Text

Proposed Tech Specs Re ESF Actuation Sys
	ML20034G277
Person / Time
Site:	Vogtle
Issue date:	03/01/1993
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML19303F394	List: ELV-03878, Application for Amends to Licenses NPF-68 & NPF-81,revising TSs Re ESF Actuation sys.WCAP-13377,Rev 2 & Proprietary WCAP-13376,Rev 2, Bypass Test Instrumentation for Vogtle Electric..., encl.WCAP-13376,Rev 2 Withheld; ML20034G275; ML20034G277; ML20034G279;
References
	NUDOCS 9303090274
	Download: ML20034G277 (35)
	v • d • e

-., - -

O I

J ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS i

l l

i i

l 9303G90274 930301 PDR ADOCK 05000424 P

PDR

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION e

MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE I

j.

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

b b.

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

6 o.

below P-8) two oper-each oper-ating loops ating loop m

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 F1-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446) 6[

D 13.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 w

level--Low-Low

in any oper-each oper-

)

ating stm.

w gen.

gen.

(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

[ ')6 Pumps 4-2/ bus 2'

3 I

I 15.

Underfrequency--Reactor Coolant 6

[9 Pumps 4-2/ bus 2'

3 I

I 16.

Turbine Trip b

a.

Low Fluid Oil Pressure 3

2 2

l' 6

(PT-6161, PT-6162, PT-6163)

D b.

Turbine Stop Valve Closure 4

4 1

l' 12 l

17.

Safety Injection Input from ESF 2

1

?

1, 2

)(f7 i

- -' Specific,'*on 3.3.3.F v

v v

TABLE 3.3-1 (Continued) e S

REACTOR TRIP SYSTEM INSTRUMENTATION 5

MINIMUM Ej 10TAL NO.

CHANNELS CHANNELS APPLICABLE v'

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 18.

Reactor Trip System Interlocks P'

a.

Intermediate Range c

Neutron Flux, P-6 2

1 2

2 8

h3 (NI-0035B,0&E, NI-00368,0&G) l b.

Power Range Neutron Flux, P-8 4

2 3

1 8

(NI-0041B&C, NI-0042B&C.

NI-0043B&C, NI-0044B&C)

R2 c.

Power Range Neutron 4

2 3

1 8

=

Flux, P-9 32 (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-00448&C) tn l

d.

Power Range Neutron Flux, P-10 4

2 3

1, 2 8

(NI-0041B&C,N1-0042B&C, l

NI-0043B&C, NI-0044B&C) e.

Turbine Impulse Chamber Pressure, P-13 2

1 2

1 8

(PI-0505,PI-0506) 19.

Reactor Trip Breakers 2

1 2

1, 2 10, 13 a

a a

2 1

2 3,4 S

37 20.

Automatic Trip and Interlock 2

1 2

1, 2 JAF7 a

a a

Logic 2

1 2

3,4,S 11 i

,~

_. ~,.. - -...

2

TABLE 3.3-1 (ContinueJ)

' TABLE NOTATIONS

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

b The provisions of Specification 3.0.4 are not applicable.

)

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

d Below the P-10 (Low 5etpoint 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 Th: ;ppli ntle i da

-.d A;tien Stet;n nt fe~r the3e channel; neted 'n T:b h 2.?-2 : = = ; r::tricti;: cr.d, ther:fer;, :ppli ab k. /4,f uR (/,

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

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 OP 'ABLE 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 :

,t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 , b.

The Minimum Channels OPERABLE requirement is met; however, th; in;p; roble 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 testin e' eth: ch: m: h per Specification 4.3.1.1, and CL C b athh el c.

Either, THERMAL POWER is restricted to less than or equal I

to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip 5etpoint 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.

s V0GTLE UNITS - 1 & 2 3/4 3-6

')

(1 s

TABLE 3.3-1 (Continued) l ACTION STATEMENTS (Continued)

ACTION 3 - With t u 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 Mini-mum 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 Reac-tor Trip System breakers, suspend all operations involving positive reactivity changes and verify valves 1208-U4-175, 1208-04-177, 1208-U4-183, and 1208-U4-176 are closed and secured in position within the next hour.

b.

With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes, and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour 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 1208-04-17f. 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 less than the Total Number of Channels, 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 b.

The Minimum Channels OPERABLE requirement is met; however, the i v re h d --d ay,be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testi

..: : uy.i per Specification 4.3.1.1.

- a, c,ngnnel ACTION 7 - (yas eee*5) M4h the nomin af OPERABLE Chuo,els one /m than de Mia, *m am Channelt OAFRA846" reguirement n'.thrt 44e inopers4Ar ebenne/t{o OPEMBLE ddu.T Wilbur lo bours or be in si feas/ //07 STANDBY widA4, t!Ae nexf fe hours.:

varun ~2 hps ecc.gresie uqu a ne o neglanna/ ma be sed fa, to 4 k v 4 wever

- a~ ciis OprsWe.

