Text

Amend 60 to License DPR-71,modifying Tech Specs to Apply New Analog Instrumentation
	ML20083D729
Person / Time
Site:	Brunswick
Issue date:	12/12/1983
From:	Vassallo D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20083D731	List: ML20083D729; ML20083D733;
References
	DPR-71-A-060 NUDOCS 8312280237
	Download: ML20083D729 (35)
	v • d • e

J UNITED STATES j]

NUCLEAR REGULATORY COMMISSION qC WASHINGTON, D. C. 20555

%.... /

+

CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC r'LANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-71 1.

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

A.- The application for amendment by Carolina Power & Light Company (the licensee) dated January 26, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I;

'B.

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

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications'as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:

r312280237 831212 DR ADOCK 0500032

2.

Technical Specificatidns The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION omenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 12, 1983 i

t

ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. DPR-71

~

DOCKET NO. 50-325 Revise the Appendix A Technical Sepcifications as follows:

Remove Insert 2-4 2-4 2-5 2-5 3/4 3-3 3/4 3-3 3/4 3-6a 3/4 3-6a 3/4 3-8 3/4 3-8 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-14a 3/4 3-15 3/4 3-15 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-22 3/4 3-22 3/4 3-23' 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-24a 3/4 3-24a 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-29a 3/4 3-29a 3/4 3 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-32a 3/4 3-32a 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-35a 3/4 3-35a 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-38a 3/4 3-38a

to TABLE 2.2.1-1 en REACTOR PROTECTION SYSTEM INSTRIMENTATION SETPOINTS W

I ALLOWABLE FUNCTIONAL UNIT AND INSTRIMENT NINBER TRIP SETPOINT VALUES 1.

Intennediate Range Monitor, Neutron Flux - High(1)

< 120 divisions of full scale

< 120 divisions

( C51-IRM-K601 A, B, C, D, E, F,G,II) of full. scale 2.

Average Power Range Monitor

( CS I-APRM-CH. A, B,C, D, E, F)

Neutron Flux - High, 15%(2)

< 15% of RATED THERMAL POWER

< 15% of RATED a.

THERMAL POWER b.

Flow-Biased Neutron Flux - High(3)(4)

< (0.66 W + 54%)

-< (0.66 W +-54%)

u Fixed Neutron Flux - liigh(4) f 120% of RATED THERMAL POWER-1 120% of RATED c.

THERMAL POWER 3.

Reactor Vessel Steam Dome Pressure - High i 1045 psig

< 1045 psig

( B21-PTM-N 02 3A-1, B-1, C-1, D-1 )

4.

Reactor Vessel Water Level - Low, Level 1

~> +162.5 inches *

> +162.5 inches *

( B 21-LTti-N017 A-1, B-1,C-1, D-1 )

~

5.

Main Steam Line Isolation Valve - Closure (5)

< 10% closed

( B 21-F022A, B., C, D; B21-F028A,B,C,D) 6.

Main Steam Line Radiation - liigh j 3 x full power background 13.5 x f ull power

( D12-RM-K603 A, B, C, D) background 7.

Dryvell Pressure - liigh 1 2 psig i 2 psig

( C71 -PTM-N002A-1, B-1, C-1, D-1 )

8.

Scram Discharge Volume Water Level.- liigh 1109 gallons 1109 gallons g

( Cl 1-LSil-N013A, B,C, D) 8

N

.T_A_Bl.E 2. 2.1-1 (Continued) 5g REACTOR PROTECTION SYSTEM INSTRilitEfffATION SETPOINTS 9

AI.LOWABI.E

_F_i_l!1_C_T_IONAI. IJ_illT...A.t..ll.t 'INSTRiftlENT NIIMHER TRIP SETPOINT VAI.llE_S g

N Stop Valve - Closure (6)

< 10% closed

< 10% closed 9.

Turbine e

(EllC-SVOS-I X,2X,3X 4X) 10 Turbine Control Valve Fast gsure, Control 011 Pressure - Iow

> 500 psig

-> 500 psig (EllC-PSI.- 17 56,17 57,17 58,1759 )

~

4 lb Us t

t iv N

8a 8

4

m.

O TABLE 3.3.1-1 (Continued)

n REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIHLH NIMBER y

OPERATIONAL' OPERABLE CHANNELS 4

r.

FUNCTIONAL. UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)

ACTION

7. Drywell Pressure - liigh

.1, 2(*)

2 6

( C71-PT-N002A,B,C, D)

( C71-PTM-N 002A-1, B-1,0-1, Dr l)

\\

)

8. Scram Discharge Volume Water Level -

High

, 1, 2, 5(f) 2 5

(Cl l-LSil-N013A, B,C, D)

I ki

9. Turbine Stop Valve Closure 1(g) 4 8

( EliC-SVOS-l X,2X,3X,4X) v>

4

10. Turbine Control Valve Fast Closure, Control Oil Pressure - Low 1(8) 2 6

( EllC-PSL-1756,1757,1758,1759)

11. Reactor Mode Switch in Shutdown Position 1,2,3,4,5 l

9 (C71A-51)

12. Manual Scram I,2,3,4,5 1

10 i

( U71-A-S 3A., B)

'Ei 8

, B-a n

.E 1

h TABLE 3.3.'l-2 (Continued)

REACTOR PROTECTION SYSTEM RESPONSE TIMES a

a RESPONSE TIME g

FUNCTIONAL UNIT AND INSTRINENT NIMBER (Seconds)

U 7..

Drywell Pressure - High NA'

( C71-PT-N002 A,B,C, D)

( C71-PTM-N 002A-1, B-1, C-1, D-1 )

8.

Sciram Discharge Volume Water Level - High NA

( Cl l-LSH-N013 A, B, C, D).

9.

'Ibrbine Stop Valve - Closure

-< 0.06 (EHC-SVOS-lX,2X,3X,4X)

10. Turbine Control. Valve Fast Closure,

< 0.08 w2 Control Oil Pressure - Low

. (EHC-PSL-1756,1757,1758,1759)

!!. Reactor Mode ' Switch in Shutdown Position NA (C71A-SI)

12. Manual Scram NA (C71A-S3A,B)

Neutron detectors are exempt f rom response time testing.

Response time shall be measured from detector output or from the input of the first. electronic component in the channel.

N 8

it a

n

i V

TABLE 4.3.1-1 (Continued) m

=

REACTOR PROTECTION SYSTEM INSTRIMENTATION SURVEILLANCE REQUIREMENTS-CHANNEL OPERATIONAL FUNCTIONAL UNIT _

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH-y AND INSTRINENT NIMBER CHE(X TEST CALIBRATION (a)

SURVEILLANCE REQUIRED w

5. Main Steam Line Isolation Valve -

- NA H

R(h) g Closure 4

(B21-F0 22A,B,C,D and B21-F028 A, B,C, D)

U)

6.. Main Steam Line Radiation - High S

M(I)

R 1, 2

( D12-RM-K603A,B,C, D)

7. Drywell Pressure - liigh

( C71-PT-N002A, B,C,D)

NA( )

NA R(1) 1, 2 u

4

)

( C71-PTM-N002 A-1, B-1,C-1, D-1)

D M

M 1, 2

8. Scram Discharge Volume Water Level - liigh NA Q

R 1, 2,. 5

( Cl 1-LSil-N013A,B,C,D)

9. Turbine Stop Valve - Closure NA M

R(h) 1 (EllC-SVOS-lX 2X,3X,4X)

10. Turbine Control Valve Fast Closure, Control Oil Pressure -

Low NA M

R 1

( EllC-PSL-1756,1757,1758,1759)

11. Reactor Mode Switch in Shutdown NA' R

NA 1,2,3,4,5 Position (C71A-SI) rt

12. Manual Scram NA Q

NA 1,2,3,4,5 (C71A-S3A,B) 8 i

T L3 TAtil.E 3. 3. 2-1 un Ej ISOLATION ACTilAff0H INSTRUNENTATION n

VALVE CROUPS HIN1Hl1H IJUHilER

- APPLICAHl.E OPCRATEI) BY OPERAlli.E CllANNELS OPERATIONAL

.-l -

.Tu.l.l'. I?t.i. tlc _T_.f 011. _A.lli)..-INSTRiltlENT NilHilER SIGNAI.(a)

PER TRIP SYSTEH(la)(c)_

CON.DITION-ACTION'

),

1.

