Text

Amends 67 & 46 to Licenses NPF-68 & NPF-81,respectively, Modifying TSs 3/4.3.1 & 3/4.3.2 & Associated Bases to Relax Surveillance Test Intervals & Allowed Times Based on Westinghouse TR WCAP-10271
	ML20058N011
Person / Time
Site:	Vogtle
Issue date:	09/30/1993
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	; Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20058N015	List: ML20058N011; ML20058N022;
References
	NPF-68-A-067, NPF-81-A-046 NUDOCS 9310070283
	Download: ML20058N011 (38)
	v • d • e

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UNITED STATES dj NUCLEAR REGULATORY COMMISSION g4

,/

WASHINGTON, D.C. 20555-0001 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA I

CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-68 i

1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated March 1,1993, as supplemented July 26 and August 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical 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.

9310070283 930930 PDR ADOCK 05000424 P

PDR

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through l

Amendment No.

67, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W N ~ ^I-it w

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes l

Date of Issuance:

September 30, 1993 h

[p nec - t 2

(

E UNITED STATES 4

'E NUCLEAR REGULATORY COMMISSION

,/

$g WASHINGTON, D.C. 20555-0001 s

....+

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-81 1.

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

A.

The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated March 1,1993, as supplemented July 26 and August 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; j

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i

Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I, i

D.

The issuance of this amendment will not be inimical to the comon 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.

1 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

[4252. A/. I h

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

September 30, 1993 t

4

ATTACHMENT T0 LICENSE AMENDMENT NO. 67 l

FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 E

i TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Paoes Insert Paces f

3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 i

3/4 3-14 3/4 3-14 3/4 3-17 3/4 3-17 1

3/4 3-20 3/4 3-20 3/4 3-23 3/4 3-23 i

3/4 3-25 3/4 3-25 j

3/4 3-26 3/4 3-26 i

3/4 3-27 3/4 3-27 3/4 3-27a 3/4 3-27a 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-46 3/4 3-46 3/4 3-47 3/4 3-47 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 B 3/4 3-1 B 3/4 3-1 i

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION y

OO MINIMUM E

TOTAL NO.

CHANNELS CHANNELS APPLICABLE g

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop l'

6 below P-8) two oper-each oper-i ating loops ating loop (LOOP 1 LOOP 2 LOOP 3 LOOP 4 FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 rI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446) 13.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 6'

Level--Low-Low

in any oper-each oper-ating stm.

ating stm.

gen.

R (LOOP 1 LOOP 2 LOOP 3 LOOP 4 FI-0517 FI-0527 FI-0537 FI-0547 i'

FI-0518 FI-0528 FI-0539 FI-0549 FI-0551 FI-0552 FI-0553 FI-0554) 14.

Undervoltage--Reactor Coolant Pumps 4-2/ bus 2'

3 l'

9 l

b FF gg 15.

Underfrequency--Reactor Coolant g&

Pumps 4-2/ bus 2'

3 l'

9 6

t 88 16.

Turbine Trip gy a.

Low Fluid Oil Pressure 3

2 2

l' 6

(PT-6161, PT-6162, PT-6163) gg b~

Turbine Stop Valve Closure 4

4 1

l'

-12 17.

Safety Injection Input gg from ESF 2

1 2

1, 2 7

l bb l

NW vv l

l-

See Specification 3.3.3.6 l

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION a:

MINIMUM 8

TOTAL NO.

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

18.

Reactor Trip System Interlocks a.

Intermediate Range 7

Neutron Flux, P-6 2

1 2

2

'8 (NI-00358,D&E,NI-0036B,0&G) b.

Power Range Neutron Flux, P-8 4

2 3

1

-8 (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) c.

Power Range Neutron 4

2 3

1 8

Flux, P-9 (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) d.

Power Range Neutron

'r' Flux, P-10 4

2 3

1, 2 8-(NI-0041B&C, NI-0042B&C, NI-0043B&C,NI-0044B&C) e.

Turbine Impulse Chamber

m >

Pressure, P-13 2

1 2

1 8

ll (PI-0505, PI-0506) aa55 19.

Reactor Trip Breakers 2

1 2

1, 2 10, 13 55 2

1 2

3*, 4*,

5*

11 zz

??

20.

Automatic Trip and Interlock 2-1 2

1, 2 7

l Logic 2

1 2

3*, 4*,

5*

11 m

my CC 1R r eo UU 1-

....~..-..;.-..,_.__.

.c.m..,.

J.,

Y!

TABLE 3.3-1 (Continued)

TABLE NOTATIONS a When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

b (Deleted) c Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

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

e Above the P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.

f Above the P-7 (Low Power Reactor Trip Block) Setpoint.

g Not used.

h Above the P-8 (Single Loop Loss of Flow) Setpoint.

4 i Trip logic consists of undervoltage/underfrequency for Reactor Coolant Pumps 1 or 2 and 3 or 4.

j The Source Range High Flux at Shutdown Alarm may be blocked during reactor startup in accordance with approved procedures.

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

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

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

b.

The Minimum Channels OPERABLE requirement is met; however, a channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for i

surveillance testing per Specification 4.3.1.1, and c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 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 per Specification 4.2.4.2.

V0GTLE UNITS - 1 & 2 3/4 3-6 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

i TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

)

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

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

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

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

~

ACTION 5 - a.