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive sta-tus light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

)

ACTION 9 - (6L useo)

ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least 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 j

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 OPERA 9LE.

ACTION 11 - With the r.=ber of OPERABLE channels one less than the Minimum Channels ODERABLE 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.

ACTION 12 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AGMN 13 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable restore it to OPERABLE status within 4B hours 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 mainte-nance to restore the breaker to OPERABLE status.

6Jdh the number O OPERABLE channek one /e.n than de 7Hr/

y Number of Channels, STARTOP cacl/or PotuGR OPERar~ ton' may proceed provodetl the fellooE13 conoW&n3 a r c S a l is b e' / :

7be ihoperalle cAunel a laced k Me frppd' conoMk a.

40/fhth b

bourS, and i

6 TAe /Gawm Cf anned OPERMM re@emed k xe4 however.,

dAe ihopea6/e chnnel mag 6e Agased foc up I

do 4 dours for survei$ance fesik.s W o/Aer cAa/isA per SpecMcccitoh 4.3. /. /

V0GTLE UNITS - 1 & 2 3/4 3-8

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

TRIP S

ANALOG ACTUATING MODES FOR E

CllANNEL DEVICE WHICH c

CilANNEL CllANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE 6,

FUNCTIONAL UNIT CllECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED v

a a

e 1.

Manual Reactor Trip N.A.

N.A.

R(14)

N.A.

1 2, 3, 4,

3 u

5 e-2.

Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, m

NI-0043B&C, NI-00440&C)

If a.

High Setpoint 5

D(2,4),

Q N.A.

N.A.

I 2 M(3, 4),

Q(4,6),

R(4, 5)

I,f f d

b.

Low Setpoint S

R(4)

S/U(1)

N.A.

2 Power Ran Neutron Flux, N.A.

R(4)

QJJ7I N.A.

N.A.

IT 2f 3.

HighPosibv,eRate w

E (NI-0041B&C,NI-0042B&C, NI-0043B&C,NI-0044B&C) 4.

Deleted I.,f f d

5.

Intermediate Range, S

R(4,5)

S/U(1)

N.A N.A.

2 Neutron Flux (NI-00358,0&E, y$

NI-00368,D&G) k k 6.

Source Range, Neutron Flux 5

R(4,5) 6/'!( 0,Q(9,'/)

N.A.

28[3i4I5+

C zz (NI-00318,0&E, Vu(. l.) 'Q(9)

PP NI-00328,D&G) 7.

Overtemperature AT S

R QM N.A.

N.A.

d2#

(101-0411C,101-04210, em

((

101-0431C,1D1-0441C) ee U

-,.. ~.

TABLE 4.3-1 (Continued) o S

REACTOR TRIP SYSTEM INSTRUMENTATION SURVElllANCE REQUIREMENTS e

TRIP ANALOG ACTUATING MODES FOR d

CllANNEL DEVICE WHICN CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT ClllCK CALIBRATION TEST TE51 LOGIC TEST 15 REQUIRED e.

m B.

Overpower ai 5

R QM N.A.

N.A.

If 2I (101-0411B, 101-04218 T01-04318, T01-04418) 9.

Pressurizer Pressure--Low 5

R QM N.A.

N.A.

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

PI-0456A, PI-0457 &

PI-0457A, PI-045B &

PI-0458A) w Q(M N.A.

N. A.

li 2E 10.

Pressurizer Pressure--High 5

R (PI-0455A,B&C, Pl.-0456

& PI-0456A, PI-0457

& PI-0457A, PI-0458

& PI-0458A)

11.. Pressurizer Water Level--

5 R

Q(y/)

N.A.

I'd High*

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

Q%

N.A.

I's 12.

Reactor Coolant Flow--Low 5

R (LOOP 1 LOOP 2 LOOP 3 LOOP 4 F1-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 -FI-0445 FI-0416 FI-0426 FI-0436 FI-0446)

See Specification 4.3.3.6 i

i e

i 1

em

TABLE 4.3-1 (Continued) o S

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS r,

TRIP c-5 ANALOG ACTUATING MODES FOR d

CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE s

FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST IS REQUIRED Q([Jd N.A.

N.A.

1 2 m

13.

Steam Generator Water Level--

5 R

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 L1-0539 LI-0549 LI-0551 Li-0552 Li-0553 LI-05S4) 14.

Undervoltage - Reactor Coolant N.A.

R N.A.

QM N.A.

l' Pumps Q(#[

N.A.

l'

15. Underfrequency - Reactor N.A.

R N.A.

Coolant Pumps 16.

