ML082390023

B.2

Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months

C.

One channel or train

C.1

Restore channel or

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

train to OPERABLE

status.

-

C.2.1

Initiate action to

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

fully insert all rods.

AND

(continued)

North Anna Units 1 and 2

3.3.1-1

Amendment 231/212

ACTIONS

-

NUCLEI~R DESIGN INFORMAnON POR rAL--

RTS Instrumentation

3.3.1

CONDITION

C.

(continued)

D.

One Power Range

Neutron Flux-High

channel inoperable.

REQUIRED ACTION

C.2.2

Place the Rod Control

System in a condition

incapable of rod

withdrawal.

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

The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

for surveillance testing and

setpoint adjustment of other

channels.

COMPLETION TIME

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months

0.1.1

Place channel in trip.

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

AND

0.1.2

Reduce THERMAL POWER

to :::; 75% RTP.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

0.2.1

Place channel in trip.

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

AND

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

Only required to be performed

when the Power Range Neutron

Flux input to QPTR is

0.2.2

Perform SR 3.2.4.2.

0.3

Be in MODE 3.

North Anna Units 1 and 2

3.3.1-2

Once per

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

78 hours

Amendment 231/212

-

NUCLEAR DESIGN INFORMATION PORTAL-

ACTIONS

RTS Instrumentation

3.3.1

CONDITION

REQUIRED ACTION

COMPLETION TIME

E.

One channel

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

The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

for surveillance testing of

other channels.

E.1

Place channel in trip.

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

E.2

Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

F.

One Intermediate Range

F.1

Reduce THERMAL POWER

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

Neutron Flux channel

to < P-6.

F.2

Increase THERMAL POWER

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

to > P-10.

G.

Two Intermediate Range

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

Neutron Flux channels

Limited plant cool down or

boron dilution is allowed

provided the change is

accounted for in the

calculated SDM.

G.1

Suspend operations

Inmediately

involving positive

reactivity additions.

AND

G.2

Reduce THERMAL POWER

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

to < P-6.

North Anna Units 1 and 2

3.3.1-3

Amendment 231/212

-- NUCLEAR DESIGN INFORMATION PORTAL ---

RTS Instrumentation

3.3.1

ACTIONS

CONDITION

REQUIRED ACTION

COMPLETION TIME

H.

One Source Range

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

Neutron Flux channel

Limited plant cool down or

boron dilution is allowed

provided the change is

accounted for in the

calculated SDM.

H.l

Suspend operations

Inmediately

involving positive

reactivity additions.

1.

Two Source Range

1.1

Open Reactor Trip

Immediately

Neutron Flux channels

Breakers (RTBs).

J.

One Source Range

J.1

Restore channel to

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

Neutron Flux channel

OPERABLE status.

-

J.2.1

Initiate action to

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

fully insert all rods.

AND

J.2.2

Place the Rod Control

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months

System in a condition

incapable of rod

withdrawal.

North Anna Units 1 and 2

3.3.1-4

Amendment 231/212

--- NUCLEAR DESIGN INFORMATION PORTAL--

ACTIONS

RTS Instrumentation

3.3.1

CONDITION

REQUIRED ACTION

COMPLETION TIME

K.

Required Source Range

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

Neutron Flux channel

Plant temperature changes are

allowed provided the

temperature change is

accounted for in the

calculated SDM.

K.1

Suspend operations

Irrrnediately

involving positive

reactivity additions.

AND

K.2

Perform SR 3.1.1.1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

AND

Once per

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

thereafter

L.

One channel

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

The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

for surveillance testing of

other channels.

L.1

Place channel in trip.

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

L.2

Reduce THERMAL POWER

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

to < P-7.

North Anna Units 1 and 2

3.3.1-5

Amendment 231/212

-

NUCLEAR DESIGN INFORMATION PORTAL--

RTS Instrumentation

3.3.1

ACTIONS

CONDITION

REQUIRED ACTION

COMPLETION TIME

M.

One Reactor Coolant

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

Pump Breaker Position

The inoperable channel may be

channel inoperable.

bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

for surveillance testing of

other channels.

