not met.

OR Two required MCR/ESGR EVS trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Operate each required MCR/ESGR EVS train 31 days for Ž 10 continuous hours with the heaters operating.

North Anna Units 1 and 2 Amendments 231/212, 3.7.14-1

MCR/ESGR EVS-During Movement of Recently Irradiated Fuel Assemblies 3.7.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.2 Perform required MCR/ESGR EVS filter In accordance testing in accordance with the Ventilation with VFTP Filter Testing Program (VFTP).

SR 3.7.14.3 Verify each required MCR/ESGR EVS train can 18 months on a maintain a positive pressure of STAGGERED TEST

Ž 0.04 inches water gauge, relative to the BASIS adjacent areas, during the pressurization mode of operation at a makeup flow rate of

Ž900 cfm and

1100 cfm.

North Anna Units 1 and 2 Amendments 231/212, 3.7.14-2

FBVS 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Fuel Building Ventilation System (FBVS)

LCO 3.7.15 APPLICABILITY:

The FBVS shall be OPERABLE and in operation.

NOTE-The fuel building boundary may be opened intermittently under administrative control.

During movement of recently irradiated fuel assemblies in the fuel building.

ACTIONS NOTE ----------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

FBVS inoperable.

A.1 Suspend movement of Immediately recently irradiated OR fuel assemblies in the fuel building.

FBVS not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the FBVS can maintain a pressure 18 months

-0.125 inches water gauge with respect to atmospheric pressure.

North Anna Units 1 and 2 Amendments 231/212, 3.7.15-1

Intentionally Blank

Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water Level LCO 3.7.16 APPLICABILITY:

The fuel storage pool water level shall be Ž 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool A.1

NOTE------

water level not within LCO 3.0.3 is not

limit, applicable.

Suspend movement of Immediately irradiated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days

Ž 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.

North Anna Units 1 and 2 Amendments 231/212, 3.7.16-1

Intentionally Blank

Fuel Storage Pool Boron Concentration 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LCO 3.7.17 APPLICABILITY:

The fuel storage pool boron concentration shall be

Ž 2600 ppm.

When fuel assemblies are stored in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTE---------

boron concentration LCO 3.0.3 is not applicable.

not within limit.

A.1 Suspend movement of Immediately fuel assemblies in the fuel storage pool.

AND A.2 Initiate action to Immediately restore fuel storage pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify the fuel storage pool boron 7 days concentration is within limit.

North Anna Units 1 and 2 Amendments 231/212, 3.7.17-1

Intentionally Blank

Spent Fuel Pool Storage 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Spent Fuel Pool Storage LCO 3.7.18 The combination of initial enrichment and burnup of each fuel assembly stored in the fuel storage pool shall be in accordance with the following:

a. New or irradiated fuel assemblies with a combination of burnup and initial nominal enrichment in the "Acceptable" burnup domain of Figure 3.7.18-1 may be stored in the fuel storage pool in a non-matrix location or a low reactivity location in the 5 x 5 matrix configuration shown in Figure 3.7.18-2. They may also be placed in a high reactivity location if stored in the 5 x 5 matrix configuration shown in Figure 3.7.18-2;

b. New or irradiated fuel assemblies with a combination of burnup and initial nominal enrichment in the "Conditionally Acceptable" domain of Figure 3.7.18-1 may be stored in the fuel storage pool in a non-matrix location, but must be placed in a high reactivity location if stored in the 5 x 5 matrix configuration shown in Figure 3.7.18-2; and

c. New or irradiated fuel assemblies with a combination of burnup and initial nominal enrichment in the "Unacceptable" domain of Figure 3.7.18-1 must be stored in the fuel storage pool in a high reactivity location in the 5 x 5 matrix configuration shown in Figure 3.7.18-2. A fuel assembly transferred from Surry for storage in the North Anna fuel storage pool must be treated as a fuel assembly in the "Unacceptable" domain.

APPLICABILITY:

Whenever any fuel assembly is stored in the spent fuel pool.

North Anna Units 1 and 2 Amendments 231/212, 3.7.18-1

Spent Fuel Pool Storage 3.7.18 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

NOTE------

LCO not met.

LCO 3.0.3 is not applicable.

Initiate action to Immediately move the noncomplying fuel assembly to an acceptable location.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by a combination of visual Prior to storing inspection and administrative means that the fuel the initial enrichment, burnup and storage assembly in the location of the assembly is acceptable.

spent fuel pool North Anna Units 1 and 2 Amendments 231/212, 3.7.18-2

Spent Fuel Pool Storage 3.7.18 45000 I

CD 0

Z.

E 0

JU 0

S IL 1.4 1.8 2.2 2.6 3

3.4 3.8 4.2 4.6 Initial U-235 Enrichment (nominal w/o)

Acceptable: Acceptable for storage in non-matrix location or low reactivity location in matrix configuration. May also be placed in high reactivity locations in matrix configuration.

Conditionally Acceptable: Acceptable for storage in non-matrix location, but must be placed in high reactivity location if stored in matrix configuration.

Unacceptable: Must be stored in high reactivity location in matrix configuration. Surry spent fuel must be stored in high reactivity locations in a matrix.

Figure 3.7.18-1 (page 1 of 1)

Burnup Credit Requirements North Anna Units 1 and 2 Amendments 231/212, 3.7.18-3

Spent Fuel Pool Storage 3.7.18 U.

U U

U U.

U.

U,))))

U, U,))

))))

U,))o))

U Low reactivity fuel (Per Figure 3.7.18-1 or cell containing no fuel assembly)

High reactivity fuel (Per Figure 3.7.18-1, reactivity up to and including 4.6 w/o U3 5 fresh fuel or cell containing no fuel assembly)

D

]

No fuel assembly Notes to Figure:

1. A partial matrix at the boundary of the spent fuel pool storage locations is an acceptable configuration.

2. Storage of non-fueled components within the matrix or non-matrix cells that results in a reduced spent fuel pool keff is acceptable.

3. A storage cell containing no fuel assembly may be substituted for any location in either matrix or non-matrix configuration.

4. Spent fuel transferred from Surry must be stored in high reactivity locations.

Figure 3.7.18-2 (page 1 of 1) 5 x 5 Matrix Storage Configuration North Anna Units 1 and 2 iil Amendments 231/212, 3.7.18-4

CC System 3.7.19 3.7 PLANT SYSTEMS 3.7.19 Component Cooling Water (CC) System LCO 3.7.19 APPLICABILITY:

Three CC subsystems shall be OPERABLE.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required CC A.1 Restore required CC 7 days subsystem inoperable, subsystem to OPERABLE status.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5.

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

Two required CC C.1 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystems inoperable.

AND C.2 Initiate actions to be 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months in MODE 5.

D.

No CC water available D.1 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to supply the residual heat removal heat AND exchangers.

D.2 Implement an alternate Immediately means of decay heat removal.

AND D.3 Initiate actions to be Immediately in MODE 5.