Turbine Trip 1[

D a.

Low Fluid Oil Pressure N.A.

.R S/U (1, IP)

N.A.

g (PT-6161, PT-6162, PT-6163) b b.

Turbine Stop Valve Closure N.A.

R N.A.

S/U(1, 10)

N.A.

I 17.

Safety injection input from N.A.

N.A.

R N.A.

1, 2 ESF 18.

Reactor Trip System Interlocks 2 >4 i

a.

Intermediate Range C

Neutron 4?ux, P-6 N.A.

R(4)

R N.A.

N. A.

(Ni-00358,0&E, NI-00368,0&G)

"See Specification 4.3.3.6

TABLE 4.3-1 (Continued) e O

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

1 RIP O

ANALOG ACTUATING MODES FOR d

CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE.

e FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED w

e N

18.

Reactor Trip System Interlocks (Continued) b.

Power Range Neutron f

Flux, P-8 N.A.

R(4)

R N.A.

N.A.

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

J c.

Power Range Neutron R

Flux, P-9 N.A.

R(4)

R N.A.

N.A.

If (NI-0041B&C, NI-0042B&C, Y

NI-0043B&C,,NI-00448&C) d.

Power Range Neutron Flux P-10 N.A.

R(4)

R N.A.

N.A.

li2i e.

Turbine Impulse Chamber r

Pressure, P-13 N.A.

R R-N.A.

M.A.

If i

(PI-0505, PI-0506) 19.

Reactor Trip Breaker N.A.

N.A.

M(7,11)

N.A.

1, 2, 3,

l 8

4, $a a

8 20.

Automatic Trip and Interlock N.A.

N.A.

M(7) 1, 2, 3,

a 8

Logic 4,5 8

21.

Reactor Trip Bypass Ereaker N.A.

N. A.

N.A.

M(15),R(16)

N.A.

1,2,3 a

4,. 5'

.-...n

......-.m,m_...., -.

,--,_,...,--,mm.m-w_n,,

f 7%h funclicn may be. bypassel for.Sunteik Mr9

/

Providd 4hd -bbe appucDble AcGon Stakmerd reguiremenLr am med TABLE 4.3-1 (Continued)

TABLE NOTATIONS I

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

System is capable of roc withdrawal.

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

t Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

c i

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

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

e (1) If not performed in previous 31 days.

t (2) Compiirison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore cnannel gains consistent with calorimetric power if absolute cifference is greater than 2%.

The provisions of 5pecification 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 RA~tED lHERMAL POWER.

Recalibrate if the aosolute differenca is greater than or equal to.d.

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

For i

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

(a) Neutron cetectors may be excluced from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, and evaluated.

For the Intermediate Range anc 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 incere measurea axial power distribution to generate setpoints for the CHANNEL CALIBRATION.

The provisions of Specification 4.0.4 are not appli-caDie for entry into MODE 2 or 1.

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

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

(B) Not used.

a (9) Quarterly :,urve111ance in MODES f.

4", and 5 shall also inc1rt.e verifi-

~

cation that permissives P-6 and P-10 are in their required stice for existing plant conditions by observation of the permissive window.

Quarterly surveillance snall incluoe verification of the Source Range High Flux at Shutdown Alarm Setpoint of less than or equal to 2.30 times Dackgrounc.

i i

.037LE UNITS - 1 & 2 3/4 3-13

l 1

TABLE 4.3-1 (Continued)

TABLE NOTATIONS (Continueo)

(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.

i (12) Not used.

l (13) Not used.

(14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip cir.cuits for the Manual i

Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

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

l i

(16) Automatic undervoltage trip.

i l

(17) Each channci :h:ll be te;ted at it::t every 02 days ca e STAGGERED TEST t

EA5f5.

,18 The surveillence frequer.:y and/or "005: :pe;i'ic; fa 24.se sh;;;;1: in Table 4.3-2 are more rest +4cth e-end, therefore, applicabit.

i i

I i

\\

l f

i i

l l

V0GTLE UNITS - 1 & 2 3/4 3-14 Amendment No. 46 (Unit 1)

Amendment No. 25 (Unit 2)

~

n TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION G

MINIMUM c

TOTAL NO.

CHANNELS CHANNELS APPLICABLE (n

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION w

1.

Safety Injection (Reactor Trip, Feedwater Isolation, Component Cooling Water, Control Room N

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),

a.

Manual Initiation 2

1 2

1,2,3,4 19 U

b.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays c.

Containment Pressure--High-1*

3 2

2 1,2,3,4

/ 20 (PI-0934, PI-0935, PI-0936) 8 d.

Pressurizer Pressure--Low 4

2 3

1,2,3 2

(PI-0455A,8&C, PI-0456 &

PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) e.