M.1

Restore channel to

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

OPERABLE status.

-

M.2

Reduce THERMAL POWER

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

to < P-7.

N.

One Turbine Trip

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

channel inoperable.

The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

for surveillance testing of

other channels.

N.1

Place channel in trip.

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

N.2

Reduce THERMAL POWER

76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months

to < P-8.

O.

One train inoperable.

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

One train may be bypassed for

up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for

surveillance testing provided

the other train is OPERABLE.

0.1

Restore train to

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

OPERABLE status.

0.2

Be in MODE 3.

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

North Anna Units 1 and 2

3.3.1-6

Amendment 231/212

_._- NUCLEAR DESIGN INFORMATION PORTAL-

ACTIONS

RTS Instrumentation

3.3.1

CONDITION

REQUIRED ACTION

COMPLETION TIME

P.

One RTB train

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

1. One train may be bypassed

for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for

surveillance testing,

provided the other train

is OPERABLE.

2. One RTB may be bypassed

for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for

maintenance on

undervo1tage or shunt trip

mechanisms, provided the

other train is OPERABLE.

3. One RTB train may be

bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

for concurrent

surveillance testing of

the RTB and automatic trip

logic, provided the other

train is OPERABLE.

P.1

Restore train to

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

OPERABLE status.

P.2

Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

Q.

One or more channels

Q.l

Verify interlock is in

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

required state for

existing unit

conditions.

Q.2

Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

North Anna Units 1 and 2

3.3.1-7

Amendment 231/212

--- NUCLEAR DESIGN INFORMATION PORTAL-

RTS Instrumentation

3.3.1

ACTIONS

CONDITION

REQUIRED ACTION

COMPLETION TIME

R.

One or more channels

R.1

Verify interlock is in

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

required state for

existing unit

conditions.

R.2

Be in MODE 2.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months

S.

One trip mechanism

S.l

Restore inoperable

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

inoperable for one

trip mechanism to

RTB.

OPERABLE status.

-

S.2

Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SR

3.3.1.2

SURVEILLANCE

Perform CHANNEL CHECK.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

after THERMAL POWER is

~ 15% RTP.

FREQUENCY

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

Compare results of calorimetric heat

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

balance calculation to power range channel

output. Adjust power range output if

calorimetric heat balance calculation

result exceeds power range channel output

by more than +2% RTP.

North Anna Units 1 and 2

3.3.1-8

Amendment 231/212

--- NUCLEAR DESIGN INFORMAnON PORTAL--

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SR 3.3.1. 3

SR

3.3.1. 5

SR 3.3.1.6

SR

3.3.1. 7

SURVEILLANCE

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

Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

after THERMAL POWER is

~ 15% RTP.

Compare results of the incore detector

measurements to Nuclear Instrumentation

System (NIS) AFD. Adjust NIS channel if

absolute difference is

~ 3%.

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

This Surveillance must be performed on the

reactor trip bypass breaker immediately

after placing the bypass breaker in

service.

Perform TADOT.

Perform ACTUATION LOGIC TEST.

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

Verification of setpoint is not required.

Perform TADOT.

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

Not required to be performed for source

range instrumentation prior to entering

MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after

entry into MODE 3.

Perform COT.

FREQUENCY

31 effective

full power days

(EFPD)

31 days on a

STAGGERED TEST

BASIS

31 days on a

STAGGERED TEST

BASIS

92 days

North Anna Units 1 and 2

3.3.1-9

Amendment 231/212

-

NUCLEAR DESIGN INFORMATION PORTAL-

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SR 3.3.1.8

SURVEILLANCE

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

This Surveillance shall include

verification that interlocks P-6 and P-10

are in their required state for existing

unit conditions.

FREQUENCY

NOTE-----

Only required

when not

performed wi thi n

previous 92 days

SR 3.3.1.9

Perform COT.