North Anna Units 1 and 2 Amendments 231/212, 3.7.19-1

CC System 3.7.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.19.1 Verify each CC manual, power operated, and 31 days automatic valve in the flow path servicing the residual heat removal system, that is not locked, sealed, or otherwise secured in position, is in the correct position.

North Anna Units 1 and 2 3.7.19-2 Amendments 231/212,

AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO

3.8.1 APPLICABILITY

The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System;

b. Two emergency diesel generators (EDGs) capable of supplying the onsite Class 1E power distribution subsystem(s);

c. One qualified circuit between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System and one EDG capable of supplying the onsite Class 1E AC power distribution subsystem on the other unit for each required shared component; and

d. Required sequencing timing relays.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One LCO 3.8.1.a A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months offsite circuit required OPERABLE inoperable.

offsite circuit(s).

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

North Anna Units 1 and 2 3.8.1-1 Amendments 231/212,

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no discovery of no offsite power offsite power to available inoperable one train when its redundant concurrent with required feature(s) is inoperability of inoperable, redundant required feature(s)

AND A.3 Restore offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status.

AND 17 days from discovery of failure to meet LCO B.

One LCO 3.8.1.b EDG B.1 Perform SR 3.8.1.1 for I hour inoperable, the required offsite circuits.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported discovery of by the inoperable EDG Condition B inoperable when its concurrent with required redundant i noperabi 1 i ty of feature(s) is redundant inoperable-required feature(s)

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-2

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO 3.8.1.b EDG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE LCO 3.8.1.b EDG.

AND B.4 Restore EDG to 14 days OPERABLE status.

AND 17 days from discovery of failure to meet LCO C. --------NOTE ---------

C.1.1 Restore inoperable AAC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable if DG to OPERABLE status.

Alternate AC (AAC) diesel generator (DG)

AND or one or more EDG on the other unit is C.1.2 Restore inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

EDG(s) on other unit to OPERABLE status.

_One LCO 3.8.1.b EDG OR inoperable.

C.2 Restore EDG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-3

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. --------NOTE---------- D.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Separate Condition required OPERABLE entry is allowed for offsite circuit(s).

AND each offsite circuit.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter One or more required LCO 3.8.1.c offsite AND circuit(s) inoperable.

D.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no discovery of no offsite power offsite power to available inoperable a train when its redundant concurrent with required feature(s) is inoperabil ity of i noperabl e.

redundant required feature(s)

AND D.3 Declare associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shared component i noperabl e.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-4

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

One required E.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months LCO 3.8.1.c EDG required offsite inoperable.

circuit(s).

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND E.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported discovery of by the inoperable EDG Condition E inoperable when its concurrent with redundant required i noperabi I i ty of feature(s) is redundant inoperable.

requi red feature(s)

AND E.3 Declare associated 14 days shared component i noperabl e.

F. --------- NOTE--------- F.1.1 Restore inoperable AAC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable if one DG to OPERABLE status.

or more LCO 3.8.1.b EDG(s) or AAC DG is AND inoperable.

F.1.2 Restore inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO 3.8.1.b EDG (s) to

-One required OPERABLE status.

LCO 3.8.1.c EDG inoperable.

OR F.2 Declare associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shared component inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-5

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

Two LCO 3.8.1.a G.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from offsite circuits feature(s) inoperable discovery of inoperable, when its redundant Condition G required feature(s) is concurrent with inoperable.

inoperability of redundant required features AND G.2 Restore one offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

H.

One LCO 3.8.1.a

NOTE---------

offsite circuit Enter applicable Conditions inoperable, and Required Actions of LCO 3.8.9, "Distribution AND Systems-Operating," when Condition H is entered with One LCO 3.8.1.b EDG no AC power source to any inoperable, train.

H.1 Restore offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

OR H.2 Restore EDG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

I.

Two LCO 3.8.1.b EDGs 1.1 Restore one EDG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable.

OPERABLE status.

J.

Two required J.1 Declare associated Immediately LCO 3.8.1.c EDGs shared components inoperable.

inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-6

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME K.--------NOTE ---------

K.1 Enter appropriate Immediately Separate Condition Conditions and entry is allowed for Required Actions for each sequencing timing any component made relay.

inoperable by inoperable sequencing timing relay(s).

One or more required sequencing timing AND relay(s) inoperable.

K.2.1 Place the component(s)

Immediately with the inoperable sequencing timing relay in a condition where it cannot be automatical ly loaded to associated emergency electrical bus.

OR K.2.2 Declare the associated Immediately EDG inoperable.

L.

Required Action and L.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, AND B, C, G, H, or I not met.

L.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months M. Three or more of M.1 Enter LCO 3.0.3.

Immediately LCO 3.8.1.a and LCO 3.8.1.b AC sources inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-7

AC Sources-Operati ng 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each required offsite circuit.

SR 3.8.1.2

NOTES--------------

1. All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified EDG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each required EDG starts from 31 days standby conditions and achieves steady state voltage Ž 3740 V and

4580 V, and frequency Ž 59.5 Hz and

60.5 Hz.

SR 3.8.1.3

NOTES--------------

1. EDG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one EDG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each required EDG is synchronized 31 days and loaded and operates for Ž 60 minutes at a load Ž 2500 kW and

2600 kW.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-8

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each required day tank contains 31 days

_Ž 450 gal of fuel oil.

SR 3.8.1.5 Check for and remove accumulated water from 92 days each required day tank.

SR 3.8.1.6 Verify each required fuel oil transfer pump 92 days operates to transfer fuel oil from the storage tank to the day tank.

SR 3.8.1.7

NOTE---------------

All EDG starts may be preceded by an engine prelube period.

Verify each required EDG starts from 184 days standby condition and achieves

a. In _*

10 seconds, voltage _> 3960 V and frequency >_ 59.5 Hz; and

b. Steady state voltage _ 3740 V and

_< 4580 V, and frequency _Ž 59.5 Hz and 60.5 Hz.

SR 3.8.1.8

NOTES--------------

1. This Surveillance is only applicable to Unit 1.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify manual transfer of AC power sources 18 months from the normal offsite circuit to the alternate required offsite circuit.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-9

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.9 NOTE---------------

If performed with EDG synchronized with offsite power, it shall be performed at a power factor

0.9. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

Verify each required EDG rejects a load greater than or equal to its associated single largest post-accident load, and:

a. Following load rejection, the frequency is

66 Hz;

b. Within 3 seconds following load rejection, the voltage is Ž 3740 V and

< 4580 V; and

c. Within 3 seconds following load rejection, the frequency is Ž 59.5 Hz and

60.5 Hz.

North Anna Units 1 and 2 I

+/-

FREQUENCY 18 months Amendments 231/212, 3.8.1-10

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.10 ----------------- NOTES--------------

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4.

However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify on an actual or simulated loss of 18 months offsite power signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. Each required EDG auto-starts from standby condition and:

1. energizes permanently connected loads in _*

10 seconds,

2. energizes auto-connected shutdown loads through sequencing timing

relays,

3. maintains steady state voltage

> 3740 V and _< 4580 V,

4. maintains steady state frequency

>_ 59.5 Hz and _ 60.5 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for

_> 5 minutes.

