Text

Amends 81 & 69 to Licenses NPF-4 & NPF-7,respectively, Revising Tech Specs for Limiting Conditions for Operating & Surveillance Requirements for Reactor Trip Bypass Breakers & Undervoltage & Shunt Trip Logic
	ML20211G802
Person / Time
Site:	North Anna
Issue date:	06/09/1986
From:	Rubenstein L; Office of Nuclear Reactor Regulation
To:	;
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ML20211G789	List: ML20211G786; ML20211G802; ML20211G812;
References
	NUDOCS 8606200196
	Download: ML20211G802 (26)
	v • d • e

g UNITED STATES y

g NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C. 20555 9'g v 8

,o

....+

VIRGINIA ELECTRIC AND POWER COMPANY CLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNTT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-4 1.

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

A.

The applicaticn for amendment by Virginia Electric and Power Company, et al., (the licensee) dated April 12, 1985, as modified September 9, Eneroy Act of 1954, as amended (the Act)quirements of the Atomic 1985, complies wi.th the standards and re

, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be i'nimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l hDR606200196 8460609 ADOCK 05000338 p

PDR

{ 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Specifications er

'The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81,, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Q Mk 0

lLesterS.Rubenstein, Director 5I#l PWR Project Directorate #2 Division of PWR Licensing-A Att'chment:

a Changes to the Technical l

Specifications Date of Issuance: June 9, 1986 1

i

)

4

ATTACHMENT TO LICENSE AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Reolece the follnwing pages of the Appendix "A" Technical Specifications with 'te enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

l The corresponding overleaf pages are also provided to maintain document completeness.

Page 3/4 3-4 4

3/4 3-5 3/4 3-7

- ~

3/4 3-12 3-13 3/4 3-14 i

i i

1 i

i

)

i

l TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION 4

I MINIMUM 3;

TOTAL NO.

CHANNELS CHANNELS APPLICABLE 5

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES __

ACTION b

8.

Overpower AT Three Loop Operation 3

2 2

1, 2 2,

]

Two Loop Operation 3

1**

2 1, 2 9

9.

Pressurizer Pressure-Low 3

2 2

1, 2 7

10. Pressurizer Pressure--High 3

2 2

1, 2

'7

11. Pressurizer Water Level--High 3

2 2

1, 2 7

12. Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7 (Above P-8) any oper-each oper-w2 ating loop ating loop

13. Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1

7 #

(Above P-7 and below P-8) two oper-each oper-ating loops ating loop 14.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1, 2 7

Level--Low-Low any oper-each oper-ating loops ating loop

15. Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop 1, 2 7

Mismatch and Low Steam and coincident level and Generator Water Level 2/ loop-flow with 2/ loop-flow

?!

mismatch 1/ loop-flow mismatch or mismatch in 2/ loop-level same loop and 1/ loop-flow J mismatch

TABLE 3.3-1 (Continued)'

REACTOR TRIP SYSTEM INSTRUMENTATION 5

MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5

16. Undervol tage-Reactor 3-1/ bus 2

2 1

7#

Coolant Pump Busses C5

17. Underfrequency-Reactor 3-1/ bus 2

2 1

7#

]

Coolant Pump Busses

18. Turbine Trip A.

Low Auto Stop 011 Pressure 3

2 2

1 7#

B.

Turbine Stop Valve Closure 4

4 4

1 7#

19. Safety Injection Input from ESF 2

1 2

1,2 1

w

20. Reactor Coolant Pump Breaker 1

Position Trip w

A.

Above P-8 1/ breaker 1

1/ breaker 1

10 1.

B.

Above P-7 1/ breaker 2

1/ breaker 1

11 per operating loop 21.

A.

Reactor Trip Breakers 2

1 2

1,2 1,14 2

1 2

3*,4*,5*

15 B.

Reactor Trip Bypass Breakers 2

1 2

13 2-

22. Automatic Trip Logic ^

2 1

2 1,2 1

2 1

2 3*,4*,5*

15 g.