Steam Line Pressure--Low

3/ steam line 2/ steam line 2/ steam line 1, 2, 3

[ /O 8

any steam line (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)

See Specification 3.3.3.6 w-

,m,-

---r, r

m

TABLE 3.3-2 (Continued)

O S

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION 1

E MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE d

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4.

Steam Line-Isolation (Continued) p.

c.

Containment Pressure--High-2*

3 2

2 1, 2, 3 MJO l

I I

(PI-0934, PI-0935, PI-0936) 1, 2, 3,f M/O I

a d.

Steam Line Pressure--Low

3/ steam 2/ steam 2/ steam line line any line (LOOP 1 LOOP 2 LOOP 3 LOOP 4 PI-0514A,B&C PI-0524A&B PI-0534A&B P I-0544 A,0&C,

w 2

PI-0515A PI-0525A PI-0535A PI-0545A.

PI-0516A PI-0526A PI-0536A PI-0546A) 3,f ggh w

b o

e.

Steam Line Pressure -

3/ steam 2/ steam 2/ steam Negative Rate--High*

line line any line steam line-(LOOP 1 LOOP 2 LOOP 3 LOOP 4 i

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)-

s 5.

Turbine Trip and Feedwater Isolation a.

Automatic Actuation Logic 2

1 2

1, 2 25-4 i -

and Actuation Relays b.

Low RCS Tavg Coincident with Reactor Trip **

'4 2

3 1, 2 2

1.

Low RCS T,g 2.

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

j

See Specification 3.3.3.6

- Feedwater isolation only. Turbine trip occurs on reactor trip.

M

.. -... _ ~... _. _ _ _. _ _ _.... _.,. _ ' _ _,.

.=.

. =.

n.

n 1ABLE 3.3-2 (Continued)

<8 ENGINEERED SAFETY rEATURES ACTUATION SYSTEM INSTRUMENTATION pf m

MINIMUM 5

TOTAL NO.

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

[,

e.

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

2 2

1, 2 23 p.

h f.

Manual Initiation 3

1/ pump 1/ pump 1,2,3 23 7.

Semi-Automatic Switchover to Containment Emergency Sump b

a.

Automatic Actuation Logic 2

1 2

1,2,3,4 14 and Actuation Relays f5' 3

b.

RWST Level--Low-Low Coincident 4

2 3

1,2,3,4

,17 with Safety Injection

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

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

LI-0992A, LI-0993A) w i

8.

Loss of Power to 4.16 kV ESF Bus,

p a.

4.16 kV ESF Bus 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 7

Undervoltage-loss of Voltage b.

4.16 kV ESF Bus I?9 Voltage 4/ bus 2/ bus 3/ bus 1,2,3,4 g,

Undervoltage-Degraded j

9.

Engineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure, P-11 3

2 2

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

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

Reactor Trip, P-4 2

1 2

1,2,3 23

]

"See Specification 3.3.3.6 J

5 1

l

TABLE 3.3-2 (Continued)

(

TABLE NOTATIONS Trip function may be blocked in this MODE below the P-11 (Pressurizer a

Pressure Interlock) Setpoint.

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

.P-11 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.

d e e i f k.;. m.. 0. C.4 ei s r.;;.sikLle.Nd(1b.

s.

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

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

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-25650) is OPERABLE.

h Manual initiation of Auxiliary Feedwater is accomplished via the pump handswitches.

f i Whenever irradiated fuel is in either storage pool.

j for actions associated with inoperabie instrumentation, follow actions specified in Specification 3.9.12.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY S

within*/ hours and in COLD SHUTDOWN within the following / hour 4

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 for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL 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 16 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, comply with the ACTION y

requirements of Specification 3.9.9 (Mode 6).

Win De numbe, d CPERABLE ebanmh cwe less dan s'Ae

Tot'd A%Ao of Ou*h I

opernG m!a proceulprovided t'Ae so esable danne/ ky/ued a t!Ae hyased cona% a d 1%e /bk Gened ChERAftr requdemed is M Gre aN%, /

i chusel mg Le h pa.ve,/ & cy 6 2 Aw& fw-n/veWlane 19&ig pc-buMut%

y 4.3.2.l.

V0GTLE UNITS - 1 & 2 3/4 3-25 l

TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued)

)

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

One additional channel

)

may be bypassert for up toghours for surveillance testing per

~

Specification 4.3.2.1.

4-ACTION 18 - With one less than the Minimum 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 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 SHUT 00WN 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 Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The ino erable channel is placed in the tripped conf tion within houd, and 8

The Minimum Channels OPERABLE requirement is met;[owever, CL b.

c= :dditic=1 channel may be bypassed for up to g hours for surveillance testing cf ethcr chr = h per Specification 4.3.2.1.