North Anna Units 1 and 2 Amendments 231/212, 3.8.1-11

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.11

NOTES--------------

1. All EDG starts may be preceded by prelube period.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each LCO 3.8.1.b EDG auto-starts from standby condition and:

a. In

10 seconds after auto-start and during tests, achieves voltage Ž 3960 V and frequency Ž 59.5 Hz;

b. Achieves steady state voltage Ž 3740 V and 5 4580 V and frequency Ž 59.5 Hz and

60.5 Hz;

c. Operates for Ž 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized or auto-connected through the sequencing timing relays from the offsite power system.

North Anna Units 1 and 2 FREQUENCY 18 months I

i Amendments 231/212, 3.8.1-12

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.12

NOTE---

This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify each required EDG's automatic trips are bypassed on actual or simulated automatic start signals except:

a. Engine overspeed; and

b. Generator differential current.

North Anna Units 1 and 2 FREQUENCY 18 months I

i Amendments 231/212, 3.8.1-13

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.13 NOTES---------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

3. If performed with EDG synchronized with offsite power, it shall be performed at a power factor

0.9. However, if grid conditions do not permit, the power factor limit is not required to be met.

Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each required EDG operates for

Ž 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For Ž 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2 2900 kW and

< 3000 kW; and

b. For the remaining hours of the test loaded 2 2500 kW and 5 2600 kW.

North Anna Units 1 and 2 I

1*

FREQUENCY 18 months Amendments 231/212, 3.8.1-14

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE

+

SR 3.8.1.14 ------------------ NOTES--------------

1. This Surveillance shall be performed within 5 minutes of shutting down the EDG after the EDG has operated

Ž 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded Ž 2500 kW and

2600 kW or after operating temperatures have stabilized.

Momentary transients outside of load range do not invalidate this test.

2. All EDG starts may be preceded by an engine prelube period.

Verify each required EDG starts and achieves

a. In 5 10 seconds, voltage Ž 3960 V and frequency Ž 59.5 Hz; and

b. Steady state voltage Ž 3740 V, and 5 4580 V and frequency Ž 59.5 Hz and 5 60.5 Hz.

SR 3.8.1.15

NOTE--

This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify each required EDG:

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

FREQUENCY 18 months 18 months North Anna Units 1 and 2 Amendments 231/212, 3.8.1-15

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.16 ----------------

NOTE--------------

This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify each required sequencing timing relay is within the design tolerance.

FREQUENCY 18 months North Anna Units 1 and 2 Amendments 231/212, 3.8.1-16

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVE I LLANCE FREQUENCY SR 3.8.1.17 ---------------- NOTES---------------

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4.

However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify on an actual or simulated loss of 18 months offsite power signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. Each LCO 3.8.1.b EDG auto-starts from standby condition and:

1. energizes permanently connected loads in _< 10 seconds,

2. energizes auto-connected emergency loads through load sequencing timing

relays,

3. achieves steady state voltage

>_ 3740 V and _*

4580 V,

4. achieves steady state frequency

_> 59.5 Hz and < 60.5 Hz, and

5. supplies permanently connected and auto-connected emergency loads for

_> 5 minutes.

North Anna Units 1 and 2 3.8.1-17 Amendments 231/212,

AC Sources-Operating 3.8.1 SURVEILLANCE REOUIREMENTS SURVEILLANCE SR 3.8.1.18

NOTE---------------

All EDG starts may be preceded by an engine prelube period.

Verify when started simultaneously from standby condition, each LCO 3.8.1.b EDG achieves:

a. in 1 10 seconds, voltage A 3960 V and frequency A 59.5 Hz; and

b. steady state voltageŽ: 3740 V and 5 4580 V, and frequency A 59.5 Hz and A 60.5 Hz.

North Anna Units 1 and 2 FREQUENCY 10 years 3.8.1-183 SURVEILLANCE REQUIREMENTS I

i Amendments 231/212,

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown"; and

b. One emergency diesel generators (EDG) capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY:

MODES 5 and 6, During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required offsite

NOTE---------

circuit inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.10, with required trains de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies.

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.8.2-1

AC Sources-Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

B.

One required EDG B.1 Suspend CORE Immediately i noperabl e.

ALTERATIONS.

AND B.2 Suspend movement of Immediately recently irradiated fuel assemblies.

AND B.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.4 Initiate action to Immediately restore required EDG to OPERABLE status.

North Anna Units 1 and 2 Amendments 231/212, 3.8.2-2

AC Sources-Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS NOTE----------------

The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.6, SR 3.8.1.9, SR 3.8.1.10, SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.14, SR 3.8.1.15, and SR 3.8.1.16.

For AC sources required to be OPERABLE, the following SRs are applicable:

SR 3.8.1.1 SR 3.8.1.6 SR 3.8.1.13 SR 3.8.1.2 SR 3.8.1.7 SR 3.8.1.14 SR 3.8.1.3 SR 3.8.1.9 SR 3.8.1.15 SR 3.8.1.4 SR 3.8.1.10 SR 3.8.1.16 SR 3.8.1.5 SR 3.8.1.12 1

FREQUENCY In accordance with applicable SRs North Anna Units 1 and 2 SR 3.8.2.1 SURVEILLANCE Amendments 231/212, 3.8.2-3

Intentionally Blank

Diesel Fuel Oil and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil and Starting Air LCO

3.8.3 APPLICABILITY

The stored diesel fuel oil and starting air subsystem shall be within limits for each required emergency diesel generator (EDG).

When associated EDG(s) is required to be OPERABLE.

ACTIONS NOTE Separate Condition entry is allowed for each EDG.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One fuel oil storage A.1 Verify replacement Prior to tank inoperable to fuel oil is available, removing tank perform an inspection from service or repairs.

AND A.2 Verify remaining fuel Once per oil storage tank 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months contains Ž 45,000 gal.

AND A.3 Verify above ground Once per fuel oil tank contains 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Ž100,000 gal.

AND A.4 Restore fuel oil 7 days storage tank to within limits.

North Anna Units 1 and 2 Amendments 231/212, 3.8.3-1

Diesel Fuel Oil and Starting Air 3.8.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more EDGs with B.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months fuel oil inventory inventory to within

< 90,000 gal and limits.

> 77,200 gal for reasons other than Condition A.

C.

One or more EDGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates within particulates not limit.

within limit.

D.

One or more EDGs with D.1 Restore stored fuel 30 days new fuel oil oil properties to properties not within within limits.

limits.

E.

One or more EDGs with E.1 Restore starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the required starting receiver pressure to air receiver pressure

_> 175 psig.

< 175 psig and

_ 150 psig.

F.

Required Action and F.1 Declare associated Immediately associated Completion EDG(s) inoperable.

Time not met.

OR One or more EDGs diesel fuel oil or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

North Anna Units 1 and 2 Amendments 231/212, 3.8.3-2

Diesel Fuel Oil and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify fuel oil inventory Ž 90,000 gal.

31 days SR 3.8.3.2 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program.

Testing Program SR 3.8.3.3 Verify each EDG air start receiver pressure 31 days is Ž 175 psig.