PRillARY CON TAI!JIIENT 'IS01.ATION Reactor Vessel Wat.er level -

1.

'Inu, level 1 2,6,7,8 2

- 1,,2, 3

~ 20

' (ll21 -1.T-N017 A-1, B-1, C-1,0- 1 ) *

( B 2 ' -llrH-N017 A-1, ll-1, C-1, D-1 )

2.

l.ow, Icvel 2 1, 3 2

- 1, 2, 3 20 (ll21 -1.T-H024 A-1,II-1, ant!

Il21 -LT-NO2 5 A-1, Il-1 )

' (ll21-LT!!-NO24 A-l. ll-l anci c

1521 -tirti-NO2 5 A-I,11- ! )

b.

larywell l'ressure - liigh 2, 6, 7 2

1, 2, 3 20

( G 7 l - PT-r:002 A,11,C, D)

( C 71 - PT: t-fla02 A-1,8-l, C-1, D-1 ).

c.

liain Steam 1.ina I.

Raillat ion - liigh (<!)

I 2

1, 2, 3 21 (012-1:tl-K601A,II C D) 2.

Pressure - luu I

2 1

22 (il21 -PT-fl015A,II,C, D)

( li 21 - P r:1-No l 5 A-1, Il-1, C-1, 0- 1 )

').

13t ow - 11181 1

2/line 1

22 1

( 1121 -PDT-flO06 A, il,C, D;

!!21 -l> DT-t1007 A,11, C,1);

li21 -l'DT-H008A, li,C, D ;

Il 21 -l>DT-NOO9A, H. C, D)

( ll21 - P11T!I-t1006 A-1, Il-1, C-1, 0- 1 ;

1121 -l'l)YH-H00 7 A-l,11-I, C- !, D-1 ;

1121 -- l'OT:1-NOO 8 A- !, lt-I, C-I, D-1 ;

1121 ' l*D fil-fl009A-I,11-I, C-I, D-I )

TABl.E 3.3.2-1 (Continued) iA

,"j IS01.ATION ACTilATION IllSTRi! MENTATION o

val.VE GROUPS HINIHilt! NUHilER APPL.ICARLE OPERATED BY OPERABl.E CilANNEl.S OPERATIONAL TRIP l'llNCTION AND lilSTRUllENT NUMBER SIGNAL.(a)

PER TRIP SYSTEH(b)(c)

CONDITION,_

_ ACTION i

l'RillARY CON TAIN!!ENT (SOI.AT[0N (Continue <!)

l it,

ll.In Steaa 1.ine Tunnel I2 ")

I, 2, 3 21 Temperature - liigh

( ll21 -TS-flu l DA, B, C, D ;

1121-TS-flul l A B C,1);

B 21 -TS-Il012 A, B,C, D ;

1521 -TS-f1013 A, li, C, D) c, u.

Contlenser vacuum - low I

2 1, 2(f) 21 i;

(ll21 - PT-NO S6 A,II,C. D) 3,

(!!21 - PTri-fl0 56A-I, B-t, C-I, D-I )

f,'

l'.

Turbine 11ul I. ling Area Temperature - liigli 1

4(*)

1, 2, 3 21

( ll21 -TS-12 2 5 A, II,C, D; 1121 -TS-3 226 A, il, C, D ;

il21 -TS-322 7 A,II.C. D ;

I!21 - rS-32 28A, ll,C, D ;

il21 -TS-12 29 A, II,C, D ;

il21 -TS-3 2 30A,11,C, D ;

ll21 --TS-12 31 A,il,C,0; 1121 -TS-3212 A, II, C, D) i i

e 6

40 q

bbl.E 3.3.2-1 (Continued)

' iA,r ISOLATION ACTilATION INSTRIJHENTATION

-1 0

VALVE CROllPS HINIMUH NilHBER APPLICABI.E OPERATED !!Y OPERAlli.E CilANNELS.

OPERATIONAL.

'f TRil' FililGrIOri ANI) IllSTRUtlENT NUtinER SIGNAL.(a )

PER TRIP SYSTEN(b)(c) CONDITION ACTIOtt

l1 le4 2.

SECollDAt Y CONTAItillENT ISOIAT[0N a.

Reactor Unil. ling Exhaust Radiation - liigh 6

1 1, 2, 3, 5, and* 23

( D 12-l:H-fl010A, B)

I h.

Drywell Preaanre - liigli 2,6,7 2

1, 2, 3 23

( C71 -PT-!1002A, B,C, D)

( C 71 -l'Til-Il002 A-1, B-1, C-1, D-1 )

c.

Reactor Vessel llater level -

I.o w, i.e ve l 2 1, 3 2

1, 2, 3 23

!'.5

( B21-l/f-fl024 A-I, B-1 and

] 6,a 1121 -1.T-IlO2 5 A- !,11-1 )

(1121 -l/rf f -11024 A-I,11-t.ind u

I!21 -1.Tti--Il02 5 A-1, B-1 )

3.

I:EACTOR LlATER Cf.EAtillP SYSTEH ISOLATION a.

A Flua - llidh 3

1 1, 2, 3 24 (C31 ilFS-fl603-I A,l B) h.

Area Teinperatore - liigli 3

2 1, 2, 3

24

( C 31 - f S-Il600A,11,C. D. E. F) c.

Area Vent i l.it ion A Temp. - liigh 3

2 1, 2, 3

24 g,

( c 11 -TS -n602 A, is, C, D, E, v )

.h IE) a.

S I.CS Initiation 3

NA 1, 2, 3 24.

g (C's l A-S I )

f1 Heaet.>r Vessel Water Invel -

U l.o u, i c v. : 1 2 1,

3 2

1, 2, 3 24

( B 21 - 1.T-flO 2 's A-I,B-I and o

1121 -1.T-IlO2') A-1, ll-1 )

(lil1 -l.Til-t1024 A-I.11-1 and ll21-lllti 11025 A-1,ll-1 )

\\

9

os g!

pliLE 3.3.2-1 (Continued) i h

ISOLATION ACTUATION IllSTRUllENTATION t,

VALVE GROUPS HINIHUN NilHBER APPLICABLE OPERATED BY OPERAlilE CilANNELS OPERATIONAL h

Td l P l',til flotl AllD INSTRUMEllr NUMBER SIGNAI.(a )

PER TRIP SYSTEM (b)(c) CONDITION.

ACT M ei s-4.

CORK STAllutiY C001.ING SYSTEMS IS01.ATION a.

liigh l'ressua e Coolant Injection System Isolation 1.

IIPCI Steam I.ine Flow - liigh 4

1 1, 2, 3 25 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-il004-2; E41-PDTS-N005-2)

{

2.

IIPCI Steam Supply Pressure - low A

2 l ', 2,

't 25 (E4l-PSL-N001A,B,C,D) da 3.

IIPCI St eaut Line Tunnel Temper.iture - lligh 4

2 1, 2, 3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E4l-TS-3318; E 'e l -TS-33 54 ;

E41-TS-3488; Eil-TS-3439) 4.

Ilus P..wer Honitor NA(h) 1/ bus I, 2, 3 26 6,

(E41-K55 anil E41-K56) b g

5.

IIPCI rurbine Exhaust g

Diaphranga Pressure - Iligh 4

2 1, 2, 3

25

( E41 -PSil-N012 A, B, C, 0) n N

6.

IIPCI Steam 1.ine Ambient l

Temper.iture - liigh 4

1 1, 2, 3 25 C

( Ei i-TS -116010, D)

g.

.TABIE 3.3.2-1 ' (continued) t3l'!

ISOLATION ACTilATION INSTRilHENTATION T4 b"

VALVE CROUPS HINIHUH'NUHHER APPLICARI.E '

t OPERATED BY OPERARLE CilANNELS OPERATIONAL

[j TRIP FUNCTION AND INSTRUMENT NUHHER SIGNAL.(a )

PER TRIP SYSTEH(b)(c) CONDITION

' ACTION N

7.