Pri or to reactor

startup

AND

Four hours after

reducing power

below P-6 for

source range

instrumentation

AND

Twelve hours

after reducing

power below P-10

for power and

intermediate

range

instrumentation

AND

Once per 92 days

thereafter

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

1. Adjust NIS channel if absolute

difference

~ 3%.

2. Not required to be performed until

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after THERMAL POWER is

~ 50% RTP.

Compare results of the excore channels to

incore detector measurements.

92 EFPD

North Anna Units 1 and 2

3.3.1-10

Amendment 231/212

._- NUCLEAR DESIGN INFORMATION PORTAL--

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

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

This Surveillance shall include

verification that the time constants are

adjusted to the prescribed values.

Perform CHANNEL CALIBRATION.

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

Neutron detectors are excluded from CHANNEL

CALIBRATION.

Perform CHANNEL CALIBRATION.

SR 3.3.1.12

Perform CHANNEL CALIBRATION.

Perform COT.

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

Verification of setpoint is not required.

Perform TADOT.

SR 3.3.1.15

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

Verification of setpoint is not required.

Perform TADOT.

FREQUENCY

18 months

Prior to

exceeding the

P-8 interlock

whenever the

unit has been in

MODE 3. if not

performed wi thi n

the previous

31 days

North Anna Units 1 and 2

3.3.1-11

Amendment 231/212

.- NUCLEAR DESIGN INFORMATION PORTAL--

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE

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

Neutron detectors are excluded from

response time testing.

FREQUENCY

Verify RTS RESPONSE TIME is within limits.

18 months on a

STAGGERED TEST

BASIS

North Anna Units 1 and 2

3.3.1-12

Amendment 231/212

-- NUCLEAR DESIGN INFORMATION PORTAL-

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 1 of 5)

Reactor Trip System Instrumentation

FUNCTION

APPLICABLE MODES

OR OTHER

SPECIFIED

REQUIRED

SURVEILLANCE

CONDITIONS

CHANNELS

CONDITIONS

REQUIREMENTS

ALLOWABLE VALUE

1. Manual Reactor Trip

2. Power Range Neutron Flux

I, 2

3(a), 4(a), 5(a)

2

B

C

NA

a. High

b. Low

I, 2

4

D

E

S 110% RTP

SR 3.3.1.2

SR

3.3.1.3

S 26% RTP

SR 3.3.1.8

SR

3.3.1.11

3. Power Range Neutron Flux Rate

a. High Positive Rate

b. High Negative Rate

4. Intermediate Range Neutron Flux

5. Source Range Neutron Flux

I, 2

1(b),

2(c)

2(d)

4

2

E

F, G

H, I

SR

3.3.1.11

SR

3.3.1.8

SR

3.3.1.8

S 5.5% RTP

with time

constant

~ 2 sec

S 5.5% RTP

with time

constant

~ 2 sec

S 40% RTP

S 1. 3 E5 cps

NA

2

I, J

K

S 1.3 E5 cps

SR

3.3.1.11

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) Below the P-I0 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e) With the Rod Control System incapable of rod withdrawal. In this condition, source range Function does

not provide reactor trip but does provide indication.

North Anna Units 1 and 2

3.3.1-13

Amendment 231/212

...- NUCLEAR DESIGN INFORMATION PORTAL -

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 2 of 5)

Reactor Trip System Instrumentation

FUNCTION

6. Overtemperature

~T

7. Overpower

~T

8. Pressurizer Pressure

APPLICABLE MODES

OR OTHER

SPECIFIED

CONDITIONS

I, 2

REQUIRED

CHANNELS

3

SURVEILLANCE

CONDITIONS

REQUIREMENTS

E

SR

3.3.1.3

SR 3.3.1. 9

SR 3.3.1.12

E

SR

3.3.1. 7

SR 3.3.1.12

ALLOWABLE VALUE

Refer to

Note 1 (Page

3.3.1-16)

Refer to

Note 2 (Page

3.3.1-17)

a. Low

b. High

9. Pressurizer Water Level-High

10. Reactor Coolant Flow-Low

11. Reactor Coolant Pump (RCP)

Breaker Position

12. Undervoltage RCPs

13. Underfrequency RCPs

14. Steam Generator (SG) Water

Level-Low Low

I, 2

3

3 per

loop

1 per

RCP

1 per

bus

1 per

bus

3 per SG

L

E

L

M

L

E

~ 1860 psig

~ 2370 psig

SR

3.3.1.10

~ 93%

~ 89%

SR

3.3.1.10

NA

SR 3.3.1.6

~ 2870 V

SR 3.3. 1.6(g)

~ 56 Hz

~ 17%

(f)

Above the P-7 (Low Power Reactor Trips Block) interlock.