$n g

6 e

TABLE 3.3-1 (Continued)

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

snThe channel (s) associated with the pr;tective functions derived from the out of service Reactor Coolant Loop Dril 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.

1. High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS With the number of channels OPERABLE one less than re-ACTION 1

~ ~

required by the Minimum Channels OPERABLE requirement, 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.

l With the number of OPERABLE channels one less than the ACTION 2 Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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, THERMAL POWER is restricted to s 75% of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% 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 move-able 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 date per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the number of channels OPERABLE one less than re-ACTION 3 required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

NOP.TH ANNA - UNIT 1 3/4 3-5 Amendment No. 35, 31

TABLE 3.3-1 (Continued) a.

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

b.

Above P-6 but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 -

With the number of channels OPERABLE one less thar, re-quired by the Minimum Channels GPERABLE requirement and with the THERMAL POWER level:

a.

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

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 CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

~

ACTION 8 -

Not applicable NORTH ANNA-UNIT 1 3/4 3-6

TABLE 3.3-1 (Continued)

ACTION 9 -

With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop 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.

ACTION 10 -

With one channel inoperable, restore the inoperable

(

channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below P-8 may continue pursuant to ACTION 11.

ACTION 11 -

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channels OPERABLE one less than re-

~

quired by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 13 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 -

With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1.

Th'e breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

NORTH ANNA - UNIT 1 3/4 3-7 Amendment No. 31

I I

TABLE 3.3-1 (Continued) 2 ToM REACTOR TRIP SYSTEM INTERLOCKS ALLOWABLE P

DESIGNATION CONDITION SETPOINT VALUES FUNCTION

-10

-10 P-6 1 of 2 Intermediate range 1 x 10

< 3 x 10 Allows manual block of above setpoint (increasing source range reactor trip m

powerlevel)

-II

-II 2 of 2 Intermediate range 5 x 10

> 3 x 10 Defeats the block of source below setpoint (decreasing range reactor trip powerlevel)

P-10 2 of 4 Power range above set-10%

<11%

Allows manual block of power t'

point (increasing power level) range (low setpoint) and inter-mediate range reactor trips and Y

intermediate range rod stop.

Blocks source range reactor trip.

3 of 4 Power range below set-8%

>7%

Defeats the block of power point (decreasing power level) range (low setpoint) and inter-mediate range reactor trips and intermediate range rod stop.

R Input to P-7.

R R

P-7 2 of 4 Power range above set-10%

<11%

Allows reactor trip on: Low point flow or reactor coolant pump 2

P or breakers open in more than one 1 of 2 Turbine Impulse Pressure equiv-

<11%

loop, Undervoltage -(RCP busses) chamber pressure above alent to 10%

Underfrequency (RCP busses),

setpoint rated turbine Turbine Trip, Pressurizer low power pressure, and Pressurizer high level.

(Power level increasing) e in 4

.g

t TABLE 3.3-2 (Continued) y REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES M

i

$E FUNCTIONAL UNIT RESPONSE TIME E

i 12.

Loss of Flow - Single Loop g

(Above P-8) 1 1.0 seconds M

13. Loss of Flow - Two Loops (Above P-7 and below P-8) 1 1.0 seconds

14. Steam Generator Water Level--Low-Low 1 2.0 seconds i

15. Steam /Feedwater Flow Mismatch and Low Steam Generator Water level '

NOT APPLICABLE

16. Undervoltage-Reactor Coolant Pump Busses 1 1.2 seconds

17. Underfrequency-Reactor Coolant Pump Busses 1 0.6 seconds us'

18. Turbine Trip A.

Low Fluid Oil Pressure NOT APPLICABLE B.

Turbine Stop Valve NOT APPLICABLE 1

19. Safety Injection Input from ESF NOT APPLICABLE

20. Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE l

TABLE 4.3-1

--g REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREPENTS

>z CHANNEL MODES IN WHICH 5

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED i

1.

