Text

Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2
	ML20134J414
Person / Time
Site:	North Anna
Issue date:	02/04/1997
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
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ML20134J398	List: ML20134J396; ML20134J414;
References
	NUDOCS 9702120122
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-..-.

s R

j ATTACHMENT 1 4

i REVISED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGES INTERMEDIATE RANGE NEUTRON FLUX TRIP SETPOINTS AND ALLOWABLE VALUES NORTH ANNA POWER STATION UNITS 1 AND 2 l

DR DO 5

338 P

PDR I

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O lc TABLE 2.2-1 d

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REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 1.

Manual Reactor Trip Not Applicable Not Applicable

-c3 2.

Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - s 26% of RATED j

THERMAL POWER THERMAL POWER l

High Setpoint - 5109%** of RATED High Setpoint - $ 110%*** of RATED THERMAL POWER THERMAL POWER 3.

Power Range, Neutron Flux, s 5% of RATED THERMAL POWER

$ 5.5% of RATEDTHERMAL POWER liigh Positive Rate with a time constant 2 2 seconds with a time constant 2 2 seconds 4.

Power Range, Neutron Flux, s 5% of RATED THERMAL POV R

$ 5.5% of RATEDTHERMAL POWER High Negative Rate with a time constant 2 2 seconds with a time constant 2 2 seconds

{

5.

Intermediate Range, Neutron s 35% of RATED THERMAL POWER s 40% of RATED THERMAL POWER l

l 6

Flux 5

5 6.

Source Range, Neutron Flux s 10 counts per second s 1.3 x 10 counts per second

-l 7.

Overtemperature AT See Note i See Note 3 8.

Overpower AT See Note 2 See Note 3 F

9.

Pressurizer Pressure - Low 21870 psig 21860 psig l

>g 10.

Pressurizer Pressure - High 5 2360 psig s 2370 psig

{

a 11.

Pressurizer Water Level-High s 92% of instrument span s 93% ofinstmment span E,

12.

Loss of Flow 2 90% of design flow per loop

2 89% of design flow per loop

l Z

i 9

i 3

Design flow per loop is one-third of the minimum allowable Reactor Coolant System Total Flow Rate as specified in Table 3.2-1.

l g

The high trip setpoint for Power Range, Neutron Flux, shall be s 103% RATED THERMAL POWER for the period of operation i

j until steam generator replacement.

j

^

j3

- - The allowable value for the high trip setpoint for Power Range, Neutron Flux,is required to be s 104% RATED THERMAL f

POWER for the period of operation until steam generator replacement.

r i

t LIMITING SAFETY SYSTEM SETTINGS BASES The Power Range Negative Rate Trip provides protection for control rod drop accidents.

At high power, a rod drop accident could cause local flux peaking which could cause an unconservative local DNBR to exist. The Power Range Negative Rate Trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate Trip for those control rod drop accidents for which the DNBR's will be greater than the applicable design limit DNBR value for each fuel type.

Intermediate and Source Range. Nuclear Flux The Source Range Nuclear Flux trip provides reactor core protection during shutdown l

(Modes 3,4 and 5) when the reactor trip system breakers are in the closed position. The Source and Intermediate Range trips in addition to the Power Range trips provide core protection during reactor startup (Mode 2). Reactor startup is prohibited unless the Source, Intermediate and Power Range trips are operable in accordance with Specification 3.3.1.1. The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED TIIERMAL POWER unless manually l

blocked when P-10 becomes active. In the accident analyses, bounding transient results are based on reactivity excursions from an initially critical condition, where the source range trip is assumed to be blocked. Accidents initiated from a suberitical condition would produce less sewre results since the source range trip would provide core protection at a lower power level. No credit was taken for operation of the trip assoc 5ted with the Intermediate Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature AT The Overtemperature AT trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transient delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the liigh and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for piping delays from the core to the loop temperature detectors. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

NORTli ANNA - UNIT 1 B 2-4 Amendment No. 84, I

m._

l 2

O M

f TABLE 3.3-i-

>2 REACTOR TRIP SYSTEM INSTRUMENTATION 2

7 MINIMUM

~

c TOTAL NO.

