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

inoperable. train to OPERABLE

status.

-OR

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

- NUCLEI~R DESIGN INFORMA nON POR rAL--

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

C. (continued) C.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.

D. One Power Range ------------NOTE-------------

Neutron Flux-High 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 and

setpoint adjustment of other

channels.

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

to :::; 75% RTP.

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. Once per

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

0.3 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

North Anna Units 1 and 2 3.3.1-2 Amendment 231/212

- NUCLEAR DESIGN INFORMATION PORTAL-

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

E. One channel ------------NOTE-------------

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.

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

inoperable. 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

inoperable. 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.

-OR

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--

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

K. Required Source Range ------------NOTE-------------

Neutron Flux channel Plant temperature changes are

inoperable. 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-------------

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.

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.

-OR

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-

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

P. One RTB train ------------NOTES------------

inoperable. 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 hour

inoperable. 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

inoperable. 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.

-OR

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.

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

SR 3.3.1.2 -------------------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.

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

SURVEILLANCE FREQUENCY

SR 3.3.1. 3 -------------------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 31 effective

measurements to Nuclear Instrumentation full power days

System (NIS) AFD. Adjust NIS channel if (EFPD)

absolute difference is ~ 3%.

SR 3.3.1.4 -------------------NOTE--------------------

This Surveillance must be performed on the

reactor trip bypass breaker immediately

after placing the bypass breaker in

service.

Perform TADOT. 31 days on a

STAGGERED TEST

BASIS

SR 3.3.1. 5 Perform ACTUATION LOGIC TEST. 31 days on a

STAGGERED TEST

BASIS

SR 3.3.1.6 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 92 days

SR 3.3.1. 7 -------------------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. 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

SURVEILLANCE FREQUENCY

SR 3.3.1.8 -------------------NOTE-------------------- -----NOTE-----

This Surveillance shall include Only required

verification that interlocks P-6 and P-10 when not

are in their required state for existing performed wi thi n

unit conditions. previous 92 days

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

SR 3.3.1. 9 -------------------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 92 EFPD

incore detector measurements.

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 FREQUENCY

SR 3.3.1.10 -------------------NOTE--------------------

This Surveillance shall include

verification that the time constants are

adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.11 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL

CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.12 Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.13 Perform COT. 18 months

SR 3.3.1.14 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 18 months

SR 3.3.1.15 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 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 FREQUENCY

SR 3.3.1.16 -------------------NOTE--------------------

Neutron detectors are excluded from

response time testing.

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

APPLICABLE MODES

OR OTHER

SPECIFIED REQUIRED SURVEILLANCE

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

1. Manual Reactor Trip I, 2 2 B SR 3.3.1.14 NA

3(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA

2. Power Range Neutron Flux

a. High I, 2 4 D SR 3.3.1.1 S 110% RTP

SR 3.3.1.2

SR 3.3.1.3

b. Low 4 E SR 3.3.1.1 S 26% RTP

SR 3.3.1.8

3. Power Range Neutron Flux Rate

a. High Positive Rate I, 2 4 E SR 3.3.1.7 S 5.5% RTP

SR 3.3.1.11 with time

constant

~ 2 sec

b. High Negative Rate I, 2 4 E SR 3.3.1. 7 S 5.5% RTP

SR 3.3.1.11 with time

SR 3.3.1.16 constant

~ 2 sec

4. Intermediate Range Neutron Flux 1(b), 2(c) 2 F, G SR 3.3.1.1 S 40% RTP

SR 3.3.1.8

5. Source Range Neutron Flux 2(d) 2 H, I SR 3.3.1.1 S 1. 3 E5 cps

SR 3.3.1.8

2 I, J SR 3.3.1.1 S 1.3 E5 cps

K SR 3.3.1.1 NA

(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

APPLICABLE MODES

OR OTHER

SPECIFIED REQUIRED SURVEILLANCE

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

6. Overtemperature ~T I, 2 3 E SR 3.3.1.1 Refer to

SR 3.3.1.3 Note 1 (Page

SR 3.3.1. 7 3.3.1-16)