Manual Reactor Trip N.A.

N.A.

R(7) 1,2 and

l 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 High Positive Rate 4.

Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 High Negative Rate 5.

Intermediate Range, S

R(6)

S/U(l) 1, 2 and

y Neutron Flux 6.

Source Range, Neutron Flux N.A.

R(6)

M,S/U(1) 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 o

10.

Pressurizer Pressure--High S

R M

1, 2 e

y

11. Pressurizer Water Level--High S

R M

1, 2

12. Loss of Flow - Single Loop S

R M

1

TABLE 4.3-1(Continueh)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

~

CHANNEL MODES IN WHICH Es 55 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED E

ji 13.

Loss of Flow - Two Loops S

R N.A.

1 b

14. Steam Generator Water Level--

S R

M 1,2 5

Low-Low

-4

15. Steam /Feedwater Flow Mismatch S

R M

1,2 and Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant N.A.

R N.A.

1 Pump Busses

17. Underfrequency - Reactor Coolant N.A.

R N.A.

1 5d Pump Busses Y

18. Terbine Trip EI A.

Low Auto Stop Oil Pressure N.A.

N.A.

S/U(1) 1,2 B.

Turbine Stop '?.ive Closure N.A.

N.A.

S/U(1) 1,2

19. Safety Injection Input from ESF N.A.

N.A.

M(4) 1,2

20. Re' actor Coolant Pump Breaker N.A.

N.A.

R N.A.

Position Trip 21.

A.

Reactor Trip Breaker N.A.

N.A.

M(5),(8) and (10) 1,2 and

El B.

Reactor Trip Bypass Breaker N.A.

N.A.

M(5),(8) and R(9) 1,2 and

R 5

22. Automatic Trip Logic N.A.

N.A.

M(5) 1,2 and

g-w.

o

.g*

s

TABLE 4.3-1 (Continued)

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

If not performed in previous 7 days.

(1)

(2)

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

(3) -

Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Adjust channel if absolute difference > 3 percent.

Manual ESF functional input check every 18 months.

(4)

Each train or logic channel shall be tested at least every l

(5) 62 days on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(6)

The CHANNEL FUNCTIONAL TEST shall independently verify the (7)

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).

(8)

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

(9)

Automatic undervoltage trip.

(10) -

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

/

I NORTH ANNA - UNIT 1 3/4 3-14 Amendment No. 31 l

i

.o E#

UNITED STATES 8 4^

NUCLEAR REGULATORY COMMISSION

, g.,

,3 5g'

/. y WASHINGTON,0. C. 20555

% -:~nvr ne e VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACTLITY OPERATING LICENSE

~

Amendment No. 69 License No. NPF-7

't 1.

The Nuclear Regulatnry Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated April IP,1985, as modified September 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance lii that the activities authorized by this amendment can be conducted without endancerina the health and safety of the public, and (ii) that such activities will be conducted in comoliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the conmon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

. 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

~ ~

s Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: June 9,1986

~

t e

ATTACHMENT TO LICENSE AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET N0. 50-339 Peplace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document comple teness.

Page l

3/4 3-4 i

3/4 3-5 3/4 3-7

~ ~

3/4 3-12 3/4 3-13 l

3/4 3-14 l

.~

I IABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRtlMENTATION p

MINIMilM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERARE MODES ACTION 8.

Overpower AT g

Three Loop Operation 3

2 2

1, 2 7

H Two Loop Operation 3

1**

2 1, 2 9

m 9.

Pressurizer Pressure-Low 3

2 2

1, 2 7

10.

Pressurizer Pressure--High 3

2 2

1, 2 7

11.

Pressurizer Water Level--High 3

2 2

1, 2

/

12.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7 (Above P-8) any oper-each oper-w ating loop ating loop w

E 13.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1

7 (Above P-7 and below P-8) two oper-each oper-ating loops ating loop 14.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1, 2 7

Level--Low-Low any oper-each oper-ating loops ating loop 15.

Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop 1, 2 7

Mismatch and Low Steam and coincident level and

. Generator Water Level 2/ loop-flow with 2/ loop-flow mismatch 1/ loop-flow mismatch or mismatch in 2/ loop-level

.~

same loop and 1/ loop-flow mismatch e

r4

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION

$5 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE e

g FUNCTIONAL UNIT OF CHANNELS TO TRIP GPERABLE MODES ACTION

[

16. Undervoltage-Reactor Coolant y

Pump Busses 3-1/ bus 2

2 1

7 17.

Underfrequency-Reactor Coolant 3-1/ bus 2

2 1

7 Pump Busses

18. Turbine Trip 7,,

A.

Low Auto Stop 011 Pressure 3

2 2

1 B.

Turbine Stop Valve Closure 4

4 4

1 7

w1 19.

Safety Injection Input w

from ESF 2

1 2

1, 2 1

s 20.

Reactor Coolant Pump Breaker Position Trip 1

A.

Above P-8 1/ breaker 1

1/ breaker 1

10 B.

Above P-7 1/ breaker 2

1/ breaker 1

11 per oper-ating loop 21.

A.

Reactor Trip Breakers 2

1 2

1, 2 1,14 2

1 2

3*,4*,5*

15 B.

Reactor Trip Bypass Breakers 2

1 2

13 E

R 22.*

Automatic Trip Logic 2

1 2

1,2

- "I a

2 1

2 3*,4*,5*

15 5

.?

l TABEL 3.3-1 (Continued)

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

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

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

s,

Tr.: 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.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPERABLE requirement, 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:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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, THERMAL POWER is restricted to s 75% of RATED THERMAL l

and the Power Range, Neutron Flux trip setpoint is reduced to s 85% 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 moveablo incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thible 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. 75, 69

TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6, (Block of Source Range Reactor Trip) set-point, restore the inoperable channel to OPERABLE status c

prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6, (Block of Source Range Reactor Trip) s'et-point, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6, (Block of Source Range Reactor Trip) set-point, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above the P-6, (Block of Source Range Reactor Trip) set-point, 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 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.

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 CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 8 Not applicable.

i I

i NORTH ANNA - UNIT 2 3/4 3-6

TABLE 3.3-1 (Continued)

With a channel associated with.an operating loop inoperable, ACTION 9 restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop 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.

ACTI0ii 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue pursuant to ACTION 11.

ACTION 11 - With less than the liinimum Number of Channels OPERABLE, operation

~.

may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 13 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

~

j l

NORTH ANNA - UNIT 2 3/4 3-7 Amendment No.69 i

i TA!!LE 3.3-1 (ContinJed)

.h REACT 0:1 TRIP SiSTEM INTERLOCKS nli A.LLOWABLE 3"

DESIGNATION CONDITION SETPOINT VALUES FUNCTION

-10

-10 P-6 1 of-2 Intermediate range 1 x 10

< 3 x 10 Allows manual block of above setpoint (increasing source range reactor trip m

power level)

-II

-II 2 of 2 Intermediate range 5 x 10

> 3 x 10 Defeats the block of source below setpoint (decreasin'g range reactor trip power level)

P-10 2 of 4 Power range above set-10%

<l1%

Allows manual block of power t'

point (increasing power level) range (low setpoint) and inter-mediate range reactor trips and s Y

intermediate range rod stop...

Blocks source range reactor trip.

3 of 4 Power range below set-8%

>7%

Defeats the block of power point (decreasing power level) range (low setpoint) and inter-mediate range reactor trips and intermediate range rod stop.

g m

i Input to P-7.

N3 P-7 2 of 4 Power range above set-10%

<l1%

Allows reactor trip on: Low point flow or reactor coolant pump

=

P or breakers open in more than one 1 of 2 Turbine Impulse Pressure equiv-

<ll%

loop, Undervoltage-(RCP busses) chamber pressure above alent to 10%

Underfrequency (RCP busses),

setpoint rated turbine Turbine Trip, Pressurizer low power pressure, and Pressurizer high levbl'.