IIPCI Steam Line Area A Temp. -

g lii gli 4

1-1, 2, 3 25 l

(E51,lTS-N604C,0)_

8.

Emergency Area Cooler Temperature - liigli 4

1 1, 2, 3 25 l

(E41-TS-N602A,B) li.

Reactor Core Isolation Cooling System Isolation R

I.

RCIC Steam I.ine Flow - liigh 5

1 1, 2, 3 25 o

(E51-PDT-N017;

.y E51-PDT-N018 )

h (E51-PDTS-N017-2; E51-PDTS-N018-2) 2.

RCIC Steam Supply Pressure - low 5

2 1, 2, 3 23 (E51-PS-N019A,B,C,D) 3.

RCIC Steam 1.ine Tunnel Temperature

- liigh 5

2 1,2,3 25 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322;

'h E51-TS-3323; u

E51-TS-3355; h

E51-TS-3487)

N 4.

Ilus P.swer Honi tor NA (I')

1/ bus 1, 2, 3 26 y

(ESI-K42 anil E51-K43) 8

1 43

o TAlll.E 3.3.2-1 (Continued)

Uid gj IS01.ATION ACTilATION INSTRUMENTATION' O

val.VE GRollPS HINIHilH NUMBER APPL.;CABl.E 8

UPEl(ATEI) BY OPERAllLE CilANNELS.

OPERATIONAL i

TRIP l'IlNCTION AND INSTRtlHENT HiltillER S ICNAI.(a )

PER TRIP SYSTEM (b)(c)-

CONDITION ACTION ei 5.

RCIC Torbine Exinaust ~ Diaphragen Pressure - liigh 5

2_

1, 2, 3 25 (E51 -l>S-fl012 A,ll,C, D) 6.

RCIC Steain Line Aiabient Temp -

liigh 5

1 1, 2, 3.

'25 l

(E51-TS-N603A,ll)

/.

"RCIC Stearn 1.ine Area A Temp - liigh 5 1

1, 2, 3 25 l

(E 51 -dTS-N604 A,ls) if M.

RCIC E.p:1pinent Rooin Ainblent Temp - llidh 5

1 1, 2, 3 25 l

Y (E51-TS-N602A,8)

^

9.

RCIC E.guipinent Rooin A Tesap - liigh 5'

i 1, 2, 3

25 l

(E51 ilTS-N601 A,il) 5.

SilHIDouri COOLING SYSTEH ISOLATION a.

Reactor Vesuel Water level -

1.o w, level 1 2, 6, 7, 8 2

1, 2, 3 27

( Is 21 -1.T-flu l 7 A-1, ll-1, C-1, D-1 )

( 15 21 - 1l111-11017h - 1,15-1, C-1,0- 1 )

h.

Reactor Stuaia lune Pressure-7, 8 II llidh l

1, 2, 3

27 (ll32-PS-flu l H A,ll) ll 0

m O

e

- 11 TAllt.E 3.3.2-2

'h IS01.ATION ACTilATION INSTRilHEffrATION SETPOINTS iil AI.LOWARI.E

" f j TRIP FiltlCTION Atill itJSTittlHEffr NUHilER TRIP SETPOINT VAI.UE el e4

.l.-

I'dlllARY CONTA!NilEfff ISOLATION a.

React.ur Vessel Water level -

1.

Inw. I.evel I

> + 162.5 inches *

> + 162.5 inclies*

( ll21 - I.Til-N017 A-1, ll-1, C-1, D-1 )

2.

Inu, I. eve l 2

> + 112 inches *

> + 112 inches

4 (1121-l/rtl-NO24 A-l, B-1 and 1121 -lirH-fl02 5A-I,11-I )

.b.

Drywel l Pressu re - liigli

< 2 psig

< 2 psig 7

( C71 - PTil-fl002 A-1, il-1, C-1, D-l )

l c.

fliin Steam 1.i ne y

I.

Rattiat ion - liigh

( 3 x full power background

< 3.5 x full power.

( 012-It:t-l'603 A, II, C, D) background 2.

Piessure - Iou

> 825 psig

> 825 psig (ll21-PTil-fl015A-1,Il-1,C-l D-l) 3.

Flow - llidh

< 140% of rated flou

( ll21 -l'DTil-flOO 6 A-1, B-1, C-1, D-l ;

ll21 - l>lrril-fl007A-1,11- !, C-I, D-I ;

1121 - I'l) fil-flOO3 A- !,11- !, C-I, D-1 ;

Is 21 - PitTH-il009A-1,11-I, C-I, D-1 )

li, n

!3 11 i!!

(1

'o b

o 9

Gbp TAllLE 3.3.2-2 (Continued) d IS01.ATIUti ACTUATION IllSTRUMENTATION SETPOINTS c) y; ALLOWABLE

._ri_t.i.l'. _Fil.ll.Cr_l 0_N.A NI) I_llS_rittillEfff NUtillER '

TRIP SETPOINT VALUE

= - - -

,a "3

l'itlilAltY CONTAlllill:ttr ISOLATION (Continued) t '*

.t.

fl. sin Steam I.ine Tunnel Temperature - liigli

< 200*F

< 200*F (152 l-IS-N010A, B,C, D ;

112 l-TS-NO I I A, B,C, D; 1121 - rS N012 A,11,C, D; il21 -TS-flu l 3 A, li, C, D) e.

Conitenser Vacuum - Iow

> 7 inclies lig vacuum

> 7 inclies Ilg vacuum

( il21 -l'TH-N 05 6 A-1, B-1, C-1, D-1 )

u 2

t.

Turtaine 11oilili ng. Area Temp - Illgli

< 200*F

< 200*F 4

ja (1121 - rS-32 25A, ts,C, D; g

n21-rS-3226A,B,C,D; 1121 - IS-32 2 7 A, II,C,1);

1121 -TS-32 28 A, II,C, D ;

1121-TS-32 29 5, il,C, D ;

1521 - IS-3 2 3tlA,ll, C, D; 1121 -T S-3 2 51 A, B, C, D ;

it 21 -TS-3212 A,1$, C, D) 2.

SECO!1DAltY CONTAltilit?NT ISOLATION a.

Iteactor ilull. ling ICxt aust f,-

Hadiation - 111gli

< 11 mr/hr

< 11 mr/hr (1112-1:ti-ilo 1 OA, B)

-8..

13 14ywell Pres.;ure - liigh

< 2 psig h

( C 71 -I'Til-tJ002 A-I,11-1, C- !, D- ! )

-< 2 psig c.

1:eactor Vessel Water level -

I.a w, level 2 a

( 1121 - I.Til-tJ021 A-I,11-I and

->1

!!2 inclies*

> + 112 inches

1121 -1. I'll-110 2') A-t,11-I )

l so TAlli.E 3.3.2-2 (Continued) 3

~

ISOI.ATION ACTUATION INSTRUMENTATION SETPOINTS R

AI.LollABLE f,.

. Trit'..FilllCTION AND ItiSTRllflEllT NUNilER

-TRIP SETPOINT-

-VAI.IIE 3.

HEAttrOR ligliR Cl.EAlllle SYSTEll' IS01.ATION a.

A Flou - liigh

-< 53 gal / min

-< 53 gal / min (G 31-d FS-fl603-1 A, l B) b.

Area Temperature - liigh

-< 150*F

< 150*F (G 31 -T:1-fl600A, B,C, D, E, F)

~

Area Ventilation Temperature A Temp - liigh

< 50*F

< 50*F c.

(G11 -TS-fl602 A, II, C, D. E, F) d.

SI.CS Ini t tat inn NA NA

(

(C4lA-SI) e.

Reactor Vessel llater level -

g 1.o u, level 2

> + 112 inches *

(1121 -1.Til-!!O2 4 A-I,11-I and

!!21 -1.Trl-!!O2 5 A-!, !!- 1 )

4.

COME S TA!!DilY C001.!!!C SYSTEMS IS01.ATION a.

liigh Pressure Coolant Injection System Isolation l.