CHANNELS CHANNELS APPLICABLE 3

FUNCTIONAL UNIT OF CIIANNELS TO TRIP OPERABLE MODES ACTION

-1

1. Manual ReactorTrip 2

1 2

1,2 and

12 e

2. Power Range, Neutron Flux 4

2 3

1, 2 2

h

3. Power Range, Neutron Flux 4

2 3

1, 2 2

Iligh Positive Rate

4. Power Range, Neutron Flux, 4

2 3

1, 2 2

W liigh Negative Rate i

ta r

h

5. Intermediate Range, Neutron Flux 2

1 2

l

,2 3

l l

6. Source Range, Neutron Flux t

A. Startup 2

1 2

2 4

B. Shutdown 2

1 2

3*,4* and 5*

15 i

C. Shutdown 2

0 1

3,4 and 5 5

t

7. Overtemperature AT E.

I Three Loop Operation 3

2 2

1, 2 7

L E

f Two Loop Operation 3

1**

2 1, 2 -

9

[

o t

ta C

'A' h

i

__._._._,___._._m_.._-__....__m.m_.__.__2.m.__.__-_

m mm.

mm--

m m

m

-.-.m*.

ew-

~.-c -mem e s---

..%-e=---e--

I TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

liigh voltage to detector may be de-energized above the P-6.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

l I

1 l

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement be in IIOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months however, one channel 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 per Specification 4.3.1.1.1 provided the other channel is operable.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

i The inoperable channel is placed in the tripped condition within I hour.

~

a.

b. The Minimum Channels OPERABLE requirement is met; however, the j

inoperable channel 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 of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either. TIIERMAL POWER is restricted to s 75% of R ATED T11ERM AL POWER and the Power Range, Neutron Flux trip setpoint is reduced to s 85% of RATED TIIERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; cr. the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be within

[

the limit when above 75 percent of RATED T11ERM AL POWER with one I

Power Range Channel inoperable by using the moveable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symrnetric thimble locations or a full-core flux map, is cerwistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the TilERMAL POWER level:

NORTli ANNA - UNIT I 3/43-5 Amendment No. M, c

(.

9 4

TABLE 3.3-1 (Continued) f Below P-6, restore the inoperable channel to OPERABLE status prior to a.

increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6 but below the P-10 setpoint, restore the inoperable channel to.

OPERABLE status prior to increasing THERMAL POWER above the P-10 setpoint.

c.

Above the P-10 setpoint, POWER OPERATION may continued.

ACTION 4 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

Below P-6, restore the inoperable channel to OPERABLE status prior to a.

increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6, operation may continue.

ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 -

Not applicable.

ACTION 7 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed until performance of the next required CIIANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 8 -

Not applicable.

l 1

NORTH ANNA - UNIT 1 3/4 3-6 Amendment No.

Z Oy TABLE 4.3-I f

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CIIANNEL MODES IN WHICH CHANNEL CIIANNEL FUNCTIONAL SURVEILLANCE b

FUNCTIONAL UNIT CIIECK CALIBRATION TEST REOUIRED Z

f7 R)

I,2 and *

]

1. Manual Reactor Trip N.A.

N.A.

2. Power Range, Neutron Flux S

D(2), g(3)

M 1, 2 and Q(6)

3. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 liigh Positive Rate t6 R)

M 1, 2 a

4. Power Range, Neutron Flux, N.A.

[

Iligh Negative Rate

5. Intermediate Range, Neutron Flux a.

S R(6.12)

M, S/U(3) 1***,2 b.

M(I 3)

N.A.

3*,4*,5*

6. Source Range, Neutron Flux N.A.

R(6)

M, S/U(I) 2,3,4 and 5

7. Overtemperature AT S

R(6)

M 1, 2

8. Overpower AT S

R(6)

M 1, 2

9. Pressurizer Pressure - Low S

R M

1, 2 kf

10. Pressurizer Pressure -liigh S

R M

1, 2 E

E I 1. Pressurizer Water Level-Iligh S

R M

1, 2 9

.I

12. Loss of Flow - Single Loop S

R M

I

.--. - ~

1 TABLE 4.3-1 (Continued)

NOTATION i

With the reactor trip system breakers closed and the control rod drive system 1

capable of rod withdrawal.

j Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

l 1

1 (1)-

If not performed in previous 7 days.