With the number of OPERABLE channels one less than 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 System breakers, suspend all operations involving positive reactivity changes and verify valves 1208-U4-175, 1208-U4-177, 1208-U4-183, and 1208-U4-176 are closed and secured in position within the hour.

b.

With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes, i

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

Verify valves 1208-U4-175, 1208-U4-177, 1208-U4-183, and 1208-04-176 are closed and secured in position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured in position every 14 days.

ACTION 6 - With the number of OPERABLE channels one liss than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the 4

following conditions are satisfied:

i a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, a channel 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 per Specification 4.3.1.1.

ACTION 7 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least H0T STANDBY within the next 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.7.1, provided the other channel is operable.

V0GTLE UNITS - 1 & 2 3/4 3-7 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

i f

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied-a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel 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 of other channels per Specification 4.3.1.1.

ACTION 10 - With the number of OPERABLE channels one less than the Minimum i

Channels OPERABLE requirement, be in at least H0T 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, provided the other channel is OPERABLE.

ACTION 11 - With the number of OPERABLE channels one less than 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 System breakers within the next hour.

1 ACTION 12 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels l

are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 13 - With one of the diverse trip features (undervoltage or shunt.

trip attachment) 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 10.

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.

'V0GTLE UNITS - 1 & 2 3/4 3-8 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

TABLE 4.3-1 8

S REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMEWTS E

TRIP e

25 ANALOG ACTUATING MODES FOR d

CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANC FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGI TEST IS REQUIRED

[

1.

Manual Reactor Trip N. A.'

N.A.

R(14)

N.A.

1, 2, 3',4',

5' 2.

Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) a.

High Setpoint S

D(2,4),

Q N.A.

N.A.

'I, 2' l

f M(3, 4),

Q(4, 6),

R R(4, 5)

[

b.

Low Setpoint S

R(4)

S/U(1)

N.A.

I ', 2' l

d 3.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

l',

2' l

High Positive Rate (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C)

EN gg 4.

(Deleted)

??

5.

Intermediate Range, S

R(4, 5)

S/U(1)

N.A.

I ', 2' l

d Neutron Flux gg (NI-00358,0&E, NI-0036B,D&G) 2' ',3',4',5'l S$

6.

Source Range, Neutron Flux S

R(4, 5)

S/U(1),Q(9)

N.A.

(NI-00318,D&E, gg NI-00328,D&G) oo NN 7.

Overtemperature AT S

R(12)

Q N.A.

N.A.

I',

2' (TDI-0411C, TDI-0421C, TDI-0431C, TDI-0441C)

A

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP g

ANALOG ACTUATING MODES FOR q

CHANNEL DEVICE WHICH m

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED 8.

Overpower aT S

R Q

N.A.

I', 2' l

(TDI-0411B, TDI-04218, N

TDI-0431B. TDI-04418) 9.

Pressurizer Pressure--Low S

R Q

N.A.

l' '

(PI-0455A,B&C, PI-0456 &

PI-0456A, PI-0457 &

PI-0457A, PI-0458 &

PI-0458A) 10.

Pressurizer Pressure--High S

R Q

N.A.

l',~2'

.l y

(PI-0455A,B&C, PI-0456

& PI-0456A, PI-0457

~

& PI-0457A, PI-0458

& PI-0458A) 11.

Pressurizer Water Level--

S R

Q N.A.

N.A.

l' '

%gg High*

g&

(LI-0459A, LI-0460A, gg LI-0461A) oo

((

12. Reactor Coolant Flow--Low S

R Q

N.A.

1* '

??

(LOOP 1 LOOP 2 LOOP 3 LOOP 4

$;O FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446)

__??

3

See Specification 4.3.3.6 m-6

..~-.. -...

.. ~,. _. -..,

~.

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS

[

TRIP E

ANALOG ACTUATING MODES FOR Z

CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE.

1 FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED

[

13.

Steam Generator Water Level--

S R

Q N.A.

N.A.

I',

2' l

Low-Low *

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554)

14. Undervoltage - Reactor Coolant N.A.

R N.A.

Q N.A.

- l' l

Pumps m

15. Underfrequency - Reactor N.A.

R N.A.

Q N.A.

l'

'l Coolant Pumps

16. Turbine Trip I'

l.

b yp a.

Low Fluid Oil Pressure N.A.

R S/U(1, 10)

N.A.

Jg (PT-6161, PT-6162, PT-6163) gg b.

Turbine Stop Valve Closure N.A.

R N.A.

S/U(1,10)

N.A.

Ib me AE

17. Safety Injection Input from N.A.

N.A.

R N.A.

1, 2 -

gg ESF

18. Reactor Trip System Interlocks

,e a.

Intermediate Range Neutron Flux, P-6 N.A.

R(4)

R N.A.

N.A.

2' '

l' gg (NI-00358,D&E, 3, 3.

NI-0036B,D&G) eo 00

See Specification 4.3.3.6

8 TABLE 4.3-1 (Continued)

S REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS I;

e TRIP

i ANALOG ACTUATING MODES FOR d

CHANNEL DEVICE WHICH i

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED 18.

Reactor Trip System Interlocks (Continued) b.

Power Range Neutron l

Flux, P-8 N.A.

R(4)

R N.A.