IIPCI St eam I.ine Flow - liigh

< 300% of rated flow

( 1541 -l'DTS-flOO4-2 ;

E4I-PDFS-fl005-2) 2.

IIPCI Steam Supply Pressure - Low

> 100 psig

> 100 psig (E41-PSI.-flOOl A,il,C,1))

1.

IIPG l Ste.ua 1.i ne Tunnel Temperature - Iligh

< 200*F

( E4 l - rS-1314 ;

E4l-TS-1315; E41 -TS-3 316 ;

E41-TS-3117;

}.

E41 -TS-1118 ;

E'41 - rS-1154 ;

E41-rS-1418; E41 - rS-3489 )

TAlli.E 3.3.2-2 (Continued) is

'M ISOI.ATION ACTUATION INSTRilHENTATION SETPolNTS' 9

AI.L0liABI.E THir FilNCrlON AllD INSTRUNENT NIIHRER

' TRIP ' SETPOINT_

val.IIE s

8 4.

Ilus Power Monitor NA NA (E41-K55 and E41-K56) 5.

IIPCI Turbine Exhaust Diapiiragm Pressure - Illgli

-< 10 psig

-< 10 psig (E41 -PSil-fl012 A, B,C, D) 1 6.

IIPCI Steam 1.ine Ambient Temp - liigli

-< 200*F

< 200*F (E51-TS-N603C,D) 7.

IIPCI Steam I.ine Area A Temp liigli

-< 50*F

< 50*F (E51-dTS-N604C,D) t,,

8.

Emergency Area Cooler Temp - liigh

< 175*F

< 175"F

'/

(E41-TS-N602A,B)

[3 b.

Huactor Core Isolation Cooling System Isolation 1.

RCIC Steam I.ine Flow - Iltgh

< 300% of rated flow

< 300% of rated flow (E51-PDTS-N017-2; E51-PI)TS-NOI8-2) 2.

HCIC Steam Supply Pressure - Imu

> 50 psig

-> 50 psig (E51-PS-N019A,B,C,D) 1.

RCIC Steam I.ine Tunnel Temp.- liigh

< 175"F

< 175*F (ESI-TS-3319; E51-TS-3320; k

E51-TS-3321; D

E51-TS-3322; h

E51-TS-3123; 3

E51-TS-3355; E51-TS-3487) no 4.

Bus P. wer flani tor h.

NA g

(E51-K42 and E51-K43)

4 TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TU1E

- TRIP FUNCTION AND INSTRUMENT NUMBER

' RESPONSE TIME (Seconds)#

1.

PRUiARY CONTAINMENT ISOLATION a.

Reactor Vessel Water IAvel -

1.

Iow, Level 1

<13 (B21-LT-N017A-1,B-1 C-1,D-1)

~

(B21-LTM-N017A-1,B-1,C-1.D-1) 2.

' Low, Level 2 -

<1.0**

(B21-LT-N024A-1,B-1 and

~

B21-LT-N025A-1,B-1)

(B21-LTM-NO24A-1,B-1 and B21-LTM-N025A-1,B-1) b.

Drywell Pressure - High

<13 (C71-PT-N002A,B,C,D)

~

(C71-PTM-N002A-1,B-1,C-1,D-1) c.

Main Steam Line

<1.0**

1.

Radiation - High*

(D12-RM-K603A,B,C,D) 2.

Pressure - Low

<13 (B21-PT-N015A,B,C,D)

/

~

(P. 21-PT:1-N015 A-1, B-1, C-1, D-1 )

3.

Flow - High

<0.5**

(B 21-PDT-N006A,B,C,D;

~

821-FDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C D)

(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,3-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1) f-d.

Main Steam Line Tunnel Temperature - High

<13

^

(B21-TS-N010A,B,C,D; B21-IS-N011A,B,C,D; B21-TS-N012A,B,C D; B21-IS-N013A,B,C D) e.

Condenser Vacuum - Low

<13 (B21-PT-N056A,B,C,D)

(B21-PTM-N056A-1,B-1,C-1,D-1)

/

i

-3RUNSWICX-UNIT 1 3/l. 3-12 Mendment :h. 60 l

.- ~ - ~

TABLE 3.3.2-3 (Continued) f ISOLATION SYSTEM INSTRIDIENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT nut 9ER.

RESPONSE TDIE (Seconds)#

PRUiARY CONTAINMENT ISOLATION (Continued) f.

Turbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D;

-B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D;-

B21-IS-3230A,B C.D; B21-IS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High*

<13 a..

(D12-RM-N010A,B)

~

b.

Dryvell' Pressure - High

<t3 (C71-PT-N002A,B,C D)

(C71-Pri-N002A-1,B-1,C-1,D-1)

Reactor Vessel Water Level - Low, Level 2

<1.0**

c.

(B21-LT-N024A-1,B-1 and

.B21-LT-N025A-1,B-1)

(321-LTM-N024A-1,B-1 and 32l-LT:1-N025A-1,B-1)

~#

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High

<13 (G31-dFS-N603-1A,lB) b.

_ Area Temperature - High

<l3 (G31-TS-N600A,B,C,D,E,F)

Area Ventilation Temperature AT - High

<13 c.

(G31-TS-N602A,B,C,D,E,F) d.

SLCS Initiation NA

~(CalA-SI)

Reactor Vessel Water Lavel - Inw. Lavel 2

<1.0**

e.

(321-LT-N024 A-1,3-1 and B21-LT-N025 A-1,B-l)

(321-LT:1-NO24 A-1,3-1 and B21-LIM-N025 A-1,3-1) 3RU::SWICK - UNIT 1 3/4 3-23 Amendment :o. 60

TA3LE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TD!E TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TI:1E (Seconds)4 4

CORE STANDBY COOLING SYSTEMS ISOLATION a.

Righ Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High

<13 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-N004-2; E41-PDTS-N005-2) i 2.- HPCI Steam Supply Pressure - Low

<13 (E41-PSL-N001A,B,C,D) 3.

HPCI Steam Line Tunnel Temperature - High j:13 (E41-TS-3314; E41-TS-3315; E41-IS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 1 Bus Power Monitor NA (E41-K55 and E41-K56) 5.

HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N012A,B,C,D) 6.

HPCI Steam Line Ambient Temperature - High NA (E31-TS-N603C,D) 7.

HPCI Steam Line Area NA (E51-dTS-N604C,D) 8.

Emergency Area Cooler Temperature - High NA (E41-TS-602A,B) b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High NA (E51-PDT-N017; E51-PDT-N018)

(E51-PDTS-N017-2:

E51-PDTS-N013-2) 2.

RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,3,C,J) m

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TUIE (Seconds)it

3.. RCIC Steam Line Tunnel Temp - High NA (E51-IS-3319; E51-TS-3320; E51-TS-3321; E51-IS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4.

Bus Power Monitor-NA (E51-K42 and E51-K43) 5.

RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C,D) 6.

RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,8) 7.

RCIC Steam Line Area a Temp - Eigh NA

(E51-dTS-N604A,8) 8.

Emergency Area Cooler Temperature - Righ NA (E51-TS-N602A,B) 9.

RCIC Equipment Room a Temp - Righ NA

-(E51-dTS-N601A,B) 5.

SHUTDOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level

Low, Level i a.

NA

( 821-LT-N017 A-1, B-1, C-1, D-1)

(B21-LIM-N017A-1,B-1,C-1,D-1) b.

Reactor Steam Dome Pressure - High NA (332-PS-N018A,8)

Radiation monitors are exempt f rom response time testing.

Response time shall be measured from detector output or the input of the first electronic component in the channel.

- Isolation actuation instrumentation response ti=e only.

Isolation system instrumentation response time specified for the Tria Function actuating eaca valve group shall be added to isolation time snown ta Iable 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTS:t RESPONSE TIME for each valve.

3RUNSWIC:' - dNIT 1 3/i 3-2ia Amendment No.

60 t _

LJ3y FABl.E 4.3.2-1 id ISOLATION ACTilATIOli INSTRiltYtfrATIOri SIIRVEILLANCE REQllIREllENTS f!