SR 3.3.1. 9

SR 3.3.1.12

7. Overpower ~T I, 2 3 E SR 3.3.1.1 Refer to

SR 3.3.1. 7 Note 2 (Page

SR 3.3.1.12 3.3.1-17)

8. Pressurizer Pressure

a. Low 3 L SR 3.3.1.1 ~ 1860 psig

b. High I, 2 3 E SR 3.3.1.1 ~ 2370 psig

SR 3.3.1.7

9. Pressurizer Water Level-High 3 L SR 3.3.1.1 ~ 93%

10. Reactor Coolant Flow-Low 3 per L SR 3.3.1.1 ~ 89%

loop SR 3.3.1. 7

11. Reactor Coolant Pump (RCP) 1 per M SR 3.3.1.14 NA

Breaker Position RCP

12. Undervoltage RCPs 1 per L SR 3.3.1.6 ~ 2870 V

bus SR 3.3.1.10

13. Underfrequency RCPs 1 per L SR 3.3. 1. 6 (g) ~ 56 Hz

bus SR 3.3.1.10

14. Steam Generator (SG) Water I, 2 3 per SG E SR 3.3.1.1 ~ 17%

Level-Low Low SR 3.3.1. 7

(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 INFORMA nON 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 SR 3.3.1.1 ~ 24%

SR 3.3.1.7

Coincident with Steam I, 2 2 per S6 E SR 3.3.1.1 $ 42.5% full

Flow/Feedwater Flow Mismatch SR 3.3.1.7 steam flow at

SR 3.3.1.10 RTP

16. Turbine Trip

a. Low Auto Stop Oil Pressure 1(h) 3 N SR 3.3.1.10 ~ 40 psig

SR 3.3.1.15

b. Turbine Stop Valve Closure 1(h) 4 N SR 3.3.1.10 ~ 0% open

SR 3.3.1.15

17. Safety Injection (SI) Input I, 2 2 trains 0 SR 3.3.1.14 NA

from Engineered Safety Feature

Actuation System (ESFAS)

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron 2(d) 2 Q SR 3.3.1.11 ~ 3E-11 amp

Flux, P-6 SR 3.3.1.13

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 SR 3.3.1.11 $ 31% RTP

P-8 SR 3.3.1.13

d. Power Range Neutron Flux, I, 2 4 Q SR 3.3.1.11 ~ 7% RTP

P-I0 SR 3.3.1.13 $ 11% RTP

e. Turbine Impulse Pressure, 2 R SR 3.3.1.10 $ 11% turbi ne

P-13 SR 3.3.1.13 power

19. Reactor Trip Breakers(i) I, 2 2 trains P SR 3.3.1.4 NA

3(a), 4(a), 5(a) 2 trains C SR 3.3.1.4 NA

20. Reactor Trip Breaker I, 2 1 each S SR 3.3.1.4 NA

Undervoltage and Shunt Trip per RTB

Mechanisms

3(a) * 4(a) , 5(a) 1 each C SR 3.3.1.4 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.

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

I

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

f 1 (~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 is the nominal Tavg at RTP, S [*]OF.

I

K4 S [*]

Ks ~ [*] rF for i ncreas i ng Tavg K6 ~ [*]/oF when T > TI

[*] rF for decreas i ng Tavg [*]/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

45000

40000 ,/

35000 /

30000 / J

s

i

~

!. 25000 V /

V

1//

Q.

.== I

/

c: Acceptable Conditionally

aI Acceptable

SE 20000

J /

Gi

~

=

15000 /I /

/

I Unacceptable I

10000 I /

V

5000

/ V

/

o

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 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--------

inoperable. 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

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 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 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.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more A.l ---------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, II

for DC train(s) made

inoperable by

inoperable

distribution

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

fail ure to meet

LCO

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

- NUCLEAR DESIGN INFOHMATION PORTAL-

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

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

inoperable. discovery of

fail ure 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}

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}