N.A.

l' (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) c.

Power Range Neutron

-l Flux, P-9 N.A.

R(4)

R N.A.

N.A.

l' M

(NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-00448&C)

Y d.

Power Range M

Neutron Flux, P-10 N.A.

R(4)

R N.A.

H.A.

l',

2' e.

Turbine Impulse Chamber Pressure, P-13 N.A.

R R

N.A.

l' (PI-0505, PI-0506) k k 19.

Reactor Trip Breaker N.A.

N.A.

M(7, 11)

N.A.

1, 2, 3a,-

gg 4a, Sa aa k k

20. Automatic Trip and Interlock N.A.

N.A.

M(7) 1, 2, 3a, Logic 4a, 5a mm OO 21.

Reactor Trip Bypass Breaker N.A.

N.A.

M(15),R(16)

N.A.

1, 2, 3a, 4a, Sa mN EE bb SC

h, 3_

TABLE 4.3-1 (Continued)

TABLE NOTATIONS When the Reactor Trip System breakers are closed and the Control Rod Drive a

System is capable of rod withdrawal.

b Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint, Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

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

Above P-7 (Low Power Reactor Trip Block) Setpoint.

e f This function may be bypar, sed for surveillance testing provided that the applicable Action Statement requirements are met.

(1)

If not performed in previous 31 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

(3)

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

For the purpose of this surveillance requirement, monthly shall mean at least once per 31 EFPD.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

Detector plateau curves shall be obtained, and evaluated.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER. This is the determination of the response of the excore power range detectors to the incore measured axial power distribution to generate setpoints for the CHANNEL CALIBRATION.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

For the purpose of this surveillance requirement, quarterly shall mean at least once per 92 EFPD.

(7)

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

(8)

Not used.

(9)

Quarterly surveillance in MODES 3a, 4a, and Sa shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive window. Quar-terly surveillance shall include verification of the Source Range High Flux at Shutdown Alarm Setpoint of less than or equal to 2.30 times background.

V0GTLE UNITS - 1 & 2 3/4 3-13 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

q i l

TABLE 4.3-1 (Continued)

TABLE NOTATIONS (Continued)

(10) Setpoint verification is not applicable.

'(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the OPERABILITY of the Undervoltage and Shunt trip of the Reactor Trip Breaker.

(12) Not Used.

t (13) Not used.

r (14) The TRIP ACTUATING DEVICE OPERATIONAL 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 i

Bypass Breaker trip circuit (s).

(15) local manual shunt trip prior to placing breaker in service.

(16) Automatic undervoltage trip.

i l

y i

l l

i i

i 3

V0GTLE UNITS - 1 & 2 3/4 3-14 Amendment No. 67 (Unit 1)

.)

Amandment No. 46 (Unit 2)

^

TABLE 3.3-2 w

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION C

MINIMUM m

TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION a-1.

Safety Injection (Reactor Trip, Feedwater Isolation, m

Component Cooling Water, Control Room Emergency Filtration System Actuation, Start Diesel Generators, Containment Cooling Fans, Nuclear Service Cooling Water, Containment Isolation, Con-tainment Ventilation Isolation, and Auxiliary Feedwater Motor-Driven Pumps).

w1 a.

Manual Initiation 2

1 2

1,2,3,4 19 w

.L b.

Automatic Actuation 2

1 2

1, 2, 3, 4 14 Logic and Actuation Relays l

c.

Containment Pressure--High-l*

3 2

2 1,2,3,4 20 gg (PI-0934, PI-0935, PI-0936) mm EE d.

Pressurizer Pressure--Low 4

2 3

1, 2, 3*

20 82 (PI-0455A,B&C, PI-0456 &

55 PI-0456A, PI-0457 & PI-0457A, g:g:

PI-0458 & PI-0458A) e.

Steam Line Pressure--Low

3/ steam line 2/ steam line 2/ steam line 1, 2, 3' 20 l

o

.any steam line ow (LOOP 1 LOOP 2 LOOP 3 LOOP 4 l

gg PI-0514A,B&C PI-0524A&B PI-0534A&B PI-0544A,B&C j

L :L PI-0515A PI-0525A PI-0535A PI-0545A l

<+ "

PI-0516A PI-0526A PI-0536A PI-0546A)

\\

",3C l

See Specification 3.3.3.6

TABLE 3.3-2 (Continued) pg ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION S

p; MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE c:

25 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

-i I'

4.

Steam Line Isolation (Continued) c.

Containment Pressure--High-2*

3 2

2 1, 2', 3' 20 l

ll (PI-0934, PI-0935, PI-0936) d.

Steam Line Pressure--Low

3/ steam 2/ steam 2/ steam 1, 2', 3*d 20 l-line line any line steam line (LOOP 1 LOOP 2 LOOP 3 LOOP 4 PI-0514A,B&C PIOS 24A&B PI-0534A&B PI-0544A,8&C, PI-0515A PI-0525A PI-0535A PI-0545A, PI-0516A PI-0526A PI-0536A PI-;546A) m

((

e.

Steam Line Pressure -

3/ steam 2/ steam 2/ steam 3'd 20 g,

Negative Rate--High*

line line any line c) steam line (LOOP 1 LOOP 2 LOOP 3 LOOP 4 PI-0514A,8&C PI-0524A&B PI-0534A&B PI-0544A,B&C PI-0515A PI-0525A PI-0535A PI-0545A gg PI-0516A PI-0526A PI-0536A PI-0546A)

.r.r

.t!I

(

5.