(2) -

Heat balance only, above 15% of RATED THERMAL POWER.

i j

(3) -

Compare incore to excore axial offset above 15% of RATED THERM AL POWER.

Adjust channel if absolute difference 2 3 percent.

(4) -

Manual ESF functional input check every 18 months.

]

(5) -

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

I 1

(6) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -

The CH ANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the manual reactor i

trip function. The test shall also verify the operability of the Bypass Breaker Trip circuit (s).

(8) -

Local manual shunt trip prior to placing the bypass breaker into service.

i l

(9) -

Automatic undervoltage trip.

1-3 (10)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of tne Reactor Trip i

Breakers.

i (11)-

Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(12)-

Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT I 3/4 3-14 Amendment No. 4,

_ - - =. -. ~ _

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

i

~

4 SPECIAL TEST EXCEPTIONS

~

PHYSICS TESTS 1

l LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4,3.1.3.1,3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERM AI. POWER, and I

c.

The reactor trip setpoints on the OPERABLE Power Range Channels are set at less than or equal to 25% of RATED THERMAL POWER.

APPLICABILITY:

MODE 2.

ACTION:

With the THERMAL POWER > 5% of RATED THERMAL POWER,immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be 5 59 of RATED THERMAL POWER at least once per hour during PHYS *CS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

NORTH ANNA - UNIT 1 3/4 10-3 Amendment No. M,

-._._....m_

1, s

j SPECIAL TEST EXCEPTIONS REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of startup and PIIYSICS TESTS provided:

The TilERMAL POWER does not exceed the P-7 Interlock Setpoint, a.

b.

The Reactor Trip Setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED T11ERMAL POWER, and The Reactor Trip Setpoints on the OPERABLE Power Range Channels are set at c.

less than or equal to 25% of RATED TIIERMAL POWER.

APPLICABILITY:

During operation below the P-7 Interlock Setpoint.

ACTION:

With the TilERM AL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The TliERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CilANNEL FUNCTION / ' TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup or PIIYSICS TESTS.

NORTIl ANNA - UNIT 1 3/4 10-4 Amendment No.

Z O

lz TABLE 2.2-I d

{

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES l.

Manual Reactor Trip Not Applicable Not Applicable CZ 2.

Power Range, Neutron Flux Low Setpoint - s 25% of RATED Low Setpoint - s 26% of RATED j

TIIERMAL POWER TIIERMAL POWER High Setpoint - s 109% of RATED Iligh Setpoint - s 110% of RATED -

TilERMAL POWER TilERMAL POWER 3.

Power Range, Neutron Flux, s 5% of RATED TiiERMAL POWER s 5.5% of RATEDTIIERMAL POWER Iligh Positive Rate with a time constant 2 2 seconds with a time constant 2 2 seconds -

4.

Power Range, Neutron Flux, s 5% of RATED TIIERMAL POWER s 5.5% of RATEDTilERMAL POWER Iligh Negative Rate with a time constant 2 2 seconds with a time constant 2 2 seconds 5.

Intermediate Range, Neutron s 35% of RATED T11ERMAL POWER s 40% of RATED TIIERMAL POWER l

g 6

Flux 4

5 5

6.

Source Range, Neutron Flux s 10 counts per second s 1.3 x 10 counts per second 7.

Overtemperature AT See Note 1 See Note 3 8.

Overpower AT See Note 2 See Note 3 9.

Pressurizer Pressure - Low 21870 psig 21860 psig 10.

Pressurizer Pressure -liigh s 2?60 psig s 2370 psig i 1.

Pressurizer Water Level-liigh s 92% ofinstrument span s 93% of instrument span 5

12.

Loss of Flow 2 90% of design flow per loop

2 89% of design flow per loop

E.

Ra y

Design flow per loop is one-third of the minimum allowable Reactor Coolant System Total Flow Rate as specified in Table 3.2-1.

?