(g) Required to be performed for Unit 2 only.

North Anna Units 1 and 2

3.3.1-14

Amendment 231/212

-- NUCLEAR DESIGN INFORMAnON PORTAL-

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 3 of 5)

Reactor Trip System Instrumentation

APPLICABLE MODES

OR OTHER

SPECIFIED

REQUIRED

SURVEILLANCE

FUNCTION

CONDITIONS

CHANNELS

CONDITIONS

REQUIREMENTS

ALLOWABLE VALUE

15. S6 Water Level-Low

I, 2

2 per S6

E

~ 24%

SR

3.3.1.10

Coincident with Steam

I, 2

2 per S6

E

$ 42.5% full

Flow/Feedwater Flow Mismatch

steam flow at

RTP

16. Turbine Trip

a. Low Auto Stop Oil Pressure

1(h)

3

N

~ 40 psig

SR 3.3.1.15

b. Turbine Stop Valve Closure

1(h)

4

N

~ 0% open

SR 3.3.1.15

17. Safety Injection (SI) Input

I, 2

2 trains

0

NA

from Engineered Safety Feature

Actuation System (ESFAS)

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron

2(d)

2

Q

~ 3E-11 amp

Flux, P-6

b. Low Power Reactor Trips

1 per

R

SR 3.3.1.5

NA

Block, P-7

train

c. Power Range Neutron Flux,

4

R

$ 31% RTP

P-8

d. Power Range Neutron Flux,

I, 2

4

Q

~ 7% RTP

P-I0

$ 11% RTP

e. Turbine Impulse Pressure,

2

R

$ 11% turbi ne

P-13

power

19. Reactor Trip Breakers(i)

I, 2

2 trains

P

NA

3(a), 4(a), 5(a)

2 trains

C

NA

20. Reactor Trip Breaker

I, 2

1 each

S

NA

Undervoltage and Shunt Trip

per RTB

Mechanisms

3(a) * 4(a) , 5(a)

1 each

C

NA

per RTB

21. Automatic Trip Logic

I, 2

2 trains

0

SR 3.3.1.5

NA

3(a), 4(a) , 5(a)

2 trains

C

SR 3.3.1.5

NA

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(h) Above the P-8 (Power Range Neutron Flux) interlock.

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

North Anna Units 1 and 2

3.3.1-15

Amendment 231/212

-- NUCLEAR DESIGN INFORMATION PORTAL-

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 4 of 5)

Reactor Trip System Instrumentation

Note 1: Overtemperature

~T

The Overtemperature

~T Function Allowable Value shall not exceed the

following nominal trip setpoint by more than 2.0% of

~T span.

Where:

~T is measured RCS

~T, OF.

~To is the indicated

~T at RTP, OF.

s is the Laplace transform operator, sec-I.

T is the measured RCS average temperature, OF.

TI is the nominal Tavg at RTP, S [*]OF.

P is the measured pressurizer pressure, psig

pi is the nominal

RCS operating pressure,

~ [*] psig

KI S [*]

K2 ~ [*];oF

K3 ~ [*]/psig

'ti

~ [*] sec

't2 S [*] sec

f1 (~I) = [*] {[*]

-

(qt - qb)}

when qt - qb < [*] % RTP

0

when [*]% RTP S qt - qb S [*] % RTP

[*] {(qt - qb) - [*]}

when qt - qb > [*]% RTP

Where qt and qb are percent RTP in the upper and lower halves

of the core, respectively, and qt + qb is the total

THERMAL

POWER in percent RTP.