ACTION 21 - With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, within I hour determine by observa-tion of the associated permissive status light (s) that the inter-lock is in its required state for the existing plant condition,/ /o Ot5fAf or apply Specification 3.0.3.

Ntsfore ye Aeperslie c4 cme Obs M'1Ain 6 hwtJ,0r' ACTION 22 - With the number of OPERABLE ch nels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY ffe

, 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 ned 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 g hours for surveillance testing per Specification 4.3.2.1 provid the other channel is OPERABLE.

p 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 .

t V0GTLE UNITS - 1 & 2 3/4 3-26

Md*N b M88PO M

TABLE 3.3-2 (Continued) de O M M P C S.A lut d/dds b q

ACTION STATEMENTS (Continued Ms, or ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the ino erable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare he associated valve inoperable and take the ACTION required by ecification 3.7.1.5.

ACTION 25 - With the number of OPERABLE ch nels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within dk 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 hours for surveillance testing per Specification 4.3.2.1 provid the other channel is OPERABLE.

y 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 initiateandmaintainoperationofthegntrolRoomEmergency l

Filtration System in the Emergency mode ACTION 27 - a)

With one channel inoperable in a unit, restore the inoperable 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 initiate and maintain operation of one Control Room F sergency Filtration System (CREFS)g*n the unaffected unit in the l

i emergency mode b)

With one channel inop e 51 in each unit, restore each inoperable channel to 0F T ABLE status within 7 days OR within the next 6 hourt itiateandmaintaig*operationof one CREFS in each un i

the emeroc cy mode l

i c)

With two channels inoperable 'a

. unit, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either 1) initiate and maintain operation of the two CREFS in the unaffected unit

OR 2) initiate and maintain g

operation of one 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 the unit with only one channel inoperable *.

l 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 two CREFS in the emergency mode *.

l ACTION 28 - a)

With one channel inoperable in a unit, restore the inoperable 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) initiateandmgntainoperationofoneCREFSinthe ergency mode

' ACTiotJ 2.9 -

See Ireea l

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

The provisions of Specification 3.0.4 are not applicable to either unit.

V0GTLE UNITS - 1 & 2 3/4 3-27 AMENDMENT NO.26 (UNIT 1)

AMENDMENT NO.7 (UNIT 2)

i 1

4

~

J Insert 1 ACTION 29 - 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 i

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 j

surveillance testing of other channels per Specification i

4.3.2.1.

j i

i s

?

t I

o t

E n

I i

~

f r

i t

[

t L

TABLE 4.3-2 6

EI ENGINEERED SArETY FEATURES ACTUATION SYSTEM INSie!UMENTATION II SURVEILLANCE HEQUIREMENIS C

di TRIP UI ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR M'ICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE e-FUNCTIONAL UNIT CHECK CAtIBRATION TEST TEST LOGIC TEST TEST TEST 15 REQUIRED co

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, Containment Ventilation Isolation, and

,g Auxiliary Feedwater Motor-driven Pumps).

y

a. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3,4 i

E?

b. Automatic Actuation N.A.

N.A.

M(1)

Q 1,2,3,4 Logic and Actuation

.i Relays If2NT4**

c. Containment Pressure-S R

/Q N.A.

N.A.

High-1* (PI-0934, PI-0935,PI-0936)

d. Pressurizer Pressure-S R

Jt'd2 N.A.

N.A.

IT Et*35#

Low (PI-0455A,3&C, PI-0456 & PI-0156A, PI-0457 & PI-0457A, PI-0458 & PI-0458A)

See Specification 4.3.3.6 m.

N>

M

-.4.

TABLE 4.3-2 (Continued) 8 h

ENGINEERED SAFFTY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVLILLANCE REQUIREMLNIS c

TRIP MODES ANALOG ACTUATING CHANNEL DEVICE MASTER SLAVE FOR WHICH v'

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

1. (Continued)

e. Steam Line 5

R M

N.A.

If2 3

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) w A

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)

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

c. Containment Pressure-S R

gQ N.A.

N.A.

f,Y 4

Nigh-3* (PI-0934, PI-0935, PI-0936, PI-0937)

3. Containment Isolation

a. Phase "A" Isolation

1) Manual Initiation N.A.

H.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) Automatic Actuation N.A.

N.A.

M(1)

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

See Specification 4.3.3.6.

i

r I

TABLE 4.3-2 (Continued) e d

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION m

SURVEILLANCE RLQUIREMENTS E

TRIP y

ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHisa CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE e-FUNCTIONAL UNIT CHECK CALIBRATION IEST TEST LOGIC TEST TEST TEST 15 REQUIRED ro

4. Steam 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

gh N.A.

N.A.

M2 N

3 R

High-2* (PI-0934, PI-0935, PI-0936) w NNN h

N.A.