Turbine Trip and Feedwater Isolation 55 EI a.

Automatic Actuation Logic 2

1 2

1,2 25

.gg and Actuation Relays b.

Low RCS Tavg Coincident with Reactor Trip **

u cn 1.

Low RCS T,y 4

2 3

1,2 20 2.

Reactor Trip, P-4 See Functional >Jnit 9.b. for P-4 requirements.

CC EL EL rr

See Specification 3.3.3.6 r3;;

- Feedwater isolation only.

Turbine trip occurs on reactor. trip.

s

~.

TABLE 3.3-2 (Continued 1 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION I

MINIMUM si TOTAL NO.

CHANNELS CHANNELS APPLICABLE 6

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION.

m i

e.

Trip of All Main Feedwater Pumps, Start Motor-Driven Pumps 2

2 2

1, 2 23 e.

f.

Manual Initiation f

1/ pump 1/ pump 1, 2, 3 23 m

7.

Semi-Automatic Switchover to Containment Emergency Sump a.

Automatic Actuation Logic 2

1 2

1,2,3,4 14 and Actuation Relays b.

RWST Level--Low-Low Coincident 4

2 3

1,2,3,4 15 l

with Safety Injection

See Functional Unit 1. above for all Safety Injection initiating w

(LI-0990A&B, LI-0991A&B, functions and requirements.

'f LI-0992A, LI-0993A)

U 8.

Loss of Power to 4.16 kV ESF Bus a.

4.16 kV ESF Bus 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 29 l

Undervoltage-Loss of Voltage EE oa b.

4.16 kV ESF Bus EE Undervoltage-Degraded ll Voltage 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 29 l

en zz 9.

Engineered Safety Features PP Actuation System Interlocks

$O a.

Pressurizer Pressure, P-11 3

2 2

1,2,3 21 (PI-0455A,8&C, PI-0456 &

gg PI-0456A, PI-0457 & PI-0457A) ao b.

Reactor Trip, P-4 2

1 2

1,2,3 23 0:

See Specification 3.3.3.6

1 TABLE 3.3-2 (Continued) l TABLE NOTATIONS i

a Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

i b Trip function automatically blocked above P-11 and may be blocked below P-11 i

when Safety Injection on low steam line pressure is not blocked.

c During movement of irradiated fuel or movement of loads over irradiated fuel within containment.

l d Not Used.

e During movement of irradiated fuel or movement of loads over irradiated j

fuel.

f Not applicable if one main steam isolation valve and associated bypass is.o-lation valve per steamline is closed.

j g Containment Ventilation Radiation (RE-2565) is treated as one channel and is considered OPERABLE if the particulate (RE-2565A) and iodine monitors (RE-2565B) are OPERABLE or the noble gas monitor (RE-2565C) is OPERABLE.

h Manual initiation of Auxiliary Feedwater is accomplished via the pump I

handswitches.

t i Whenever irradiated fuel is in either storage pool.

j For actions associated with inoperable instrumentation, follow actions j

specified in Specification 3.9.12.

ACTION STATEMENTS l

ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or be in at least HOT STANDBY l

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD. SHUTDOWN within the follow-l ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to i

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, l

provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total i

Number of Channels, operation may proceed provided the inoper-able channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met.

One additional channel t

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 4.3.2.1.

ACTION 16 - With the number of OPEP.ABLE channels less than the Minimum i

Channels OPERABLE requirement, comply with the ACTION

~

requirements of Specification 3.9.9 (Mode 6).

V0GTLE UNITS - 1 & 2 3/4 3-25 Amendment No.

67 (Unit 1)

Amendment No. 46 (Unit 2)

t TABLE 3.3-2 (Continued.1 l

ACTION STATEMENTS (Continued)

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoper-able channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel 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 per l

Specification 4.3.2.1.

3 ACTION 18 - With one less than the Miniram Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are closed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 19 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to I

OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 20 - With the number of OPERABLE channels one less than the Total I

Number of Charnels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

i b.

The Minimum Channels OPERABLE requirement is met; i

however, a channel 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 per Specification 4.3.2.1.

ACTION 21 - With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than 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 at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

V0GTLE UNITS - 1 & 2 3/4 3-26 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued)

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 declare the associated valve inoper-i able and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status witin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or be in at least HOT STANDBY within the next 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore at least one channel to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ini-tiate and maintain operation of the Control Room Emergency Filtration System in the Emergency mode #.

ACTION 27 - a) With one channel inoperable in a unit, restore the inoperable channel to OPEPABLE status within 7 days OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of one Control Room Emergency Filtration System (CREFS) in the unaffected unit in the emergency mode #.

b) With one channel inoperable in each unit, restore each inoperable channel to OPERABLE status within 7 days OR t

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of one CREFS in each unit in the emergency mode #.

l c) With two channels inoperable in a unit, within I hour either

1) initiate and maintain operation of the two CREFS in the unaffected unit OR 2) initiate and maintain operation of one r

CREFS in each unit in the emergency mode #,

d) With three channels inoperable, within I hour initiate and maintain operation of the two CREFS in the emergency mode in i

the unit with only one channel inoperable.

e) With four channels inoperable, within I hour initiate and maintain operation of two CREFS in the emergency mode.