CllAtlNEL OPERATI0tlAL CilANNEL FilHCTIONAI, CilANNEL CONDITIONS !!! WillCil

[j TRIP FilflCT10!J AND INSTRutlENT NUHBER CllECK TEST cal.IBRATION SilRVEll.I.ANCE REQUIREI)

H 1.

l'RIllTRY CorirAIrlilEttr IS01.ATION Reactor Vessel Water lavel -

1.

lesw, t.e ve l 1 (821-1/r-N017A-1 B-1,C-1,D-1) riA(a)

NA R(b) 1, 2, 3

( l!21 -lirt i-N017 A-1, B-1, C-1, D-l )

D H

H 1, 2, 3 2.

Inw, level 2 (821-l.T-fl024A-1, B-1 and I

II')

NA ")

NA R

1121 -I.T-Il02 5 A-1, Il-1 )

1, 2, 3 5'

(l521-1.Tri-NO24 A-1,Il-1 and

'j 1121 -I.Tri-N02 5 A-1, ll-1 )-

D H

H 1, 2, 3 Drywell Pressure - liigli (C 71-PT-flOO2A It,C,D)

NA(a)

NA R(b) 1, 2, 3

( C71 -PTil-r1002 A-1, B-1, C-1,0- 1 )

D H

H 1, 2, 3 c.

tLa1in Steain 1.1 ou I.

Raillat ion - tilgli l)

W R

I, 2, 3

( D 12-Ril-K603 A,II, C,1))

2.

Pressure - Inw (Is 21 -PT-flu l 5 A, ll,C, D)

IJA(")

NA RII')

1 (1121 -l'Tri-flo l S A-I, B-I, C-1, D-t )

l)

H I

g-1.

F1ou - tilgli g

(It 21 -PDT-NOO6A, ll-, C, D ;

NA(")

NA RII')

1

))

1121 -l'DT-t1007A. il, C, D ;

1 il21 - PDT-N008A,II C,l);

il21 - Pl>T-fl009A,11,C,1))

( 1121 -l'DTri-N006 A-I,15-1, C-I, D-1 ;

l)

H H

I ll21 - PDT!!-fl007 A-1, B-1, C-1,0- l ;

1121 -l DTil-NOO8A-I, li-I, C-1, D-I ;

e 1521 -l*DT:1-il00'J A-I,11-I, C-I, D-I )

4-

4 L2 y

TAPLE 4.3.2-1 (Continued) is ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS fl CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL-CONDITIONS IN WilICil d

'rH i { t'llHCriori AND INSTRilHENT NUMBER CllECK TEST CALIBRATION SURVEILI.ANCE REQUIRED

1 l'HillARY CONTAltlilENT ISOI.ATION (Continued)

.l.

ILiin Steam Line Tunnel Tmaperatiere - lli h NA M

R 1, 2, 3 d

( ll21 -TS-N01 DA, B,C, D ;

il21-TS-fl0 l l A, B,C, D; il21 -TS-N012 A, B,C, D ;

il21-TS-flD 13 A, B, C, D)

~

c.

Comleaser V.icuum - Iou h

( il 21 - PT-H056 A, B, C,0)

IIA (a)

NA R(b) 1, 2#

( ll21 -PTil-N05 6 A-1, B-1, C-1, D-1 )

D H

H 1, 2#

f.

Turtaine Bui l< ling Area Temp-liigh NA M.

R 1, 2, 3 j

(B21-TS-3225A,B,C,0; il21 -TS-3226 A,II,C, D ;

il21 -TS '12 27A, B,C, D; j

ll21 -TS-32 28 A,ll,C, D ;

il21 -TS-3229 A, II,C, D; il21-TS-3230A,B,C D; il21-TS '3231 A,B,C,0; il21 -TS-3 2 3 2 A, II, C, D) i o

I 9

!B

11

!i

.n 2

l 1

wp TABI.E 4.3.2-1.(Continued)

{.

. h*

ISOLATION ACTilATION IllSTHilNENTATION SilRVEILLANCE REQllIREHENTS F!

CilANNEL OPERATIONAL CilANNEl.

FUNCTI0liAI.

CllANNEL

- CONDETIONS IN WilICil

. j,, Trit' FullCTiori AND lilSTRIRIEllT NUMBER.

CilECK TEST CALIBRATION SURVEII I.ANCE REQllIRg es 2. SECollDARY CONTAlHilENT ISOI.ATION a.

.Heactor Buliding. Exhaust Radiation - liigh D

H R

1,2,3,5, and *

( DI 2-R!!-Nill DA, B) b.

Drywe1i Pressure - liigh (C 71 -PT-fl002 A, B, C, D)

NA NA R

1, 2, 3

( C 71 -PT!!-N002 A-1, B-1, C-1, D-1 )

D H.

H 1, 2, 3 c.

Reactor Vessel Water level -

,g Inw, level 2 (1121-LT-fl024 A-1,il-1 and NA NA R

1, 2, 3

.g

,a 112 I -1.T-1102 5 A-I, B-I )

(B21-I!rH-11024 A-1,B-1 and I)

H H

1, 2; 3-Il21-I.Til-H025 A-1, B-1) 3.

HEACron WATER Cl.EANilP SYSTEtt IS01.ATION a.

A Flow - tilgh I)

H R

1, 2, 3 (G31 lFS-N603-IA,lB) li.

Area - Tempe rat uru - liigh fla H

R 1, 2, 3 (C 31 -TS-fl600 A, il,C, D, E, F) c.

Area Ventilation A Temp - liigh NA H

R 1, 2, 3

(

(C 11 -TS-fl602 A,is, C, D, E, F) f

.l.

S t.CS InlLiation flA R

NA 1, 2, 3 g

(C41A-SI)

['

c.

Heact.or Vessel Water Icvel -

o I.<,w, level 2 (ll21-lif-IJO24 A-1,Il-1 and flA( 3 )

.NA R(b) 1, 2, 3 g

1121 -I.T-flO25 A-I,11-l')

(1121-1.TiI 11024 A-I,11-I and D

H H

l, 2, 3 1121 -l. Irl-1102 5 A-I,11-I )

m TABLE 4.3.2-1 (Continued)

oD Li ISol.ATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREHENTS Il

[]

CllANNEL

' OPERATIONAL e

CilANNEL FUNCTIONAL CilANNEL CONDITIONS LN WilICll TRIP l>llNCTION'AND INSTRutlENT NUMBER CllECK TEST CALIBRATION SURVEII.f.ANCE REQilIREI) p.

. 4.

_ CORE ST_AN_DilY C00l.ING SYSTEMS ISOI.ATION-g a.

Illgh Pressure Coolant Injection System isolation p 1.

IIPCI Steam Line Flow - liigh (E41-PUT-N004; NA(a)

NA R(b)

I, 2, 3 E41-PDT-N005)

(E41-PDTS-NOO4-2; D

M M

1, 2, 3 E41-PDTS-N005-2) 2.

IIPCI Steam Supply Pressure -

v

}: -

1.ow NA H

R 1, 2, 3 (E41-PSL-il001 A, B,C, D) u d

3.

IIPCI Steam Line Tunnel Temperature - liigh NA H

Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41,-TS-3317 ;

E41-TS-3318; l

E41-TS-3354; E41-TS-3388; E41-TS-3489) l,,E 4.

lins Po.ier tionitor HA R

NA 1, 2, 3 i R (E41-K55 and E41-K56)

H

'.3 5.

IIPC I rurbine Exhaust Diaphragm Pressure - liigh NA H

Q 1, 2, 3 g

(E41-PSillfl012A, B,C. D) 6.

IIPCI Ste.am I.i ne Ambient i

O Temp - liigh NA H

R I, 2, 3 (E51 -TS-fl603C, D)

[

TABl.E 4.3.2-1 (Continue.1) si U

IS01.ATION ACTilATION INSTRUMENTATION SURVEll.I.ANCE REQil[NEMENTS

, g' CilANNEL Ol'ERATIONAL CilANNEL FUNCTIONAL.