SR 3.8.3.4 Check for and remove accumulated water from 92 days each stored fuel oil storage tank.

North Anna Units 1 and 2 Amendments 231/212, 3.8.3-3

Intentionally Blank

DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO

3.8.4 APPLICABILITY

The following DC electrical power sources shall be OPERABLE:

a. The Train H and Train J DC electrical power subsystems;

b. The Emergency Diesel Generator (EDG)

DC systems for each required EDG; and

c. One DC electrical power subsystem on the other unit for each required shared component.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One LCO 3.8.4.a DC A.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power power subsystem to subsystem inoperable.

OPERABLE status.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time for Condition A AND not met.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. --------NOTE--------- C.1 Enter applicable Immediately Separate Condition Conditions and entry is allowed for Required Actions for each EDG DC system.

associated EDG(s) made inoperable.

One or more required EDG DC system(s) inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.8.4-1

DC Sources-Operating 3.8.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. --------NOTE ----------

D.1 Declare associated Immediately Separate Condition shared component(s) entry is allowed for inoperable.

each DC subsystem.

One or more required LCO 3.8.4.c DC electrical power subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify for each required Station and EDG 7 days battery, terminal voltage is Ž 129 V on float charge.

SR 3.8.4.2 Verify for each required Station and EDG 92 days battery, there is no visible corrosion at battery terminals and connectors.

OR Verify battery connection resistance is

1.5E-4 ohm for inter-cell connections,

1.5E-4 ohm for inter-rack connections,

1.5E-4 ohm for inter-tier connections, and

1.5E-4 ohm for terminal connections.

SR 3.8.4.3 Verify for each required Station and EDG 18 months battery, cells, cell plates, and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

North Anna Units 1 and 2 Amendments 231/212, 3.8.4-2

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.4 For each required Station and EDG battery, 18 months remove visible terminal corrosion, verify battery cell to cell and terminal connections are clean and coated with anti-corrosion material.

SR 3.8.4.5 Verify for each required Station and EDG 18 months battery, connection resistance is

1.5E-4 ohm for inter-cell connections,

1.5E-4 ohm for inter-rack connections,

1.5E-4 ohm for inter-tier connections, and

1.5E-4 ohm for terminal connections.

SR 3.8.4.6 Verify each required Station battery 18 months charger supplies e 270 amps at Ž 125 V for

Ž 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SR 3.8.4.7 Verify each required EDG battery charger 18 months supplies Ž 10 amps at Ž 125 V for

Ž 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

North Anna Units 1 and 2 Amendments 231/212, 3.8.4-3

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.8

NOTES--------------

1. The modified performance discharge test in SR 3.8.4.9 may be performed in lieu of the service test in SR 3.8.4.8.

2. The performance discharge test in SR 3.8.4.9 may be performed in lieu of the service test in SR 3.8.4.8 once every 60 months.

3. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4.

However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify for each required Station battery, 18 months capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

SR 3.8.4.9

NOTE---------------

This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4 for Station batteries. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.

Verify for each required Station and EDG 60 months battery, capacity is Ž 80% of the manufacturer's rating when subjected to a AND performance discharge test or a modified performance discharge test.

18 months when battery shows degradation or has reached 85%

of expected life North Anna Units 1 and 2 Amendments 231/212, 3.8.4-4

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 DC electrical power subsystem(s) shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown," and EDG DC system shall be OPERABLE for the EDG required by LCO 3.8.2, "AC Sources-Shutdown."

APPLICABILITY:

MODES 5 and 6, During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Declare affected Immediately DC electrical power required feature(s) subsystems inoperable, inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies.

AND A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in a loss of required SDM or boron concentration.

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.8.5-1

DC Sources-Shutdown 3.8.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.4 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.

B.

Required EDG DC system B.1 Enter applicable Immediately inoperable.

Conditions and Required Actions for associated EDG made inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 NOTE---------------

The following SRs are not required to be performed: SR 3.8.4.4, SR 3.8.4.7, SR 3.8.4.8, and SR 3.8.4.9.

For DC sources required to be OPERABLE, the In accordance following SRs are applicable:

with applicable SRs SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8 SR 3.8.4.3 SR 3.8.4.6 SR 3.8.4.9 North Anna Units 1 and 2 Amendments 231/212, 3.8.5-2

Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO

3.8.6 APPLICABILITY

Battery cell parameters for the following batteries shall be within limits:

a. The Train H and Train J DC electrical power subsystems;

b. The Emergency Diesel Generator (EDG)

DC systems for each required EDG; and

c. One DC electrical power subsystem on the other unit for each required shared component.

When associated DC electrical power subsystem(s) or EDG DC system(s) are required to be OPERABLE.

ACTIONS

- NOTE Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Station or A.1 Verify pilot cell 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months EDG batteries with one electrolyte level and or more battery cell float voltage meet parameters not within Table 3.8.6-1 Table 3.8.6-1 Category C limits.

Category A or B limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 AND Category C limits.

Once per 7 days thereafter AND

_(continued)

North Anna Units 1 and 2 Amendments 231/212, 3.8.6-1

Battery Cell Parameters 3.8.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Restore battery cell 31 days parameters to Table 3.8.6-1 Category A and B limits.

B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more Station batteries with average electrolyte temperature of the representative cells

< 60 0F.

OR One or more Station or EDG batteries with one or more battery cell parameters not within Table 3.8.6-1 Category C values.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify for each required Station and EDG 7 days battery cell parameters meet Table 3.8.6-1 Category A limits.

North Anna Units 1 and 2 Amendments 231/212, 3.8.6-2

Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.6.2 Verify for each required Station and EDG battery cell parameters meet Table 3.8.6-1 Category B limits.

FREQUENCY 1-92 days AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a battery discharge

< 110 V AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a battery overcharge

> 150 V SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells for each required Station battery is Ž 60 0F.

North Anna Units 1 and 2 Amendments 231/212, 3.8.6-3

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameters Requirements CATEGORY C:

CATEGORY A: LIMITS CATEGORY B: LIMITS ALLOWABLE LIMITS FOR EACH DESIGNATED FOR EACH CONNECTED FOR EACH CONNECTED PARAMETER PILOT CELL CELL CELL Electrolyte Level

> Minimum level

> Minimum level Above top of indication mark, indication mark, plates, and not and ! k inch above and : k inch above overflowing maximum level maximum level indication indication mark(a) mark(a)

Float Voltage

> 2.13 V

> 2.07 V Speci fic

> 1.200

_> 1.195 Not more than Graviity~b) (c) 0.020 below AND average of all connected cells Average of all connected cell s AND

> 1.205 Average of all connected cells

> 1.195 (a)

It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b)

Corrected for electrolyte temperature and level. Level correction is not required for Station batteries when battery charging is < 2 amps when on float charge.

(c)

Station batteries only: A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

Amendments 231/212, North Anna Units 1 and 2 3.8.6-4

Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO

3.8.7 APPLICABILITY

The Train H and Train J inverters shall be OPERABLE.