ACTION 28 - a) With one channel inoperable in a unit, restore the inoper-able channel to OPERABLE status within 7 days, OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either 1) lock closed the affected and lock open the unaffected OSA intake dampers OR 2) initiate and maintain operation of one CREFS in the emergency mode #.

l l

The initiated CREFS shall be Train B unless Train B is inoperable.

V0GTLE UNITS - 1 & 2 3/4 3-27 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

1 TABLE 3.3-2 (Continued) i ACTION STATEMENTS (Continued) i b) With one channel inoperable in each unit, restore each j

inoperable channel to OPERABLE status within 7 days OR within the n' ext 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of one CREFS in the emergency mode #.

c) With two channels inoperable in a unit, within I hour either.

1) lock closed the affected and lock open the unaffected OSA intake dampers OR 2) initiate and maintain operation of one CREFS in each unit in the emergency mode #.

d) With three channels inoperable, within I hour either 1) lock closed the OSA intake dampers of the unit with two inoper-able channels and lock open the other OSA intake dampers and either restore the remaining affected channel to OPERABLE status within 7 days OR initiate and maintain operation.qf one CREFS in the emergency mode # in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR

2) initiate and maintain operation of one CREFS in each unit in the emergency mode #.

e) With four channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and

)

maintain operation of one CREFS in each unit in the emergency mode #,

i ACTION 29 - With the number of OPERABLE channels one less than the Total Numoer of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, an additional 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 other channels per Specification i

4.3.2.1.

l i

The initiated CREFS shall be Train B unless Train B is inoperable.

V0GTLE UNITS - 1 & 2 3/4 3-27a Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

5 TABLE 4.3-2 S

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l

E SURVEILLANCE REQUIREMENTS C

l 5

TRIP d

ANALOG ACTUATING MODES s

CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE p.

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST.TlS.I IEST IS REQUIRED N

1.

Safety Injection (Reactor Trip, Feedwater Isolation, Component Cooling Water, Control Room Emergency Filtration System Actuation, Start Diesel Generators, Containment Cooling Fans, Nuclear Service Cooling Water, Containment Isolation, M

Containment Ventilation Isolation, and

[

Auxiliary Feadwater Motor-driven Pumps).

b

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

b. Automatic Actuation N.A.

N.A.

M(1)

M(I)

Q 1, 2, 3, 4 Logic and Actuation Relays kk

c. Containment Pressure-S R

Q N.A.

N.A.

l##,2##,

RR 3##,491 gg High-l* (PIO934, PIO935, PIO936) 2, OO

d. Pressurizer Pressure S

R Q

N.A.

l##,2##,

3##

Low (PIO455A,B&C, PIO456 & PIO456A, 22 PIO457 & PIO457A, hh PIO458 & PIO458A)

U U *See Specification 4.3.3.6

.,,_.x

,.o..

.-._y_

l TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g

SURVEILLANCE REQUIREMENTS E

TRIP g

ANALOG ACTUATING

. MODES g

CHANNEL DEVICE MASTER SLAVE FOR WHICH m

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

~

1. (Continued) p.

~

e. Steam Line S

R Q

N.A.

l##,'2##, 3## l' Pressure-Low *

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 PI-0514A,B&C PI-0524A&B PI-0534A&B PI-0544A,B&C PI-0515A PI-0525A PI-0535A PI-0545A PI-0516A PI-0526A PI-0536A PI-0546A) w1

2. Containment Spray

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

b. Automatic Actuation N.A.

N.A.

M(1)

M(I)

Q 1,2,3,4 Logic and Actuation Relays

((

c. Containment Pressure-S R

Q N.A.

N.A.

1", 2", 3", 4" gg High-3* (PI-0934, gg PI-0935, PI-0936, gg PI-0937) f f

3. Containment Isolation

a. Phase "A" Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

_gg

2) Automatic Actuation N.A.

N.A.

_N.A.

M(1)

Ql, 2, 3, 4 gg Logic and Actuation Relays

See Specification 4.3.3.6.

g TABLE 4.3-2 (Continued)

Sg ENGINEERED SAFETY FEATURES ACTUATION SYNfEM INSTRUMENTAT'Off SURVEILLANCE RE0VIREMEN12 c5g TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED y

4. Stea:a Line Isolation

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

-1, 2, 3

b. Automatic Actuation N.A.

N.A N.A N.A.

M(1)

Q 1, 2, 3 Logic and Actuation Relays

c. Containment Pressure-S R

Q N.A.

N.A.

l##, 2##, 3##

High-2* (PI-0934, o

d, PI-0935, PI-0936) e

d. Steam Line S

R Q

N.A.

l##,2##,3##l Pressure-Low

gg (LOOP 1 LOOP 2 LOOP 3 LOOP 4 EE PI-0514A,8&C PI-0524A&B PI-0534A&B PI-0544A,B&C PI-0515A PI-0525A, PI-0535A PI-0545A EE PI-0516A PI-0526A PI-0536A PI-0546A)

EE

e. Steam Line Pressure-S R

Q N.A.

N.A.

3##

l Negative Rate-High*

w (LOOP 1

. LOOP 2 LOOP 3 LOOP 4 gg PI-0514A,B&C PI-0524A&B PI-0534A&B PI-0544A,8&C

=. :5,.