LIMITING S AFETY SYSTEM SETTINGS BASES Intermediate and Source Range. Nuclear Flux The Source Range Nuclear Flux trip provides reactor core protection during shutdown l

(Modes 3,4, and 5) when the reactor trip system breakers are in the closed position. The Source and Intermediate Range trips in addition to the Power Range trips provide core protection during reactor startup (Mode 2). Reactor startup is prohibited unless the Source, Intermediate and Power Range trips are operable in accordance with Specification 3.3.1.1. The Source Range Channels will initiate a reactor trip at about 10+5 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range Channels will initiate a reactor trip at a current level proportional to approximately 35 percent of RATED THERMAL POWER unless manually l

blocked when P-10 becomes active. In the accident analyses, bounding transient results are based on reactivity excursions from an initially critical condition, where the source range trip is assumed to be blocked. Accidents initiated from a suberitical condition would produce less severe results since the source range trip would provide core protection at a lower power level. No credit was taken for operation of the trip associated with the Intermediate Range Channels in the accident analyses; however, their functional capability at the specified trip settings is required by this specification to enhance the overall reliability of the Reactor Protection System.

Overtemperature Delta T The Overtemperature Delta T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transient delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic compensation for piping delays from the core to the loop temperature detectors. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1.

Operation with a reactor coolant loop out of service below the 3 loop P-8 setpoint does not require reactor protection system setpoint modification because the P-8 setpoint and associated trip will prevent DNB during 2 loop operation exclusive of the Overtemperature Delta T setpoint. Two loop operation above the 3 loop P-8 setpoint is permissible after resetting the K, K and K inputs i

2 3

to the Overtemperature Delta T channels and raising the P-8 setpoint to its 2 loop value. In this mode of operation, the P-8 interlock and trip functions as a High Neutron Hux trip at the reduced power level.

NORTil ANNA - UNIT 2 B 2-4 Amendment No. 74,

4 2

O lc f

TABLE 3.3-1 3z REACTOR TRIP SYSTEM INSTRUMENTATION Z

7 MINIMUM C

TOTAL NO.

CIIANNELS CIIANNELS APPLICABLE FUNCTIONAL UNIT OF CIIANNELS TO TRIP OPERABLE MODES ACTION

1. Manual ReactorTrip 2

1 2

1,2 and

12

2. Power Range, Neutron Flux 4

2 3

1, 2 2

3. Power Range, Neutron Flux liigh 4

2 3

1, 2 2'

Positive Rate

4. Power Range, Neutron Flux, High 4

2 3

1, 2 2"

y Negative Rate

C#

5. Intermediate Range, Neutron Flux 2

1 2

l

,2 3

l

6. Source Range, Neutron Flux

[

t A. Startup 2

1 2

2"#

4 l

i B. Shutdown 2

1 2

3*,4* and 5*

15 C. Shutdown

'2 0

1 3,4 and 5 5

3. Overtemperature AT 3

B{

Three Loop Operation 3

2 2

1, 2 7'

E Two Loop Operation 3

1**

2 1, 2 9

%9

.M i

-m

. m

4, TABLE 3.3-l(CONTINUED)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above the P-6,(Block of Source Range Reactor Trip), setpoint.

Below the P-10 (Low Setpoint Powe Range Neutron Flux Interlock) Setpoint.

l ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel 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 per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition within I hour, a.

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel 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 of the redundant channel (s) per Specification 4.3.1.1.1.

c.

Either, THERM AL POWER is restricted to s 75% of RATED THERM AL t'OWER and the Power Range, Neutron Flux trip setpoint is reduced to ewe of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NORTH ANNA-UNIT 2 3/4 3-5 Amendment No. 69,

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

~

1 TABLE 3.3-1 (CONTINUED) l

{

ACTION 3 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the TilERMAL i

l POWER level:

)

i Below the P-6,(Block of Source Range Reactor Trip) setpoint, restore the a.

inoperable channel to OPERABLE status prior to increasing TIIERMAL l

POWER above the P-6 Setpoint.

j

b. Above,he P-6 (Block of Source Range Reactor Trip) setpoint, but below the j

P-10 setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERM AL POWER above the P-10 setpoint.

c. Above the P-10 setpoint, POWER OPERATION may continued.

ACTION 4 -

With the number of channels OPERABLE one less than required by the j

Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

Below P-6, (Block of Source Range Reactor Trip) setpoint, restore the a.