NOTE--

One inverter may be disconnected from its associated DC bus for

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform an equalizing charge on its associated battery, provided:

a. The associated AC vital bus is energized from its constant voltage source transformer; and

b. All other AC vital buses are energized from their associated OPERABLE inverters.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One inverter A.1

NOTE-----

inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution Systems-Operating" with any vital bus de-energized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associ ated Completion Time not met.

AND B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months North Anna Units 1 and 2 3.8.7-1 Amendments 231/212,

Inverters-Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage and 7 days alignment to required AC vital buses.

North Anna Units 1 and 2 Amendments 231/212, 3.8.7-2

Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO 3.8.8 Inverter(s) shall be OPERABLE to support the onsite Class 1E AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown."

APPLICABILITY:

MODES 5 and 6, During movement of ACTIONS recently irradiated fuel assemblies.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required inverters inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies.

AND A.2.3 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.4 Initiate action to restore required inverters to OPERABLE status.

Inmmedi ately Immedi atel y Immedi ately Immediately Immediately L

North Anna Units 1 and 2 3.8.8-1 Amendments 231/212,

Inverters-Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage and 7 days alignments to required AC vital buses.

North Anna Units 1 and 2 Amendments 231/212, 3.8.8-2

Distribution Systems-Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems-Operating LCO 3.8.9 APPLICABILITY:

The following distribution subsystems shall be OPERABLE:

a. The Train H and Train J AC, DC, and AC vital buses; and

b. One AC and DC bus on the other unit for each required shared component.

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1

NOTE-----

LCO 3.8.9.a AC Enter applicable electrical power Conditions and distribution Required Actions of subsystem(s)

LCO 3.8.4, "DC inoperable.

Sources-Operating,"

for DC train(s) made inoperable by inoperable di stri buti on subsystem(s).

Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months power distribution subsystem(s) to AND OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO North Anna Units 1 and 2 Amendments 231/212, 3.8.9-1

Distribution Systems-Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more B.1 Restore AC vital bus 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO 3.8.9.a AC vital subsystem(s) to bus(es) inoperable.

OPERABLE status.

AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO C.

One or more C.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO 3.8.9.a DC power distribution electrical power subsystem(s) to AND distribution OPERABLE status.

subsystem(s) 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from inoperable, discovery of failure to meet LCO D. --------NOTE ---------- D.1 Declare associated Immediately Separate Condition shared component(s) entry is allowed for inoperable.

each AC subsystem.

One or more required LCO 3.8.9.b AC electrical power distribution subsystem(s) inoperable.

E. -------- NOTE ---------- E.1 Declare associated Immediately Separate Condition shared component(s) entry is allowed for inoperable.

each DC subsystem.

One or more required LCO 3.8.9.b DC electrical power distribution subsystem(s) inoperable.

North Anna Units 1 and 2 Amendments 231/212, 3.8.9-2

Distribution Systems-Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.

Required Action and F.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A, AND B, or C not met.

F.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G.

Two or more G.1 Enter LCO 3.0.3.

Immediately LCO 3.8.9.a electrical power distribution subsystems inoperable that result in a loss of safety function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and 7 days voltage to required AC, DC, and AC vital bus electrical power distribution subsystems.

North Anna Units 1 and 2 Amendments 231/212, 3.8.9-3

Intentionally Blank

Distribution Systems-Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEM 3.8.10 Distribution Systems-Shutdown LCO 3.8.10 APPLICABILITY:

The necessary portion of AC, DC, and AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

MODES 5 and 6, During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare associated Immediately AC, DC, or AC vital supported required bus electrical power feature(s) inoperable.

distribution subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently i rradi ated fuel assemblies.

AND A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.8.10-1

Distribution Systems-Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.4 Initiate actions to Immediately restore required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and 7 days voltage to required AC, DC, and AC vital bus electrical power distribution subsystems.

North Anna Units 1 and 2 Amendments 231/212, 3.8.10-2

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO

3.9.1 APPLICABILITY

Boron concentrations of the Reactor Coolant System (RCS),

the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.

MODE 6.

NOTE-Only applicable to the refueling canal and refueling cavity when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration A.1 Suspend CORE Immediately not within limit.

ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

AND A.3 Initiate action to Immediately restore boron concentration to within limit.

SURVEILLANCE REQUIREMENTS_

SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit specified in the COLR.

North Anna Units 1 and 2 3.9.1-1 Amendments 231/212,

Intentionally Blank

Primary Grade Water Flow Path Isolation Valves-MODE 6 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Primary Grade Water Flow Path Isolation Valves-MODE 6 LCO

3.9.2 APPLICABILITY

Each valve used to isolate primary grade water flow paths shall be secured in the closed position.

NOTE -------------

Primary grade water flow path isolation valves may be opened under administrative control for planned boron dilution or makeup activities.

MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE --------- A.1 Suspend CORE Immediately Required Action A.3 ALTERATIONS.

must be completed whenever Condition A AND is entered.

A.2 Secure valves in 15 minutes closed position.

One or more valves not secured in closed AND position.

A.3 Perform SR 3.9.1.1.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each valve in the affected flow path Within that isolates primary grade water flow 15 minutes paths is locked, sealed, or otherwise following a secured in the closed position.

boron dilution or makeup activity North Anna Units 1 and 2 3.9.2-1 Amendments 231/212,

Intentionally Blank

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO

3.9.3 APPLICABILITY

Two source range neutron flux monitors shall be OPERABLE.

MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One source range A.1 Suspend CORE Immediately neutron flux monitor ALTERATIONS.

inoperable.

AND A.2 Suspend operations Immediately that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B.

Two source range B.1 Initiate action to Immediately neutron flux monitors restore one source inoperable, range neutron flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 and 2 Amendments 231/212, 3.9.3-1

Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.3.2

NOTE----------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

18 months North Anna Units 1 and 2 Amendments 231/212, 3.9.3-2

Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:

a. The equipment hatch closed and held in place by four bolts;

b. One door in each air lock is capable of being closed; and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE containment purge and exhaust isolation valve.

NOTE -------------

Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

APPLICABILITY:

During movement of containment.

recently irradiated fuel assemblies within ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Suspend movement of Immediately containment recently irradiated penetrations not in fuel assemblies within required status.

containment.

North Anna Units 1 and 2 Amendments 231/212, 3.9.4-1

Containment Penetrations 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment 7 days penetration is in the required status.

SR 3.9.4.2

NOTE---------------

Not required to be met for containment purge and exhaust valve(s) in penetrations closed to comply with LCO 3.9.4.c.1.

Verify each required containment purge and 18 months exhaust valve actuates to the isolation position on manual initiation.

North Anna Units 1 and 2 Amendments 231/212, 3.9.4-2

RHR and Coolant Circulation-High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.

NOTE-The required RHR loop may be removed from operation for

< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction into the Reactor Coolant System (RCS),

coolant of boron concentration less than required to meet the minimum required boron concentration of LCO 3.9.1.

APPLICABILITY:

MODE 6 with the water level Ž 23 ft above vessel flange.

the top of reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RHR loop requirements A.1 Suspend operations Immediately not met.

that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.