PI-0515A PI-0525A PI-0535A PI-0545A e+ c+

PI-0516A PI-0526A PI-0536A PI-0546A) 00

See Specification 4.3.3.6 e

j TABLE 4.3-2 (Continued) o f{

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS c-5 TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED n,

5. Turbine Trip and Feedwater Isolation

a. Automatic Actuation N.A.

N.A.

N A.

M(1)

Q 1, 2 Logic and Actuation Relays

b. Low RCS Tavg us ls Coincident with Reactor Trip

usj; 1.

Low RCS T,y S

R M

N.A.

l##, 2##

l 2.

Reactor Trip, P4 See Functional Unit 9.b. for P4 Surveillance requirements.

c Steam Generator S

R Q

N.A.

l##, 2##

l gigt Wate, Level-High-

.g g Higt** (P14) aa!$

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 en if jf LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549

.,, e, o' "

LI-0551 LI-0552 LI-0553 LI-0554) q; g

d. Safety Injection See Functional Unit 1. above for all Safety Injection Surveillance Requiremants.

bbbb I300

Feedwater isolation only.

Turbine trip occurs on reactor trip.

- See Specification 4.3.3.6 v---

w-r m

r#.--

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8

d TRIP ANALOG ACTUATING MODES -

E CHANNEL DEVICE MASTER SLAVE FOR WHICH Z

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE y FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS RE0VIRED

~

6. Auxiliary Feedwater p.

a. Automatic Actuation N.A.

N.A N.A.

N.A.

M(1)

Q 1, 2, 3 Logic and Actuation Relays

b. Steam Generator Water Level-Low-low *

(LOOP 1 LOOP 2 10P3 LOOP 4 LI-0517 LI-0527

' 0537 LI-0547 LI-0518 LI-0528 i.I-0538 LI-0548 w

A LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554)

~

1) Start Motor-Driven Pumps S

R Q

N.A.

N.A N.A l##, 2##, 3##

2) Start Turbine Driven kk Pump S

R Q

N.A.

N.A N.A l##, 2##, 3## l ooSS

c. Safety Injection Start See Functional Unit 1. above for all Safety Injection Surveillance Requirements.

Motor-Driven Pumps yy

d. Loss of or Degraded N.A.

R Q

N.A.

N.A 1, 2, 3 l

4.16 kV ESF Bus Voltage SO

e. Trip of All Main Feed-N. A.

N.A.

R N.A.

N.A.

N.A 1, 2 Water Pumps, Start gg Motor-Driven Pumps hh

f. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3 OO

See Specification 4.3.3.6 4

Ej TABLE 4.3-2 (Continued)

S G;

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c:

SURVEILLANCE REQUIREMENTS 5

Dj TRIP i

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE na FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REOUIRED

7. Semi-Automatic Switchover to Containment Emergency Sump

a. Automatic Actuation N.A.

N.A.

M(1)

Q 1,2,3,4 Logic and Actuation Relays j{

b. RWST Level-Low-Low

S R

H N.A.

N.A.

N.A 1", 2", 3", 4" Coincident With Safety Inj,ection

$5 (LI-0990A&B, LI-0991A&B, LI-0992A, LI-0993A)

8. Loss cf Power to 4.16 kV ESF Bus

![![

a.

4.16 kV ESF Bus N.A.

R M

N.A.

1, 2, 3, 4 gg Undervoltage-Loss gg of Voltage

!I!I b.

4.16 kV ESF Bus N.A.

R M-N.A.

N.A.

1, 2, 3, 4 Undervoltage-sR EO Degraded Voltage 1212 SS Ei 1

See Specification 4.3.3.6 s

(

k

~

2s TABLE 4.3-2 (Continued)

El -

o

.l~

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION e

SURVEILLANCE RE0UIREMENTS z

Di TRIP i

ANALOG ACTUATING MODES

.a CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY

. RELAY SURVEILLANCE na FUNCTIONAL UNIT CHECK CALIBRATION IEST TEST LOGIC TEST TEST TEST IS REQUIRED 9.

Engineered Safety Features Actuation System Interlocks

a. Pressurizer N.A.

R Q

N.A.

l##,'2##, 3##

Pressure, P-11 (PI-0455A,B&C, PI-0456 & PI-0456A,

[

PI-0457 & PI-0457A)

$5 b.

Reactor Trip, P-4 N.A.

N.A.

R N.A.

N.A.

1,'2, 3 -

10.

Control Room Emergency Filtration System Actuation

![![-

a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

Either Unit in EL EL-1,2,3,4,

',5 g 5#, 6#

b.

Automatic Actuation me 2, P.o Logic and Actuation Either Unit in Relays N.A.

N.A.

M(1)

N.A.

1,.2, 3,'4, g;e; 5#, 6#

EE r+ r+

ISE: '

During movement of irradiated fuel or movement of loads over. irradiated fuel.

l' j

..JP

_. -. ~ - -,

TABLE 4.3-2 (Continued) h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

d SURVEILLANCE REOUIREMENTS m

E TRIP Z

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL GPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

{ FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED m

10.

Control Room Emergency Filtration System Actuation (Continued) c.