CHANNEL CONDITIONS IN WlilCil

[!

Tu l t' filtlCTIOtl Aill) IllSTRullENT NUMBER CllECK TEST CAI.iBRATION SURVEII.I.ANCE HIUPIIRED Il s.

7.

Ill'CI Steam I.ine Area A Temp - liigh NA H

R 1, 2, 3 (E51-dTS-N604C,D) 8.

l'anergency Area Cooler Teinp - liigh NA H

Q 1, 2, 3 (E41-TS-N602A,8) h.

Reactor Core Isolation Cooling System Isolation 1.

RCIC' Steam Line Flow - liigh.

l i.a U

(E51-PDT-N017; NAId)

R(b)

I, 2, 3

NA E51-PDT-N018).

6.,

s

~ (E51-PDTS-Noll-2; D

H H

1, 2, 3 (E51-PI)TS-fl018-2) 2.

HCIC Steam Supply Pressure - Inw IIA H

Q 1, 2, 3 (E51-PS-N019A,H C.D) 3.

RCIC Steaia 1.ine Tiinnet liigh Temperature NA H

R 1, 2, 3 (E51-TS-3319; ESI-TS.-3320; ESI ~aS-3321; II E51 - rS-3322 ;

E51-rS-3323; fa' E51-rS-3355; E

E51-TS-348/)

f1 4.

Ilus Power flani tor flA R

NA I, 2, 3 P

(E51-K42 anil E51-K43) 5.

RC i t' ren bl ue Exhaust Islaphr. igm Pressuce - liigh IIA fl R

1, 2, 3

( E 51 - PS-flu l 2A,0,C, D)

vs.

pl

'rABLE_4.3.2-1 (continued) 1

'['

ISOI.ATION ACTilATION INSTRUNEttfATION StlHVEII.I.ANCE REQUIREMENTS o

CilANNEL OPERATIONAL a

CilANNEL FUNCTIONAI.

CNANNEL CONDITIONS IN WillCil b.

TR I t* FUNCrlotl AND INSTHiltlENT NUMBER CilECK TEST-CALIBilATICN SilRVEll.l.ANCE REQUIRED

.1 6.

MCIC Steam I.ine Ambient Temp - Iligh NA H

R I, 2, 3 (E51-TS-fl603A,B) 7.

RCIC Steam Line Area A Teing - liigt:

NA H

R I, 2, 3 (E51-dTS-N604A,8) 8.

HCIC Equipment Roose Ambient Temp - liigh 14A H

i.*

(E51-TS-N602A,B)

Q 1, 2, 3 4*

9.

RCIC Equipment Room A

,8, Tenip - 111g1:

NA H

Q 1, 2, 3 go (E 51 -dTS-N60! A,il)

J

').

SilllTih>LIN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water larvel -

I.ow, I A:ve l 1 (H21-1.T-N017A-1,B-1,C-1,D-1)

NA(a)

NA.

R(b) 1, 2, 3

( ll21-Ilril-fl017 A-1,8-l, C-1, D-1 )

D H

H 1, 2, 3 h.

React or Steain thaue Pressure -

liigh NA S/U(c),H R

1, 2, 3 g

(ll32-PS-N0184,11) m I

,3

~TillEMiandYing irraillated fuel in Llae secondary cont.iinment.

rt

Uhen react or steam pressure > $00 psig.

j.:

(a) The transmitter channel checE is satisfied by the trip unit channel check.

1-A sep.erate transmitter check is not required.

i.$

(h) Transmitters are exempted from the monthly channel calibration.

(c) 11 not pe tormeil withlia the previous 31 days. '

1 I

e

..sf!

TABLE 3.3.3-1 EMERCENCY CORE COOLING SYSTEH' ACTUATION INSTRUMENTATION n

HINIHUN NUMBER APPI.ICAHLE OPERAni.E CilANNELS OPERATIONAL 4

_TR.IP._F_iltHTT.Inti AND IllSTRilllErff flUHtiER PER TRIP SYSTEM CONDITIONS ACTION r

1.

CORE Sl' DAY SYSTE.f_t a.

Reactor Vessel Water level - tow, Level 3 2

1,2,3,4,5 30

( B21 -LT-t1031 A, B, C. D)

(il11-LTS-t303 t A-4, B-4,C-4, D-4 )

Is.

Reactor Steam Dome Pressure - Iow (Injection Permissive) 2 1,2,3,4,5 31 (1121 -PT-t1021 A, B,C. D)

(B21-PTS-N02tA-2,8-2,C-2,D-2) c.

Drywell Pressure - liigh 2

1, 2, 3 30

M

( E l 1 -PT-fl01 I A, B,C, D)

(EIi-PTS-1301IA-2,B-2,C-2,0-2) 4)

' d,

.l.

Time lulay Relay 1

1,2,3,4,5 31 (E21-Kl6A,B) e.

lius Ibwer IIcattorf 1/ bus 1, 2, 3, 4, 5 32 (E21-KIA,d).

2.

1.0Ll PRESSilRE C001. ANT INJECTION HODE OF HilR SYSTEM l

a.

1)ryue l l Pre:asure - Illgia 2

1, 2, 3

30 (E l 1-PT-fl011 A, B,C, D) q

( E l 1-PTil-da l l A-1, B-1,C-1, D-1) b.

Reactor vessel Water level - low, level 3 2

1, 2, 3, 44, 5*

30 fi (il21-1.T-r1031 A,B C.D) 5

( B 21 -IlrS-dO31 A-4, B-4,C-4, D-4 )

R He.ict.ir Vessel Shroud Level (Drywell Spray Permissive)

I 1, 2, 3, 4*,

5*

31

ro e.

3 (1521-11r-h036 and il21-LT-NO37) u (1121-LTri-do36-I and 1121-1.TH-NO37-1)

.o d.

Huaet.or Steam Ibme Pressure - Iow (lajection Permissive) j (il21 -PT-fl021 A,il,C,1))

( It 21 - PT:1 -il021 A-1,3-1, C-1, D-1 )

( 0 21 -P rS--!!a2 l A-2, B-2, C-2 D-2) 1.

talR Pump Start and LPCL Injection Valve Actuation 2

1, 2, 3, 4*,

5*

31 2.

I!netrculation Inop Puinp Discharge Valve Actuation 2

1, 2, 3, 4*, 5*

31

U

.]

TAnl.E 3.3.3-1 (Continued) en b*

EHERCENCY CORE C001.INC SYSTEM ACTUATION INSTRUMENTATION O

HINIHUH NUMBER APPI.ICARLE fj OPERABLE CilANNEl.S OPERATIONAL.

.M TRIP FilflCTIOli AND INSTRilHENT NUHRER PER TRIP SYSTEM CONiitTIONS ACTION i

4 i.tMJ PRESSilRE COOLANT IN.lECTION HODE OF RilR SYSTEH (Continued) l e.

RilR Pinnp Start. - Time iblay Relay 1

1, 2, 3, 4*,

5*

31 (STR-lAl,2 and STR-ini,2) 1.

lius Power :lonitorf 1/ bus 1, 2, 3, 4*,

5*

32 (El1-KlO6A,B)

{'{

3.

l11011 PRESSilRE COOLANT INJECTION SYSTEH l

a.

Reactor Vessel LJacer level - low, level 2 2

1, 2, 3

30

't (ll21 -LT-fl031 A, lI,C, D)

(il21-LTS-Il03 i A-2, B-2, C-2, D-2) b.

Drywell Pressure - liigh 2

1, 2, 3 30

( E l l -PT-fl0 l l A, B,C, D)

(E i 1-P FS-ilOl i A-2,il-2,C-2,D-2) c.

Conilensate Storage Tank level - tow 2**

1, 2, 3 33 (E41-LS-fl002, E41-1.S-N003)

.l.

Suppression Chainber Water level - Iligh 2**

1, 2, 3 33

( E41 -1.Sil-flu l 5A,il) e.

lius Power :loat tor #

1/ bus I, 2, 3 32

,,j, (E41-K55 and E41-K56)

.n

,i{

4.