I 2 3 h

d. Steam Line 5

R Pressure-Low

li (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 l

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

)(Q N.A.

N.A.

3

e. Steam Line Pressure-S R

Negative Rate-High*

[

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 i

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)

See Specification.4.3.3.6 f

m.

_m._,,,

.. m

...m.

m

...,_m,_._,-_,,,m_,_,_

r.

.,m,m..,,.,m.m,_,,,,~,_,

TABLE 4.3-2 (Continued) 5 S

ENGINEERED SAIE1Y FEATURES ACTUATION SYSTEM INSi!.HENTATION EI SURVLll{hWCE REQUIREMLNIS E

TRIP d

ANALOG ACTUATING MODES CHANNEL OEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE e-FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

~

5. Turbine Trip and feedwater Isolation

a. Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2 Logic and Actuation Relays

b. Low RCS Tavg Coincident with u,;;

Reactor Trip

S R

M N.A.

N.A.

1, 1.

Low RCS T,yg 8

2.

Reactor Trip, P-4 See Functional Unit 9.b. for P-4 Surveillance requirements.

N.A.

1 2*8"

,)('dh

c. Steam Generator S

R Water Level-High-High** (P-14)

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 LI-C517 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) d.

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

Feedwater isolation only.

Turbine trip occurs on reactor trip.

- See Specification 4.3.3.6 N

M W

TABLE 4.3-2 (Continued) 1 yo h3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION en SURVEILLANCE REQUIREMENIS E

TRIP

~*

UI ANALOG ACTUATING M00ES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE c'

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

6.

Auxiliary Feedwater

a. Automatic Actuation N.A.

N.A N.A.

N. A.

M(1)

N(1)

Q 1,2,3 Logic and Actuation Relays

b. Steam Generator Water Level-Low-Low *

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 y

LI-0517 LI-0527 LI-0537 LI-0547 f:

LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554) 1)- Start Motor-Driven Pumps S

R M' G2 N.A.

N.A.

N.A M.A

2) Start Turbine Driven f(ggZ", 3 Pump 5

R

)('(Q N.A.

N.A.

N.A N.A

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

Motor-Driven Pumps

d. loss of or Degraded N.A.

R

)(d2 N.A.

N.A.

M.A 1,2,3 4.16 kV ESF Bus Voltage

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

N.A.

R N.A.

N.A.

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

f. Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3

See Specification 4.3.3.6

TABLE 4.3-2 (Continued)

.o h}

ENGINEERED SAFE 1Y FEATURES ACTUATION SYSTEM INSTRui1ENTATION SURVLILLANCE REQUIREMENIS C

[}

TRIP m

ANALOG ACTUATING MODES CllANNEL DEVICE MASTER SLAVE FOR WHICN CllANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

~

p" FUNCTIONAL UNIT CllECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

~

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

b. RWST Level-Low-Low

5 R

M N.A.

N.A.

N.A f$2T*ll4*

Coincident With Safety t*

Injection (LI-0990A&B, LI-0991A&B,

}{

LI-0992A, LI-0993A) 8.

Loss of Power to 4.16 kV ESF Bus a.

4.16 kV ESF Bus N.A.

R M

N.A.

1,2,3.4 Undervoltage-Loss of Voltage b.

4.16 kV ESF Bus N.A.

R M

N.A.

1, 2, 3, 4 Undervi>1 tage-Degraded Voltage

See Specification 4.3.3.6 4

4 er um 2

=

,w

- - -, - ~-

mn.-,

=

~

n n

TABLE 4.3-2 (Continued)

o ENGINEERED SAFETY FEATURES ACTUATION SYSTE'1 INSTRUMENTATION SVRVEILLANCE RLQUIREMENTS r"

E TRIP y

ANALOG ACTUATING MODES v'

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 ro 9.

Engineered Safety i

Features Actuation System Interlocks ph N.A.

N.A.

N. A.

N.A.

I d

a. Pressurizer N.A.

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

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

Reactor Trip, P-4 N.A.

N.A.

R N.A.

N.A.

1,2,3 0 10.

Control Room Emergency Filtration System Actuation a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

Either Unit in 1, 2, 3, 4, 5#, 6#

b.

Automatic Actuation Either Unit in Logic and Actuation Relays N.A.

N.A.

M(1)

N.A.

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

1

0uring movement of irradiated fuel or movement of loads over irradiated fuel.

c

a.,,,

,, ~, - -

TABLE 4.3-2 (Continued) h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMfNTATION SURVLILLANCE RLQUIRLMLNIS m

E TRIP d

ANALOG ACTUATING MODES e

CHANNEL DEVICE MASTER SLAVE FOR WillCH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE w

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 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 M

N.A.

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

(RE-12116,RE-12117)

$ 11.