Safety Injection See Functional Unit 1. above for all Safety Injection Surveillance Requirements.

d.

Intake Radiogas Either Unit-in Monitor S

R H

N.A.

1, 2, 3, 4, 5#, 6#

(RE-12116, RE-12117) 11.

Fuel Handling Building Post w

Accident Ventilation Actuation h

(Common System) a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

(2) b.

Fuel Handling S

R H

N.A.

(2)

Building Exhaust YE Duct Radiation EE Signal EE (ARE-2532 A&B

$k ARE-2533 A&B) c.

Automatic N.A.

N.A.

M(1)

N.A.

(2)

Actuation Logic gg and Actuation Relays TABLE NOTATION

^^cc S. S.

(1)

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

(2)

Whenever irradiated fuel is in either storage pool.

OO During movement of irradiated fuel or movement of loads over irridated fuel..

This function may be bypassed for surveillance testing provided that the applicable Action Statement requirements are met.

-_-------------,---.-_-----,,--_---..,-__-_._----.m_----------,-------.-a,-__

- - - - - - - - -, - - - - -_-_-----Y

=t-La,-

r" m-

,z v

9 w

+e it

TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS E5 MINIMUM gi CHANNELS CHANNELS APPLICABLE ALARM / TRIP

q FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION w

l.

Containment

a. Containment Area (High Range) 1 See Table 1, 2, 3, 4 100 R/hr See (RE-0005, RE-0006) 3.38 Table 3.3-8

^>

b. RCS Leakage Detection

1) Gaseous Activity (RE-2562C) 1 1

1,2,3,4 s 2 x back-30 ground l

2)

Particulate Activity 1

1 1, 2, 3, 4 s 2 x back-30 (RE-2562A) ground 2.

Containment Ventilation 1

2' 1, 2, 3, 4, See See 6'

' Table 3 33 Table 3.32 u,

i Area low Range (RE-0002, RE-0003)

Gaseous Activity (RE-2565C)

Particulate Activity (RE-2565A)

Iodine Activity (RE-2565B) g g>

3.

Control Room Air Intake m.

ELil (RE-12116, RE-12117)

Either Unit in MM 1

2 5, 6, 3, 4 I

2, See See g

?+ ??

Table 3.3-3 Table 3.3-2 E.E CC

-o.*.

ce r+

e

TABLE 3.3-4 (Continued)

TABLE NOTATIONS a During movement of irradiated fuel or movement of loads over irradiated fuel within containment.

b During movement of irradiated fuel or movement of loads over irradiated fuel.

RE-2565 is considered OPERABLE if the Particulate (RE-2565A) and lodine (RE-c 2565B) Monitors are OPERABLE, or the noble gas monitor (RE-2565C) is OPERABLE.

ACTION STATEMENTS ACTION 30 -

With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, satisfy the ACTION requirements of Specification 3.4.6.1.

V0GTLE UNITS - 1 & 2 3/4 3-47 Amendment No. 67 (Unit 1)

Anandment No. 46 (Unit 2)

TABLE 3.3-8 h

ACCIDENT MONITORING INSTRUMENTATION M

TOTAL MINIMUM E

NO. OF CHANNELS

]

INSTRUMENT CHANNELS OPERABLE ACTION l.

Reactor Coolant Pressure (Wide Range) 4 1

37

(

~

(Loop 408, 418, 428, & 438) a.

Reactor Coolant System That (Wide Range) 1/ loop 1/ loop 34 l

2.

(Loop 413A, 423A, 433A & 443A) 3.

Reactor Coolant System Tm (Wide Range) 1/ loop 1/ loop 34 (Loop 413B, 423B, 433B & 4438) 4.

SG Water Level (Wide Range) 1/SG 1/SG 34 l

(Loop 501, 502, 503 & 504) 5.

SG Water Level (Narrow Range) 4/SG 1/SG 37-(Loop 517, 518, 519, 527, 528, 529, 537, 538, 539, 547, w

h 548, 549, 551, 552, 553, 554) 6.

Pressurizer Level 3

1 31 l

(Loop 459, 460, 461)

-pg 7.

Containment Pressure 4

1 37 l

gg (Loop 934, 935, 936, 937)

a. o.

8.

Steamline Pressure 3/stm. line 1/stm. line 31 l

(Loop 514, 515, 516, 524, 525, 526, 534, 535, 536, 544, gg 545 & 546) l 9.

RWST Level 4

1 37 we (Loop 990, 991, 992 & 993) gg

10. Containment Normal Sumps Level (Narrow Range) 2 1

32 l

a :L (Loop 7777 & 7789)

MM i

3-

11. Containment Water Level (Wide Range) 2 1

32 (Loop 0764 & 0765) l

)

1 1

TABLE 3.3-8 (Continued)

ACCIDENT MONITORING INSTRUMENTATION 5

TOTAL MINIMUM-c.

5 NO. OF CHANNELS d

INSTRUMENT CHANNELS OPERABLE ACTION' b

12. Condensate Storage Tank Level 2/ tank 1/ tank

'32 (Loop 5101, 5111, 5104 & 5116)

~ '

13. Auxiliary Feedwater Flow 2/ feed line 1/ feed line 32 l

(Loop 5152, 15152, 4 53, 15153, 5151, 15151, 5150 & 15150)

14. Containment Radiation Level (High Range) 2 1

35' l

(Loop.0005 & 0006)

15. Steamline Radiation Monitor 1/stm. line 1/stm. line 35' l

(Loop 13119, 13120, 13121 & 13122)

16. Core Exit Thermocouples 4/ quad / train 2/ quad / train 31' l

8 17.