(Power level increasing)

=f

~

+

- ~ - - -,

--,e, r--

I TABLE 3.3-2 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME 12.

Loss of Flow - Single Loop E

(Above P-8) 1 1.0 seconds

.-e N>

13.

Loss of Flow - Two Loops (Above P-7 and below P-8) 1 1.0 seconds 14.

Steam Generator Water Level--Low-Low i 2.0 seconds 15.

Steam /Feedwater Flow Mismatch and Low Steam Generator Water Level NOT APPLICABLE 16.

Undervoltage-Reactor Coolant Pump Busses i 1.2 seconds 17.

Underfrequency-Reactor Coolant Pump Busses 1 0.6 seconds ca 3:

18. Turbine Trip l

A.

Low Fluid Oil Pressure NOT APPLICABLE B.

Turbine Stop Valve NOT APPLICABLE 19.

Safety Injection Input from ESF NOT APPLICABLE 20.

Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE 21.

Reactor Trip Breakers NOT APPLICABLE 22.

Automatic Trip Logic NOT APPLICABLE 4

e

t'.

E.

TABIE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION slRVEILLANCE REQUIREMENTS, L

5 CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE c

h FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.

Manual Reactor Trip N.A.

N.A.

R(8) 1,2 and

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 High Positive Rate

,s

[

4.

Power Range, Neutron Flux, N.A.

R(6)

M 1, 2 L

High Negative Rate n

5.

Intermediate Range, S

R(6)

S/U(1) 1, 2, and

Neutron Flux 6.

Source Range, Neutron Flux S(7)

R(6)

M,S/U(1) 2, 3, 4, 5, and

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 I

5 10.[PressurizerPressure--High 5

R M

1, 2 11.

Pressurizer Water Level--High S

R H

1, 2 12.

Loss of Flow - Single Loop S

R M

j1 s

gj TABLE _4.3-1fContinued)

M REACTOR TRIP SYSTEM INSTRUMENTATION :r RVEILLANCE REQUIREMENTS 5

c:

CHANNEL MODES IN WHICH 55 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

-4 FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED to 13.

Loss of Flow - Two Loops S

R N.A.

1 14.

Steam Generator Water Level--

S R

H 1, 2 Low-Low 15.

Steam /Feedwater Flow Mismatch and S

R M

1, 2 Low Steam Generator Water Level 3g 16.

Undervoltage - Reactor Coolant N.A.

R H

1 Pump Busses w

{;

17.

Underfrequency - Reactor Coolant N.A.

R M

1 Pump Busses 18.

Turbine Trip A.

Low Auto Stop Oil Pressure N.A.

N.A.

S/U(1)

N.A.

B.

Turbine Stop Valve Closure N.A.

N.A.

S/U(1)

N.A.

19.

Safety Injection Input from ESF N.A.

N.A.

M(4) 1, 2 27 20.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

g Position Trip I

ct g

21.

A'. Reactor Trip Breaker N.A.

N.A.

M(S) (9)&

1, 2, and * '

M(5),,(9) (11)

B.

Reactor Trip Bypass Breaker N.A.

N.A.

1,2, and

g and R(10)

22. Automatic Trip I.ogic N.A.

N.A.

M(5) 1,2, and

m m.

m

TABLE 4.3-1 (Continued)

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

If not performed in previous 7 days.

(1)

Heat balance only, above 15% of RATED THERMAL POWER. Adjust (2) channel if absolute difference >2 percent.

Compare incore to excore axial offset above 15% of RATED THERMAL (3)

POWER. Recalibrate if absolute difference >3 percent.

Manual ESF functional input check every 18 months.

(4)

Each train or logic channel shall be tested at least every 62 days (5) on a STAGGERED TEST BASIS, (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 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.

(11) -

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

NORTH ANNA - UNIT 2 3/4 3-14 Amendment Nr. 69

ML20211G802

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