AND A.3 Initiate action to Immediately sati sfy RHR loop requirements.

AND (continued)

North Anna Units 1 and 2 Amendments 231/212, 3.9.5-1

RHR and Coolant Circulation-High Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4 Close equipment hatch 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and secure with four bolts.

AND A.5 Close one door in each 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months installed air lock.

AND A.6.1 Close each penetration 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR A.6.2 Verify each 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetration is capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circulating reactor coolant at a flow rate of Ž 3000 gpm.

North Anna Units 1 and 2 Amendments 231/212, 3.9.5-2

RHR and Coolant Circulation-Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

NOTES--

1. All RHR pumps may be removed from operation for

15 minutes when switching from one train to another provided:

a. The core outlet temperature is maintained > 10OF below saturation temperature;

b. No operations are permitted that would cause a reduction of the Reactor Coolant System boron concentration; and

c.

No draining operations to further reduce RCS volume are permitted.

2. One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided that the other loop is OPERABLE and in operation.

APPLICABILITY:

MODE 6 with the water level < 23 ft above vessel flange.

the top of reactor ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Less than the required A.1 Initiate action to Immediately number of RHR loops restore required RHR OPERABLE.

loops to OPERABLE status.

OR A.2 Initiate action to Immediately establish Ž 23 ft of water above the top of reactor vessel flange.

North Anna Units 1 and 2 3.9.6-1 Amendments 231/212,

RHR and Coolant Circulation-Low Water Level 3.9.6 CONDITION REQUIRED ACTION COMPLETION TIME B.

No RHR loop in operation.

B.1 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore one RHR loop to operation.

AND B.3 Close equipment hatch and secure with four bolts.

AND B.4 Close one door in each installed air lock.

AND B.5.1 Close each penetration providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.

OR Immediately Immediately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

North Anna Units 1 and 2 ACTIONS

_I_

[

I__

Amendments 231/212, 3.9.6-2

RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.5.2 Verify each 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetration is capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circulating reactor coolant at a flow rate of:

a. Ž 3000 gpm, or

b. Ž 2000 gpm if RCS temperature

140°F and time since entry into MODE 3

Ž 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

SR 3.9.6.2

NOTE---------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after a required RHR pump is not in operation.

Verify correct breaker alignment and 7 days indicated power available to the required RHR pump that is not in operation.

North Anna Units 1 and 2 Amendments 231/212, 3.9.6-3

Intentionally Blank

Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Refueling Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained Ž 23 ft above the top of reactor vessel flange.

APPLICABILITY:

During movement of containment.

irradiated fuel assemblies within ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within irradiated fuel limit.

assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify refueling cavity water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Ž 23 ft above the top of reactor vessel flange.

North Anna Units 1 and 2 Amendments 231/212, 3.9.7-1

Intentionally Blank

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The North Anna Power Station is located in the north-central portion of Virginia in Louisa County and is approximately 40 miles north-northwest of Richmond, 36 miles east of Charlottesville; 22 miles southwest of Fredericksburg; and 70 miles southwest of Washington, D.C. The site is on a peninsula on the southern shore of Lake Anna at the end of State Route 700.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U02) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.

4.2.2 Control Rod Assemblies The reactor core shall contain 48 control rod assemblies. The control material shall be silver indium cadmium, as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.6 weight percent; North Anna Units 1 and 2 Amendments 231/212, 4.0-1

Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued)

b. keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties calculated in accordance with the methodology described in Virginia Electric and Power Company letter dated September 27, 2000 (Serial No.00-491);

c. keff

0.95 if fully flooded with water borated to 350 ppm, which includes an allowance for uncertainties calculated in accordance with the methodology described in Virginia Electric and Power Company letter dated September 27, 2000 (Serial No.00-491); and

d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.6 weight percent;

b. keff

0.95 if fully flooded with unborated water, which includes an allowance for uncertainties;

c. keff

0.98 if moderated by aqueous foam, which includes an allowance for uncertainties; and

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with. a storage capacity limited to no more than 1737 fuel assemblies.

North Anna Units 1 and 2 Amendments 231/212, 4.0-2

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The Shift Supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

North Anna Units 1 and 2 Amendments 231/212, 5.1-1

Intentionally Blank

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions.

These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the UFSAR/QA Plan;

b.

The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c.

A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d.

The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

North Anna Units 1 and 2 Amendments 231/212, 5.2-1

Organization 5.2 5.2 Organization 5.2.2 Unit Staff The unit staff organization shall include the following:

a.

An auxiliary operator shall be assigned to each reactor containing fuel and an additional auxiliary operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

Two unit sites with both units shutdown or defueled require a total of three auxiliary operators for the two units.

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs),

licensed Reactor Operators (ROs),

health physicists, auxiliary operators, and key maintenance personnel).

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the above guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

North Anna Units 1 and 2 Amendments 231/212, 5.2-2

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

e.

The operations manager shall hold (or have previously held) a Senior Reactor Operator License for North Anna or a similar design Pressurized Water Reactor plant. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for North Anna Power Station.

f.

An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

North Anna Units 1 and 2 Amendments 231/212, 5.2-3

Intentionally Blank

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI 3.1 (12/79 Draft) for comparable positions.

Exceptions to this requirement are specified in VEPCO's QA Topical Report, VEP-1, "Quality Assurance Program, Operational Phase." The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The SS, Assistant SS, Control Room Operator-Nuclear, and the individual providing advisory technical support to the unit operations shift crew, shall meet or exceed the minimum qualifications of 10 CFR 55.59(c) and 55.31(a) (4).

5.3.2 For the purpose of 10 CFR 55.4, a licensed SRO and a licensed RO are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

North Anna Units 1 and 2 Amendments 231/212, 5.3-1

Intentionally Blank

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a.

The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b.

The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c.

Quality assurance for effluent and environmental monitoring;

d.

Fire Protection Program implementation; and

e.

All programs specified in Specification 5.5.

North Anna Units 1 and 2 Amendments 231/212, 5.4-1

Intentionally Blank

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a.

The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b.

The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Annual Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3.

Licensee initiated changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s),

and

2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b.

Shall become effective after the approval of the plant manager; and

c.

Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

North Anna Units 1 and 2 Amendments 231/212, 5.5-1

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Recirculation Spray, Safety Injection, Chemical and Volume Control, gas stripper, and Hydrogen Recombiner. The program shall include the following:

a.

Preventive maintenance and periodic visual inspection requirements; and

b.

Integrated leak test requirements for each system at least once per 18 months.

The provisions of SR 3.0.2 are applicable.

5.5.3 Reserved 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; North Anna Units 1 and 2 Amendments 231/212, 5.5-2

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate

500 mrem/yr to the whole body and a dose rate

3000 mrem/yr to the skin, and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate

1500 mrem/yr to any organ;

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and North Anna Units 1 and 2 Amendments 231/212, 5.5-3

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

j.

Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 5.2, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant.Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel once every 10 years by a qualified inplace UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces defined by the volume of disassembled flywheels.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program surveillance frequency.