{

inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6, (Block of Source Range Reactor Trip) setpoint, operation may j

continue.

j ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the

)

i SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

[

ACTION 6-Not applicable.

j ACTION 7 -

- With the number of OPERABLE channels one less than the Total Number of l

Channels, STARTUP and POWER OPERATION may proceed until j

performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 8 -

Not applicable.

1 i

NORTH ANNA - UNIT 2 3/43-6 Amendment No.

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

I Z

O

[

c TABLE 4.31 H*

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS

^

'llANNEL MODES IN WillCH CllANNEL CIIANNEL FUNCTIONAL SURVEILLANCE b

FUNCTIONAL UNIT CllECK CALIBRATION TEST REOUIRED z9 1.

Manual Reactor Trip N.A.

N.A.

R(8)

I,2 and

a tJ

2. Power Range, Neutron Flux S

D(2) M(3)

M 1, 2 and Q(6)

3. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 liigh Positive Rate

4. Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 w

[

liigh Negative Rate

5. Intermediate Range, Neutron Flux a.

S R(6.13)

M, S/U(I)

!***,2 b.

M(12)

N.A.

3*,4*,5*

6. Source Range, Neutron Flux S(7)

R(6)

M, S/U(I) 2,3,4,5 and *

[

l

7. Overtemperature AT S

R(6)

M 1, 2 f

8. Overpower AT S

R(6)

M 1, 2

9. Pressurizer Pressure - Low S

R M

1, 2 S

4 9

g.

10 Pressurizer Pressure-Iligh S

R M

1, 2 L

8 i

E I 1. Pressurizer Water Level-liigh S

R M

1, 2

[

o

.E

12. Loss of Flow - Single Loop S

R M

i

[

TABLE 4.3-1(CONTINUED) i NOTATION 4

With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Surveillance requirements for the manual ESF functional test of the safety injection input to the reactor trip breakers is suspended for the duration of Cycle 9 operation.

i Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

[

(1)-

If not performed in previous 7 days.

(2) -

Heat talance only, above 15% of RATED THERM AL POWER. Adjust channel if absolute difference >2 percent.

(3) -

Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Recalibrate if absolute difference 2 3 percent.

(4) -

Manual ESF functional input check every 18 months.

(5) -

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST B ASIS.

(6) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -

Below the P-6, (Block of Source Range Reactor Trip) Setpoint.

(8)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(9) -

Local manual shunt trip prior to placing the bypass breaker into service.

(10) -

Automatic undervoltage trip.

(I1)-

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12)-

Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(13)-

Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 2 3/4 3-14 Amendment No. MO,

~

SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4,3.1.1.5,3.1.3.1,3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

2 J

The THERM AL POWER does not exceed 5% of RATED THERMAL POWER, a.

b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, l

The reactor trip setpoints on the OPERABLE Power Range Channels are set at less c.

j than or equal to 25% of RATED THERMAL POWER, and d.

The Reactor Coolant System lowest operating loop temperature (Tavg) is greater than or equal to 531 F.

APPLICABILITY: MODE 2.

I ACTION:

With the THERMAL POWER greater than 5% of RATED THERMAL POWER, a.

immediately open the reactor trip breakers.

b.

With a Reactor Coolant System operating loop temperature (Tavg)less than 531 F, restore T to within its limit within 15 minutes or be in at least HOT STANDBY 4

avg within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4

4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

i 4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating PHYSICS TESTS.

j 4.10.3.3 The Reactor Coolant System temperature (Tavg) shall be determined to be greater than or equal to 531 F at least once per 30 minutes during PHYSICS TESTS.

i U

NORTH ANNA - UNIT 2 3/4 10-3 Amentiment No.

SPECIAL TEST EXCEI'TIONS REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of startup and PHYSICS TESTS prouded:

The THERM AL POWER does not exceed the P-7 Interlock Setpoint, a.

b.

The reactor trip setpoints on the OPERABLE Intermediate Range Channels are set at less than or equal to 35% of RATED THERMAL POWER, and c.

The reactor trip setpoints on the OPERABLE Power Range Channels are set at less than or equal to 25% of RATED THERMAL POWER.

APPLICABILITY: During operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint,immediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERM AL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup or PHYSICS TESTS.

1 i

i NORTH ANNA - UNIT 2 3/4 10-4 Amendment No.

ML20134J414

Text

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