A.llT._ol_lA.T._I C _ D_.E_l_'R.ES SilR I Z AT_ _i nti SYST_EN l

S a.

lir yue l l Preasure - liigh, coincident with 2

1, 2, 3 30 u

(E I l-PT -fl010A, H,C, D)

( E l l -PTH -Ho l 0 4-1, Il-1, C-1,1)- 1 )

~$

b.

I:cactor Ve:nsel IJatur icvel - Iow, level 3-2 1, 2, 3 30 (ll21 -1.T-1103 l A,it,C,0)

( n.! I -1.rS-H011 A-3, a-3,C-3, D-3)

t>J n".

-TAlli.E - 3. 3.3-1 (Cont inued) f is fj EHERGENCY CORE C001.INC SYSTElf ACTUATION INSTRUMENTATION oa:

HINIMUH NUMBER APPLICABLE r.

OPERABLE CllANNELS OPERATIONAL.

'd TillP FilflCTIOff AND INSTRiltlENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION el AllToll% TIC DEPRESSilRIZATION SYSTEH (Continued) l c.

Reactor Vessel tlater level - low, Level I i

1, 2, 3 30 (1521 -l.T-fl04 2A, B)

( 1121-LTH-1404 2 A-1, 8-1 )

.l.

ADS Timer 1

1, 2, 3 31 (l!21-TDPil-KSA, B)

Core Spray Puiap Discharge Pressure - liigh (Periaissive) 2 1, 2, 3 31 e.

(E21-PS-dOO8A,B and E21-PS-N009A,B)

N f.

RilR (I.PCI 110DE) Ptuap Discharde Pressure - liigli (Permissive) 2/ pump 1, 2, 3 31 y

(El l-PS-t!Ol 6A,B,C,D and p,'

E l 1 -PS-fl020A, B,C, D)

i..

g.

lius Pawer floultor#

1/ bus 1, 2, 3 32 (ll21 -K I A, ll)

APPL.ICABLE TOTAL. NO.

CilANNEl.S HINIHilH CilANNELS OPERATIONAL F_.ilH :l'idilAl. II_N_I.T OF CilANNELS TO TRIP Ol'ERABLE CONDIT10 tis ACTION 5.

1.uSS OF l' oiler a.

4. I t, kv Fmergency tsus 1/ bus 1/ bus 1/ bus 1,2,3,4N,5N 34

(

- Q.

lloile r vo l t age (lass of u

Voltage) b.

4.16 kv IGaerdency lius 3/ bus 2/ bus 2/ bus 1,2,3,4N,5##

35 IInile i vo l t ag.: (Insgrailed m

y Voltage)

.cn o

....tbt A

.____.________ applicable when two cure spray system subsy, stems are OPERAllLE per Specification 3.5.3.1.

^^ Psovides siqu.il to ilPCI pump suction valves only.

Alarm nuly.

1. Reqis f i e.1 when ESF equi pment is required to be OPl;RABl.E.

i sn iS TAtlLE 3.3.3-2 rny EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

'O AI.LOWABLE TR.I.P.F_il_llCT__I_n_ti_ AND itiSTRllflENT NilHliER TRIP SETPOINT

. _ VALUE gg s

' ~8 1.

aRE SPRAY SYSTEll p.4 a.

Reactor Vessel Water Level - Iow, level 3

-> + 2.5 inches *

> + 2.5 inches *

(!!21-tifS-11031 A-4,B-4,C-4,D-4) h.

Reactor Steam thuae Pressure - low 410 + 15 psig 410 + 15 psig

(!!21-PTS-fl021 A-2,B-2,C-2,D-2) c.

1)rywell Pressure - liigh

-< 2 psig

~-< 2 psig

( E l 1 -PTS-fl011 A-2, B-2, C-2, D-2) '

d.

. Time iblay-Relay 14 < t < 16 secs 14 < t < 16 secs (E21 -K16A,11)

~

e.

lins Power lionitor NA NA

,8 (E21-KI A,11) 4-l 2.

l 00 PRESSilRE C001. ANT IN.IECTION HODE OF Hllit SYSTEM a.

Dryweli Pre ssu re - liigh

< 2 psig

< 2 psig (E l l-PTil-fl0l l A-1,ll-1,C-1,D-1)

I,.

Reactor Vessel Water level - Iou, Level 3

-h+2.5 inches *

>~+ 2.5 inches *

(il21-I.TS-fl031 A-4, B-4,C-4,D-4)

?

c.

Reactor Vessel Shroud level

> - 53 inches *

(!!21-1.Til-!!O36-I and 1121 -firil-11037-1 )

it.

Reactor Steam lbme Pressure - low I.

Riln Pump Start and 1. CPI Va lve Actuation 410 + 15 psig 410 + 15 psig (1121 -P I S-tJ021 A-2, B-2, C-2, D-2 )

8 1.

Reci rculat ion Pump ilischarge Va lve Actuation 310 1 15 psig 310 i 15 psig (1521 -P'rtl-fl02 t A-1,Il-1,C-l.1)-1) so

TAlit.E 3.3.3-2 (Continued)

EMERGENCY CORE C001.ING SYSTEtt ACTtlATION INSTRilHENTATION SETPOINTS AI.LOWAHl.E THIP FilNCTIOil Atl0 INSTRilHENT N!!HilER TRIP SETPOINT VAI.llE 1.(r.1, PHESSilRi? C001.ANr 'IN.IE(TTION H0DE OF RilR SYSTEM (Continued) l e.

RilR Pump Start - Time Iblay Relay.'

9<t -< 11 seconds 9<t<- 11 seconds (STit-I Al,2 and STit-I B 1,2 )

f.

lius Power Monitor NA NA (E l 1 -K 106A,il)

L liiGli PuisSSilRE C001. ANT IN.lECTIOri SYSTi!H a.

Reactor vessel Water Invel - low, Imval 2

> + 112 inches *

( B21-tirS-fl031 A-2, B-2,C-2,D-2).

li.

Drywel1 Pressure - liigli

< 2 psig

( E I I -PTS-fl011 A-2,15-2,C-2, D-2) e.

Condensate Storage Tank lovel' - low

-> 23 feet 4 inches

> 23 feet 4 inches (E41-1.S-fl002; E41-1.S-N003)

.l.

Suppression Chamber Water lovel - liigli

-< -2 feet **

< -2 feet **

( E41 -1.Sil-flu t SA,II)

Iluu Pawer !!ont tor NA NA (E41-K55 an.1 E41-K56) 40 AllToilATIG OEl>RisSSilu!ZATION SYSTisH l

a.

Ihyueli Pr e as u re-lii gh

< 2 psig

( E l l - P r!!--Il010 A-1, B - 1, C-l, D-l )

h.

Reactor Vesaal Water Imvel - Iow, level 3

> + 2.5 inches *

> + 2.5 Inches *

(ll21 -l.TS-11031 A-3,Il-3,C-3, D-3) c.

Reactor Vesael Water level - Iow, level I

> + 162.5 inches *

( ll21 -1.T!!-!104 2 A-l. li-l )

.l.

AlsS 'l i nae r

( 1121 -T Dl'il--l) A.11)

< 120 seconds

.snp TABLE 3.3.3-2 (Continued)

~

.d un-d-

EHERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

-O ALLOWABl.E -

_TK..i.l'. FilflCT.I_O_N AND IflSTRUMENT NilHBER TRIP SETPOINT VAI Ul!

g U

Allroll4 TIC DEPattiSSilRIZATION SYSTEM (Continued)

Core Spray Pinnp Discharge Pressure - liigli

> 100 psig

> 100 psig e.

(E?l-PS-tt008A,B and is21-PS-N009A, B) f.

KliR (1.PC1 110D8) Puinp Discharge Pressure - liigh

-> 100 psig

~> 100 psig (1st1-PS-N016A,B,C,D and

~

E l l-PS-N O 20 A,ll,C, D) g.

Ilus Pawer Monitor NA NA it2 (821-KlA,B)

I t,a 5.

I.OSS OF POWER so

- u.

!w a.

4.16 kv Euergency Bus Undervoltage a.