Fuel Handling Building Post Accident Ventilation Actuation w

g (Common System) a.

Manual Initiation N.A.

N. A.

N.A.

R N.A.

N.A.

(2) b.

Fuel Handling S

R M

N.A.

N. A.

(2)

Building Exhaust Duct Radiation Signal j

(ARE-2532 A&B ARE-2533 A&B) c.

Automatic M.A.

N.A.

M(1)

N. A.

N.A.

(2)

Actuation logic and Actuation Relays TABLE NOTATION (1) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

1 (2) Whenever irradiated fuel is in either storage pool.

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

$# 7)ns $dncbon rnae bc h bCSb fY jf Jddn ShdemeM qu5 passe / for Surve$czntC l

cmenh. ** met-

TABLE 3.3-4 RAO'IATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS E

b NINIMUM d

CHANNELS CHANNELS APPLICABLE ALARM / TRIP FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION w

1.

Containment e.

a. Containment Area (High Range) 1 See Table l',

2, 3, 4 100 R/hr See l

(RE-0005, RE-0006) 3.3-8 Table 3.3-8 4

b. RCS Leakage Detection

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

1,2,3,4 5 2 x back-Ef30 ground t'

2) Particulate Activity 1

1 1,2,3,4

< 2 x back-jW 3 0 (RE-2562A) ground C

2.

Containment Ventilation 1

2 1, 2, 3, 4, -See See a

Table 3.3-3 Table 3.3-2 6

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

Gaseous Activity (RE-2565C) l Particulate Activity (RE-2565A)

Iodine Activity (RE-25658) kk 3.

Control Room Air Intake oaIk (RE-12116,RE-12117)

Either Unit in 1

2 1,2,3,4 See See 2m 0

b

.E.E 5,6 Table 3.3-3 Table 3.3-2

=

99

= =_

W&

2

I C

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.

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

ACTION STATEMENTS r

ACTION)$'-

With the number of OPERABLE Channels less than the Miniaua

3c)

Channels OPERABLE requirement, satisfy the ACTION requirements of Specification 3.4.6.1.

e d

4 V0GTLE UNITS - 1 & 2 3/4 3-47

TABLE 3.3-8 o

S ACCIDENT MONITORING INSTRUMENTATION "m

TOTAL MINIMUM e5 NO. OF CHANNELS d

INSTRUMENT CilANNEL}

OPERABLE ACTION

[

1.

Reactor Coolant Pressure (Wide Range) 4 1

JIJ7 (Loop 408, 418, 428, & 438) 2.

Reactor Coolant System Thot (Wide Range) 1/ loop 1/ loop J[34

~

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

Reactor Coolant System Tcold (Wide Range) 1/ loop 1/ loop J2' Sf (Loop 4138, 4238, 4338 & 4438) 1:

4.

SG Water level (Wide Range) 1/SG 1/SG

34 -

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

SG Water Level (Narrow Range) 4/SG 1/SG JVg7 4-(Loop 517, 518, 519, 527, 528, 529, 537, 538, 539, 547, 548, 549, 551, 552, 553, 554)

[gf 6.

Pressurizer Level 3

1 (Loop 459, 460, 461) gg 7.

Containment Pressure 4

1

)(J7 gg (Loop 934, 935, 936, 937) 4 oo sh 8.

Steamline Pressure 3/stm. line 1/stm. line g3/

(Loop 514, 515, 516, 524, 525, 526, 534, 535, 536, 544, 3g 545 & 546) bb 9.

RWST Level 4

1 Er37 gg (Loop 990, 991, 992 & 993)

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

JV 82l (Loop 7777 & 7789)

NN

[fg l

11. Containment Water Level (Wide Range) 2 1

(Loop 0764 & 0765) i i

TABLE 3.3-8 (Continued) y O

h ACCIDENT MONITORING INSTRUMENTATION m

c TOTAL MINIMUM 5

NO OF CHANNELS d

INSTRUMENT CHANNELS OPERABLE ACTION e

w 12.

Condensate Storage Tank Level 2/ tank 1/ tank Jfa 'i2-l e

(Loop 5101, 5111, 5104 & 5116) ro

13. Auxiliary Feedwater Flov 2/ feed line 1/ feed line

,31a32.l (Loop 5152, 15152, 5153, 15153, 5151, 15151, 5150 & 15150) 14.

Containment Radiation Level (High Range) 2 1

)( 35~

(Loop 0005 & 0006)

15. Steamline Radiation Monitor 1/stm. line 1/stm. line

,3f 3f

{

(Loop 13119, 13120, 13121 & 13122)

{

16.

Core Exit Thermocouples 4/ quad / train 2/ quad / train g 7I o

17.

Reactor Coolant System Subcooling 2

1 31r 3Ll

18. Neutron Flux (Extended Range) 2 1

,3 M J2-l (Loop 13135A & 13135B) 19.