Reactor Coolant System Subcooling 2

1 32 l

18. Neutron Flux (Extended Range) 2 1

32

- l (Loop 13135A & 131358)

((

19. RVLIS' 2

1

'36 l

ao

. II

20. Containment Hydrogen Concentration 2

1 33 l

%{

(Loop 12979 & 12980)

EE

21. Containment Pressure (Extended Range) 2 1

32 l

.(Loop 10942 & 10943) i. SO l

22. Containment Isolation Valve' Position Indication

1/ valve 1/ valve 38.

22

! ~~~

Applicable for cont'ainment isolation valve position indication designated' as post-accident monitoring instrumentatidn-

~

L (containment isolation valves which receive containment' isolation' Phase A or containment ventilation isolation j

signals).

i

.m m

-. u.....-

.~.....-.

,_______a___

,__._1_

TABLE 3.3-8 (Continued)

ACTION STATEMENTS ACTION 31

- a.

With the number of OPERABLE channels one less than the Total Number of Channels requirement, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE channels two less than the Total Number of Channels requirement, restore at least one inoper-able channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, restore at least one inoper.

able 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 SHUTDOWN within the next 12 hnurs.

d.

The provisions of Specification 3.0.4 are not applicable.

ACTION 32 - a.

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

Number of Channels requirement, restore one inoperable chan-nel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, restore at least one inoper-able 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

The provisions of Specification 3.0.4 are not applicable.

ACTION 33 - a.

With the number of OPERABLE channels less than the Total l

Number of Channels requirement, comply with the provisions of Specification 3.6.4.1.

i b.

The provisions of Specification 3.0.4 are not applicable.

ACTION 34 With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, restore at least one inoper-able 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 are not applicable.

ACTION 35 With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, initiate the alternate method of monitoring the parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commis-sion, pursuant to Specification 6.8.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE l

status.

i V0GTLE UNITS - 1 & 2 3/4 3-61 Amendment No.

67 (Unit 1)

Amendment No.

46 '(Unit 2)

TABLE 3.3-8 (Continued)

ACTION STATEMENTS ACTION 36 -

With the number of OPERABLE channels less than the required num-ber of channels or the Minimum Channels OPERABLE requirement, restore the inoperable channel (s) to OPERABLE status as per Action 32a or 33a as applicable if repair is feasible during l

plant operation.

If repair is not feasible, prepare and submit a Special Report to the Commission, pursuant to Specification 6.8.2 within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status. The provisions of Specification 3.0.4 are not applicable.*

ACTION 37 - a. With the number of OPERABLE channels two less than the Total Number of Channels requirement, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b With the number of OPERABLE channels three less than the Total Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7' days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. With the number of OPERABLE channels less than the Minimum Chan-nels OPERABLE requirement, restore at least one inoperable chan-nel to OPERABLE status with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The provisions of Specification 3.0.4 are not applicable.

i ACTION 38 - With the number of OPERABLE channels less than the Minimum Channels i

OPERABLE requirement, comply with the provisions of Specification 3.6.3. for an inoperable containment isolation valve.

1 1

1

Action Statement 36 applies to the first fuel cycle only. Action Statement 32 is applicable thereafter.

V0GTLE UNITS - 1 & 2 3/4 3-62 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTVATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and the Engineered Safety 1

Features Actuation System instrumentation and interlocks ensures:

(1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance consistent with main-taining an appropriate level of reliability of the Reactor Trip System and Engineered Safety Features Actuation System instrumentation, and (3) sufficient system functional capability is available from diverse parameters.

~

The OPERABILITY of these systems is required to provide the overall reli-ability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.

The inte-grated operation of each of these systems is consistent with the assumptions used in the safety analyses. The Surveillance Requirements specified for tttese systems ensure that the overall system functional capability is maintained com-parable to the original design standards. The periodic surveillance tests per-formed at the minimum frequencies are sufficient to demonstrate this capabil-ity.

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Sur-veillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and supplements to that report.

Surveillance inter-vals and out of service times were determined based upon maintaining an appro-priate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.

The NRC Safety Evaluation Reports for WCAP-10271 and its supplements were provided in letters dated February 21, 1985, from C. O. Thomas (NRC) to J. J. Sheppard (WOG-GP); February 22, 1989, from C. E. Rossi (NRC) to R. A. Newton (WOG); and on April 30, 1990, from C. E.

Rossi to G. T. Goering.

The Engineered Safety Features Actuation System Instrumentation Trip Set-points specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.

To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated.

Allowable Values for the Setpoints have been specified in Table 3.3-3.

Opera-tion with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncertainties of the instrumentation to measure the process variable and the uncertainties in calibrating the instrumentation.

In Equation 2.2-1, Z + R + S 5 TA, the interactive effects of the errors in the rack and the sensor, and the "as measured" values of the errors are considered.

Z, as V0GTLE UNITS - 1 & 2 B 3/4 3-1 Amendment No. 67 (Unit 1)

Amendment No. 46 (Unit 2)

.

ML20058N011

Text

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