4.16 kv Basis - 2940

161 volts 2940 i 315 volts (Insa of V.il tage)#

b.

120 v Basis - 84'i_4.6 volts 84 i 9 volts c.

< 10 sec. time delay

< 10 secs, time delay b.

4.16 kv ILuergency liins !!adervoltage a.

4.16 kv Basis - 3727 i 9 volts 3727 i 21 volts (oegraded voltage) b.

120 v Basis - 106.5 1 0.25 volts 106.5 i 0.60 volts c.

10 t 0.5 sec. time delay 10 i 1.0 sec. time delay I

di E

11 my n:

This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result

.9 In a trip.

lower vultage conditions will result in lecreased trip times.

cn A V.ess.:1 was er levels refer to RisFERENCli LEVEL ZERO.

A4 :ioppr.ssion chamber u. iter level zero is th.: tuIns centerline minus I inch.

6

5 TABLE 4.3.3-1

.n ENERGENCY CORE C001.ING SYSTEtt ACTUATION INSTHUHENTATION SURVEILI.ANCE REQillREllENTS

_n M

CilANNEL OPERATIONAL CilANNEI.

FUNCTIONAL CliANNEL CONDITIONS Ill WillCil

'O Tul e* FilllCTIO'tl AND IllSTRilHElif NUtillER CllECK TEST CAI.IllRATION SURVEILI.ANCli REQulHEI) m.

- - - - - - =

H

1. COHE SPRAY SYSTI:t!----

zi.

Reactor Vessel Water level -

Inw, i.evel 3

( li21 -I.T-fl031 A, B,C, D)

NA(a )

NA

- R( b) -

1, 2, 3, 4, 5' (ll21 -1.TS-H0 31 A-4, B-4,C-4,D-4)

D H.

H 1,2,3,4,5 is. Reactor Steam Dome Pressure - Iow (821-PT-fl021 A,II,C,D)

NA(")

NA R(b) 1,2,3,4,5 (ll21-PTS-N021A-2,8-2,C-2,D-2)

D H

H 1,2,3,4,5 c.

l>rywell Pressure - liigli I

NA ")

11A R(b) 1, 2, 3 (E l 1-PT-flDI I A,ll,C, D)

( til 1 -PTS-fl01 I A-2,il-2,C-2, D-2)

D H

H 1, 2, 3

.l. Time IAtlay Relay NA R

R 1,2,3,4,5 (li21 -K l 6A,lI) c.

lius Power !!ani tor NA R

NA 1, 2, 3, 4,.5 (li21-KI A,11) 2.

l. sal PHisSSul:E C001.At1T INJECT 10t1 HODE OF RilR SYSTtiH l

a.

Dryweli Pressu re - liigli (E I I-l'I'-flu t i A,II,C, D)

!{A(")

NA R(b) 1, 2, 3 (El 1 -P rf t-flol 1 A-1,13-I,C-1,0-1) 1)

H 1, 2, 3 ii.

Reactor Vessel llater level -

k luu, i.e ve l 3 (Is21-1.T-il031 A,il,C,D) f1A(")

NA R(h) 1, 2, 3, 4*,

5*

M (ll21 -1.TS-Il031 A-4,11-4,C-4,D-4)

D H

1, 2, 3, 4*, 5*

a" c.

He,ict or Vessel Siiruoil level y

(Is21-1.T-NO36.in<l ll21-LT-NO37)

NA(a)

NA RII')

1, 2, 3, 4*,

5*

(1521-1.T11-110 l(>-1 an.1 Il21-1.TM-NO37-1) 1)

H H

1, 2, 3, 4*,

5*

4

N TAllLE 4.3. 3-1 : (Continued)

El U

EHERCENCY CORE COOLING SYSTEM ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREHENTS e-<

i1 CilANNEL OPERATIONAL CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICil

'131' FiltlCi!Ori AND IslSTRilHENT NUHBER CilECK TEST CALIBRATION SURVEII.I.ANCE REQUlitEI)

,s-ic 1.OW l>RESSilRE COOLANT INJECTION HODE OF RilR SYSTEN (Continuest) l it.

Reactor Steani Ibue Pressure - Iow NA(a)

NA R(b) 1, 2, 3, 4*,

5A (ll21 -PT-N021 A, B,C, D) l.

RilR Puinp Start and LPCI in }ect ion Valve Actuation D

H H

1, 2, 3, 4*,

5*

(ll21-PTS-N021A-2,B-2,C-2,D-2) 2.

Recirculation loop Pump Discliarde Valve Actuation D-M N

1, 2, 3, 4*,

5*

M (ll21-PT!!-fl021 A-l. 8-1,C-l.D-1) r u

e.

RilR Pump Start - T1:ne iblay Relay NA R

R 1, 2, 3, 4*,

5*

b (STit-I Al 2 anal S TR-illi,2 )

f.

lius Power !!anitor NA R.

NA 1, 2, 3, 4*,

5*

( E l l-K 106A. II)

J. Ills;ll PRESSilRE C001. ANT INJECTION SYSTEM

.i.

Reactor Vessel Water level -

Inw. l.evel 2 (ll21-LT-NO31 A,II,C,D)

NA(")

NA R(b)

I, 2, 3 (ll21 -1. rS-flO 31 A-2, B-2, C-2, D-2 )

!)

it '

H 1, 2, 3 iT li.

Dryweli Pressu re - lli it d

NA ")

NA R(b)

I, 2, 3 I

( E l l-PT-N0 l l A,il,C, D)

{}

(El l -PTS-t10 l l A-2, B-2,C-2, D-2 )

D 11 H

1, 2, 3 ru N

c.

Contienuate Storage Tank invol - low NA H

Q 1, 2, 3 u

( E41 -1.S-NOO2 ; E41-LS-N003)

.o

.l.

Suppression Cliaintier Water level - liigli NA N

Q 1, 2, 3 o

( E41 -1.Sil-No I SA,11) c.

11u:6 Powe r !!.nii tor NA R

NA 1, 2, 3 (L41-K55 an.1 E41-K56) i l

hj TAlli.E 4.3.3-1 (Continued) i P!

EHERGENCY CORE C00LINC SYSTEM ACTilAf f0N INSTilUMENTATION SURVEILLANCE REQUIREME'NTS

3 O

CilANNEL OPERATIONAL 8

CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN Wil[Cil Q

'rRIv, FullCr!Off AtID lilSTRUMEdT NUMBER CilECK TEST CALIBRATION.

SURVEILt.ANCE REQlilREI)

M

4. AllrolltrtC DEPRESSilRlZATION SYSTEM a.

Drywell Pressure - llidh (El1-PT-N010A,B,C,D)

NA(a)

NA R(b)

I, 2, 3 (Ell-PTH-N010A-1,B-1,C-1,D-1)

D H

H 1, 2, 3 '

li.

Reactor Vessel Wter level -

Inu, i.e ve l 3 (ll21-l.T-NO31 A, H,C,D)

NA(8)

NA R(b)-

1, 2, 3 (ll 21 -1.TS-fl0 31 A-3, 8-3, C-3, D-3 )

D H

H 1, 2, 3 k

e.

Reactor Vessel Nater level -

Inu, Invel I I

NA ")

NA.

R(b) 1, 2, 3 j 'j *

(li21 -1.T-NO4 2 A, B)

(1121-LTil-fl04 2 A-1,8-1 )

D H

H 1, 2, 3 m

it.

Al)S Timer NA R

R 1, 2, 3 (1521 -TDPU-K 5A,11) e.

Core Spray l' ump Ulucliarge Pressure - ll18 :

NA H.

Q 1, 2, 3 1

(E21-l'S-N008A,11 aut!

E21-PS-N009A,li) t.

RilR (l.I'd! IlODE) Pump Discliarge Pressure - liigh NA H

Q 1, 2, 3 (E l l-l'S-flu l (>A,li,C,0 and h,

EI l-PS-NO20A,H C,1))

s

[j-r,.

lius Power floul tor NA R

NA 1, 2, 3 y

(ll21-KI A, ti) f, O

P I

g

-

ML20083D729

Text

Attachment:

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