North Anna Units 1 and 2 Amendments 231/212, 5.5-4

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a.

Testing frequencies specified in the ASME Code for Operation and Maintenance of Nuclear Power Plants and applicable Addenda as follows:

ASME Code for Operation and Maintenance of Nuclear Power Plants and applicable Addenda Required Frequencies for terminology for inservice performing inservice testing activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b.

The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

c.

The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d.

Nothing in the ASME Code for Operation and Maintenance of Nuclear Power Plants shall be construed to supersede the requirements of any TS.

5.5.8 Steam Generator (SG) Tube Surveillance Program The provisions of SR 3.0.2 are applicable to the SG Tube Surveillance Program test Frequencies.

North Anna Units 1 and 2 Amendments 231/212, 5.5-5

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Tube Surveillance Program (continued)

This program provides the controls for the inservice inspection of steam generator tubes to ensure that the structural integrity of this portion of the RCS is maintained. The program for inservice inspection of steam generators is based on a modification of Regulatory Guide 1.83, Revision 1. This program shall include:

5.5.8.1 Steam Generator Sample Selection and Inspection Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 5.5.8-1.

5.5.8.2 Steam Generator Tube Sample Selection and Inspection The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.5.8-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 5.5.8.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.8.4. The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a.

Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.

b.

The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1. All nonplugged tubes that previously had detectable wall penetrations > 20%, and

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 5.5.8.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

North Anna Units 1 and 2 Amendments 231/212, 5.5-6

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8.2 Steam Generator Tube Sample Selection and Inspection (continued)

c.

The tubes selected as the second and third samples (if required by Table 5.5.8.2) during each inservice inspection may be subjected to a partial tube inspection provided:

1.

The tubes selected for these samples include the tubes from those areas of the tube sheet array where, tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories:

Category Inspection Resultsa C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

a.

In all inspections, previously degraded tubes must exhibit significant

(> 10%) further wall penetrations to be included in the above percentage calculations.

5.5.8.3 Inspection Frequencies The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a.

The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-7

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8.3 Inspection Frequencies

a.

(continued) not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

b.

If the results of the inservice inspection of a steam generator conducted in accordance with Table 5.5.8-2 at 40 month intervals fall into category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.8.3.a; the interval may then be extended to a maximum of once per 40 months.

c.

Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 5.5.8-2 during the shutdown subsequent to any of the following conditions:

1. Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.13.

2. A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

4. A major steam line or feedwater line break.

5.5.8.4 Acceptance Criteria

a.

As used in this Specification:

1.

Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

North Anna Units 1 and 2 Amendments 231/212, 5.5-8

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8.4 Acceptance Criteria

a.

(continued)

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3. Degraded Tube means a tube containing imperfections > 20% of the nominal wall thickness caused by degradation.

4. % Degradation means the percentage of the tube wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

6. Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 5.5.8.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry completely around the U-bend to the top support.

9. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy-current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed using the equipment and techniques expected to be used during subsequent inservice inspection.

b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 5.5.8-2.

North Anna Units 1 and 2 Amendments 231/212, 5.5-9

Programs and Manuals 5.5 Table 5.5.8-1 Minimum Number of Steam Generators to Be Inspected During Inservice Inspection Preservice Inspection No Yes No. of Steam Generators per Unit Two Three Four Two Three Four First Inservice Inspection All One Two Two Second & Subsequent Inservice Inspection One' One' One 2 One 3 Table Notation:

1. The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3N% of the tubes (where N is the number of steam generators in the unit) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

2. The other steam generator not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in 1 above.

3. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected during the second and third inspections. The fourth and subsequent inspections shall follow the instructions described in 1 above.

North Anna Units 1 and 2 Amendments 231/212, 5.5-10

Programs and Manuals 5.5 Table 5.5.8-2 Steam Generator Tube Inspection 1st Sample Inspection 2nd Sample Inspection 3rd Sample Inspection Sample Action Action Action Size Result Required Result Required Result Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per C-2 Plug defective C-1 None N/A N/A SG tubes and C-2 Plug defective C-i None inspect tubes and C-2 Plug defective additional 2S inspect tubes tubes in SG additional 4S tubes tubes in SG C-3 Perform action for C-3 result of first sample C-3 Perform action N/A N/A for C-3 result of first sample C-3 Inspect all All other None N/A N/A tubes in this SGs are SG, plug C-1 defective tubes Some SGs Perform action N/A N/A and inspect 2S C-2 but no for C-2 result tubes in each additional of second sample other SG SG are C-3 Additional Inspect all N/A N/A SG is C-3 tubes in each SG and plug defective tubes S = 3[N/n]%

Where N is the number of steam generators in the unit, steam generators inspected during an inspection.

and n is the number OT North Anna Units 1 and 2 Amendments 231/212, 5.5-11

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:

a.

Identification of a sampling schedule for the critical variables and control points for these variables;

b.

Identification of the procedures used to measure the values of the critical variables;

c.

Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage;

d.

Procedures for the recording and management of data;

e.

Procedures defining corrective actions for all off control point chemistry conditions; and

f.

A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.10 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems in general conformance with the frequencies and requirements of Regulatory Positions C.5.a, C.5.c, C.5.d, and C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, and ANSI N510-1975.

a.

Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 1.0% when tested in accordance (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-12

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP)

a.

(continued) with Regulatory Positions C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2, March 1978, and ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System Flowrate Main Control Room/Emergency Switchgear 1000 +/- 10% cfm Room (MCR/ESGR)

Emergency Ventilation System (EVS)

Emergency Core Cooling System (ECCS)

Nominal Pump Room Exhaust Air Cleanup System accident flow (PREACS) for a single train actuation Nominal accident flow for a single train actuation is greater than the minimum required cooling flow for ECCS equipment operation, and

39,200 cfm, which is the maximum flow rate providing an adequate residence time within the charcoal adsorber.

b.

Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass

< 1.0% when tested in accordance with Regulatory Positions C.5.a and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System MCR/ESGR EVS ECCS PREACS Flowrate 1000 +/- 10% cfm Nominal accident flow for a single train actuation Nominal accident flow for a single train actuation is greater than the minimum required cooling flow for ECCS equipment operation, and

39,200 cfm, which is the maximum flow rate providing an adequate residence time within the charcoal adsorber.

c.

Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration less than the (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-13

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (VFTP)

c.

(continued) value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 300C (860F) and relative humidity specified below.

ESF Ventilation System Penetration RH MCR/ESGR EVS 2.5%

70%

ECCS PREACS 5%

70%

d.

Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with ANSI N510-1975 at the system flowrate specified below.

ESF Ventilation System Delta P Flowrate MCR/ESGR EVS 4 inches W.G.

1000 +/- 10% cfm ECCS PREACS 5 inches W.G.

39,200 cfm

e.

Demonstrate that the heaters for each of the ESF systems dissipate Ž the value specified below when tested in accordance with ASME N510-1975.

ESF Ventilation System Wattage MCR/ESGR EVS 3.5 kW The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Gaseous Waste System, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP)

ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or (continued)

North Anna Units 1 and 2 5.5-14 Amendments 231/212,

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

Failure". The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures".