The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2

3.3.1-16

Amendment 245/226

._- NUCLEAR DESIGN INFORMATION PORTAL ---

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 5 of 5)

Reactor Trip System Instrumentation

Note 2: Overpower .1T

The Overpower .1T Function Allowable Value shall

not exceed the following

nominal trip setpoint by more than 2% of .1T span.

Where:

.1T is measured Res .1T, of .

.1To is the indicated .1T at RTP, OF.

s is the Laplace transform operator, sec-i.

T is the measured RCS average temperature, OF.

T

I is the nominal Tavg at RTP, S [*]OF.

K4 S [*]

Ks ~ [*] rF for increasing Tavg

[*] rF for decreasing Tavg

K6

~ [*]/oF when T > T

I

[*]/oF when T S T

I

The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2

3.3.1-17

Amendment 231/212

-. NUCLEAR DESIGN INFORMATION PORTAL -

Spent Fuel Pool Storage

3.7.18

4.6

4.2

3.8

3.4

3

2.6

2.2

1.8

/,

/

J

V

/ V

/

I

Acceptable

Conditionally 1/

Acceptable

/

/ /

I

/

I

Unacceptable I

I

/

V

/

V

/

o

1.4

5000

10000

15000

45000

40000

30000

35000

si

~!. 25000

Q.=

c:..=

aI

SE 20000

J

Gi=

~

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

3.7.18-3

Amendments 231/212

-

NUCLEAR DESIGN INFORMATION PORTAL-

Inverters-Operating

3.8.7

3.8

ELECTRICAL POWER SYSTEMS

3.8.7

Inverters-Operating

LCO 3.8.7

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.

APPLICABILITY:

MODES 1. 2. 3. and 4.

ACTIONS

CONDITION

REQUIRED ACTION

COMPLETION TIME

A.

One inverter

A.1

NOTE--------

Enter applicable

Conditions and

Required Actions of

LCO 3.8.9.

"Distribution

Systems-operating"

with any vital bus

de-energized.

Restore inverter 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 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 235/217

-- NUCLEAR DESIGN INfORMATION PORTAL-

Inverters-Operating

3.8.7

SURVEILLANCE REQUIREMENTS

SR 3.8.7.1

SURVEILLANCE

Verify correct inverter voltage and

alignment to required AC vital buses.

FREQUENCY

7 days

North Anna Units 1 and 2

3.8.7-2

Amendments 231/212

_. NUCLEAR DESIGN INFORMAnON POR fAL --

Distribution Systems-Operating

3.8.9

3.8

ELECTRICAL POWER SYSTEMS*

3.8.9

Distribution Systems-Operating

LCO 3.8.9

The following distribution subsystems shall be OPERABLE:

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

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

shared component.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS

CONDITION

A.

One or more

LCO 3.8.9.a AC

electrical power

distribution

subsystem(s)

North Anna Units 1 and 2

A.l

REQUIRED ACTION

NOTE--------

Enter applicable

Conditions and

Required Actions of

LCO 3.8.4, "DC

Sources-Operating, II

for DC train(s) made

inoperable by

inoperable

distribution

subsystem(s).

Restore AC electrical

power distribution

subsystem(s) to

OPERABLE status.

3.8.9-1

COMPLETION TIME

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

AND

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from

discovery of

fail ure to meet

LCO

Amendments 231/212

ACTIONS

-

NUCLEAR DESIGN INFOHMATION PORTAL-

Distribution Systems-Operating

3.8.9

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

fail ure 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

discovery of

fail ure to meet

LCO

D.

NOTE----------

D.1

Declare associated

Immediately

Separate Condition

shared component(s}

entry is allowed for

each AC subsystem.

One or more required

LCO 3.8.9.b AC

electrical power

distribution

subsystem(s}

E.

NOTE----------

E.1

Declare associated

Immediately

Separate Condition

shared component(s}

entry is allowed for

each DC subsystem.

One or more required

LCO 3.8.9.b DC

electrical power

distribution

subsystem(s}