RVLIS 2

1 gI EE EE

20. Containment Hydrogen Concentration 2

1 ptf33 l

]

j$

(Loop 12979 & 12980)

x::m

j

21. Containment Pressure (Extended Range) 2 1

JasJZ-l y%

(Loop 10942 & 10943)

{ }

22.

Containment Isolation Valve Position Indication

1/ valve 1/ valve IJU EE

" Applicable for containment isolation valve position indication designated as post-accident monitoring instru-00 mentation (containment isolation valves which receive containment isolation Phase A or containment ventilation' isolation signals).

.~

TABLE 3.3-8'(Continued)

ACTION STATEMENTS ACTION)6

- a.

With the number of OPERABLE channels one less than the Total 31 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 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 Channels OPERABLE requirement, restore at least one 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 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.

ACTION ptr - a.

With the number of OPERABLE channels one less than the Total

(

g Number of Channels requirement, restore 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 , b.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, restore at least one inoperable channel to 0PERABLE 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.

c.

ACTION S M - a.

With the number of OPERABLE channels less than the Total g3 Number of Channels requirement, comply with the provisions of Specification 3.6.4.1.

b.

The provisions of Specification 3.0.4 are not applicable.

j ACTION FI With the number of OPERABLE channels less than the Minin,um Chan-g nels OPERABLE requirement, restore at least one inoperable chan-nel 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.

ACTIONff With the number of OPERABLE channels less than the Minimum 3,f 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 prep re and submit a Special Report to the Commission, pursuant to Sp::ci-fication 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 Specifica-tion 3.0.4 are not applicable.

V0GTLE UNITS - 1 & 2 3/4 3-61 AMENDMENT NO.27 (UNIT 1)

AMENDMENT NO.8 (UNIT 2)

l TABLE 3.3-8 (Continued)

ACTION STATEMENTS ou 33a.

y ACTION)( -

With the iumber off0PERABLE channels less than the required rtum-ber of channels orfthe Minimum Channels OPERABLE requirement, restore tme inoperable channel (s) to OPERABLE status as per Action 31a e or 31ert 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 in-operability, and the plans and schedule for restoring the chan-nels to OPERABLE status. The provisions of Specification 3.0.4 are not applicable.*

ACTION

- 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 f

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.

ACT10N)6-With the number of OPERABLE channels less than the Minimum

]

Channels OPERABLE requirement, comply with the provisions of l

Specification 3.6.3. for an inoperable containment isolation valve.

l l

32.

Action Statement / applies to the first fuel cycle only. Action Statement ) V I

is applicable thereafter.

l l

V0GTLE UNITS - 1 & 2 3/4 3-62 AMENDMENT NO.27 (UNIT 1)

AMENDMENT NO.8 (UNIT 2)

o.nd 3/4.3 INSTRUMENTATION

(

BASES 3/4.3.1 and 3/4.3.2 REACTOR TRI SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATIOy The OPERABILITY of the Re ctor Trip System and the Engineered Safety i

Features Actuation System ins rumentation and interlocks ensures:

(1) the associated ACTION and/or Rea or trip will be initiated when the parameter b

monitored by each channel o combination thereof reaches its Setpoint (2) t Sg

1 specified coincidence logic Q sufficient redundancy is maintained to p it a channel to be out-of-service for testing or maintenance consistent wi main-taining an appropriate level of reliability % sufficient system functional of the Reactor Pr:t::t hr and Engi-neered Safety Features instrumentation, and capability is availabl from divey,se para eters.(3) l

}letktion Sg5 em l

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 these 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 capability.

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

Surveillance intervals and out of ser-vice times were determined based upon maintaining an appropriate level of reliability of the Reactor Protection System and Engineered Safety.Featurec agf instrumentation.

The NRC Safety Evaluation Reportsfor WCAP-102716es provided svy/Q in + letter 5 dated February 21,1985'G.Rous Mec) e. s (NRC) to J. J. Sheppard from C. O. Thoma (WDG-GP) } FebnAr3 n 190s from C.

t af,

K.4. /Vedon (wos); ea on o

AprilJo,tsso k C.S.derri 6 C. X Gc er riy,

The Engineered Safety Features Actuation System Instrumentation Trip 5et-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" 5etpoint 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 l

for determining the OPERABILITY of a channel when its Trip 5etpoint is found l

to exceed the Allowable Value.

The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and l

sensor components in conjunction with a statistical combination of the other entertainties of the instrumentation to measure the process variable and the uncertainties in calibrating the instrumentation.

In Equation 2.2rl, 2 + R + 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 i

i I

i i

l WCAP-13377, Revision 2 (Non-Proprietary)

I

ML20034G277

Text

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