The program shall include:

a.

The limits for concentrations of hydrogen and oxygen in the Gaseous Waste System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

b.

A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of 2 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and

c.

A surveillance program to ensure that the quantity of radioactivity contained in each of the following outdoor tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains liquid radwaste ion exchanger system is less than the amount that would result in concentrations greater than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, excluding tritium, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents:

1. Refueling Water Storage Tank;

2. Casing Cooling Storage Tank;

3. PG Water Storage Tank;

4. Boron Recovery Test Tank; and

5. Any Outside Temporary Tank.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

North Anna Units 1 and 2 Amendments 231/212, 5.5-15

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a.

Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within

limits,

2. a flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. water and sediment

0.05%.

b.

Within 31 days following addition of the new fuel oil to storage tanks verify that the properties of the new fuel oil, other than those addressed in a. above, are within limits for ASTM 2D fuel oil;

c.

Total particulate concentration of the stored fuel oil is

10 mg/l when tested every 92 days in accordance with ASTM D-2276, Method A-2 or A-3; and

d.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program testing Frequencies.

5.5.13 Technical Specifications (TS)

Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. a change in the TS incorporated in the license; or (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-16

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Technical Specifications (TS) Bases Control Program (continued)

b.

(continued)

2. a change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d.

Proposed changes that meet the criteria of Specification 5.5.13b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.14 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists.

Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a.

Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b.

Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c.

Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d.

Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or loss of onsite diesel generator(s),

a safety function assumed in the accident (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-17

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (SFDP)

(continued) analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a.

A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b.

A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c.

A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.15 Containment Leakage Rate Testing Program

a.

A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995.

b.

The calculated peak containment internal pressure for the design basis loss of coolant accident, Pas is 44.1 psig. The containment design pressure is 45 psig.

c.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of containment air weight per day.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 5.5-18

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

d.

Leakage Rate acceptance criteria are:

1. Prior to entering a MODE where containment OPERABILITY is required, the containment leakage rate acceptance criteria are:

0.60 La for the Type B and Type C tests on a Maximum Path Basis and

0.75 La for Type A tests.

During operation where containment OPERABILITY is required, the containment leakage rate acceptance criteria are:

1.0 La for overall containment leakage rate and

0.60 La for the Type B and Type C tests on a Minimum Path Basis.

2. Overall air lock leakage rate testing acceptance criterion is

0.05 La when tested at Ž Pa

e.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

f.

Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

North Anna Units 1 and 2 Amendments 231/212, 5.5-19

Intentionally Blank

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Report

NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent > 100 mrems and the associated collective deep dose equivalent (reported in person rem) according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.

This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket ionization chamber, thermoluminescence dosimeter (TLD),

electronic dosimeter, or film badge measurements. Small exposures totaling < 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report covering the previous calendar year shall be submitted by April 30 of each year.

5.6.2 Annual Radiological Environmental Operating Report NOTE....

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM),

and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

(continued)

North Anna Units 1 and 2 Amendments 231/212, 5.6-1

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements commensurate with the format in the ODCM.

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Annual Radioactive Effluent Release Report

NOTE---

A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Annual Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Safety Limits,

2.

SHUTDOWN MARGIN, (conti nued)

North Anna Units 1 and 2 Amendments 231/212, 5.6-2

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

(continued)

3.

Moderator Temperature Coefficient,

4. Shutdown Bank Insertion Limits,

5. Control Bank Insertion Limits,

6.

AXIAL FLUX DIFFERENCE limits,

7. Heat Flux Hot Channel Factor,

8. Nuclear Enthalpy Rise Hot Channel Factor,

9.

Power Factor Multiplier, 1O.Reactor Trip System Instrumentation -

OTAT and OPAT Trip Parameters, 11.RCS Pressure, Temperature, and Flow DNB Limits, and 12.Boron Concentration.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. VEP-FRD-42, "Reload Nuclear Design Methodology."

2.

WCAP-9220-P-A, "WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION."

3. WCAP-9561-P-A, "BART A-i: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS-SPECIAL REPORT:

THIMBLE MODELING IN W ECCS EVALUATION MODEL."

4. WCAP-10266-P-A, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code."

5. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."

(continued)

North Anna Units 1 and 2 Amendments 231/212, 5.6-3

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

b.

(continued)

6. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code."

7. WCAP-12610, "VANTAGE+

FUEL ASSEMBLY-REFERENCE CORE REPORT."

8. VEP-NE-2-A, "Statistical DNBR Evaluation Methodology."

9. VEP-NE-3-A, "Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code."

10. VEP-NE-1-A, "VEPCO Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications."

11. WCAP-8745-P-A, "Design Bases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function."

12. WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report."

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 PAM Report When a report is required by Condition B of LCO 3.3.3, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

North Anna Units 1 and 2 Amendments 231/212, 5.6-4

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report

a.

Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Nuclear Regulatory Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be reported to the NRC by March 1 of each year for the previous calender year. This report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged.

c.

Results of steam generator tube inspections that fall into Category C-3 require prompt notification of the Commission pursuant to Section 50.72 to 10 CFR Part 50. A Licensee Event Report shall be submitted pursuant to Section 50.73 to 10 CFR Part 50 and shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

North Anna Units 1 and 2 Amendments 231/212, 5.6-5

Intentionally Blank

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.7-1

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

d.

(continued)

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, Mi) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)

Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

North Anna Units 1 and 2 Amendments 231/212, 5.7-2

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a.

Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the radiation protection shift supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)

North Anna Units 1 and 2 Amendments 231/212.

5.7-3

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

d.

(continued)

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)

Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3),

above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f.

Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual (continued)

North Anna Units 1 and 2 Amendments 231/212, 5.7-4

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

f.

(continued) area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

North Anna Units 1 and 2 5.7-5 Amendments 231/212,

Intentionally Blank

v t e Letter Sequence Other
TAC:MB0799, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MB0800, Nis Power Range Channel Daily SR TS Change to Address LOW Power Decalibration, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML020650715, ML020840253, ML021220053, ML021220061, ML021220067, ML021220088, ML021220108, ML021220166, ML021220192, ML021220214, ML021220221, ML021220224, ML021220254, ML021550518
MONTHYEAR2002-02-20 [Table View]

ML021220166

Text

3.5.5 APPLICABILITY

3.5.6 APPLICABILITY

3.6.1 APPLICABILITY

3.6.3 APPLICABILITY

3.6.8 APPLICABILITY

3.7.1 APPLICABILITY

3.7.2 APPLICABILITY

3.7.4 APPLICABILITY

3.7.5 APPLICABILITY

3.7.6 APPLICABILITY

3.7.7 APPLICABILITY

3.7.8 APPLICABILITY

3.7.9 APPLICABILITY

3.8.1 APPLICABILITY

3.8.3 APPLICABILITY

3.8.4 APPLICABILITY

3.8.6 APPLICABILITY

3.8.7 APPLICABILITY

3.9.1 APPLICABILITY

3.9.2 APPLICABILITY

3.9.3 APPLICABILITY

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