Text

Forwards Proposed Changes to Proof & Review Tech Specs Re Reactor Trip Sys Instrumentation Trip Setpoints & ESF Actuation Sys.Changes Reflect New Info Not Contained in Tech Specs
	ML20084L257
Person / Time
Site:	Catawba
Issue date:	05/04/1984
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 8405140402
	Download: ML20084L257 (14)
	v • d • e

- - -

I. 3M POWEli COMPANY P.O. 3, OIL !WHHH O H Alet.h tTtt. N.O. W H W HI

" ^ ' '

..1EUI"-

pilliSIEEEii

],

May 4, 1984

" * " ' " ~ ' "

4 Mr. Harold R. Denton, Director.

Office of Nuclear Reactor Regulation U. S. Nuclear Dagulatory Conctssion Washington, D. C. 20555 Attention: Mt C. G. Adensam. Chief Licensing Branch No. 4 Re: Catawba Nuclear Stallon, Unit 1 Docket No. 50-41.1 Proof and Review Technical Specifications

Dear Mr. Denton:

Please find attache,i proposed changes to the Proof and Review Technical

'ncificetions f or Catawba Unit 1. These changes reflect new information not i

-currently contatt.ed in the Technical Specifications.

Very trilly yours, f45

/

. Hai D. TuckeP RWO/php isttachment cc: Mr. Jimos P. O'Reilly Mr. Jesse L. Riley Regional Administrator Carolina Environmental Study Group U. S. Nuclear Regulatory Commission 854 Henley Place Region 11' Charlotte, North Carolina 28207 101 W.rlett,a Stract, NW, Suite 2000 Atlanta, Georgia 30303 Palmetto Alliance 21351 Devine Street NRC Resident Intt.ector Columbia, South Carolina 28207 Cataba Nuclear !.tation Mr. kohert Guthi, Esq.

Attorn ty at ta,.

P. O. Box 12097 Charleston.. South Carolina 29205 1

0 h

t k

I l

[

TABLE 2.2-1 i

g REACTOR TRIP SYSTEN INSTRESENTATION TRIP CmJINTS i

r E

TOTAL (SENSOR t

LERROR ALLO m MCE e

g FlasCTIONAL INIIT (TA)

Z (5)

TRIP SETPOINT ALLOWASLE VALUE U

1.

haual Reactor Trip N.A.

N.A.

2.

Power Range, Neutron Flux a.

High Setpoint

7. 5 4.56 0

$109E of RTP*

_ 1 of RTP*

.h f RTP*

b.

Low Setpoint 8.3 4.56 0

$25% of RTP*

3.

Power Range, Neutron Flux,

1. 6 0.5 0

$5% of RTP* with

$6.3% of RTP* with High Positive Rate a time constant a time constant 1 2 seconds 3 2 seconds 4.

Power Range, Neutron Flux, 1.6 0.5 0

<E% of RTP* with

<f. 3% of RTP* with High Negative Rate i time constant a time constant C3

~

"4 12 seconds 12 seconds Q

5.

Intermediate Range, 17.0 8.4 0

<25% of RTP*

-<31% of RTP*

Neutron Flux i

E 6.

Source Range, Neutron Flux 17.

10 no 105 cps

<1.4 x 105 M

cps

[4s42

- Jet z y See Note 1 See Note 2 c3 i

J 7.

Overtemperature AT

, /_

C3 8.

Overpower AT 4@43

/

l 'l.

"U

.2 See Note 3 See No 4

/

1.zs, 5 j 31945 psig 9.

Pressurizer Pressure-Low

,3re 4

Jaspt

>19 g

10.

Pressurizer Pressure-High

.Det

$2385 psig

<23 ig

11. Pressurizer W ter Level-High 5.0 2.18 1.5

<92% of instrument -<93.8%

f instrument span C'

\\

I e3 2.7, 1

12.

Reactor Coolant Flow-tow 2.5 1.77 0.6 190% of loop 3.

f loop l

design flow'*

ign flow **

" RIP = RATED TWIBtAL POWER

- Loop design flow = %,900 gpa

9 TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g

TOTAL SENSOR x^

O

-18 15.3 '7e c

ALLOWANCE ERROR ((TRIPSETPOINT FUNCTIONAL UNIT (TA)

Z (S)

\\

ALLOWABLE VALUE g

t h of span

13. Steam Generator Water 3E'-

-4&cM 1.5 2

%'of span from g

l Level Low-Low lp ly, ffom 0% to 30%

fo 30% RTP*

/

RTP* ingreasing nc 671%}vor spa i@h, linearly liner y to

%,cf span from j

i from 30L to 100% RTP*

f 6 30% to 10 %

68 M i

RTP*

,s 14.

Undervoltage - Reactor

'I N

) =c't: Flo"/o (Solfa *II8)J Coolant Pumps

[,

777,ffn,uvol}

v;{k /

H.o 0.0 f 1.0 a.> see

' 15.

Underfrequency - Reactor 4,@

107. ^.. -re n e ase +; g_ @'

^

C :::

Coolant Pumps m

5d4 de w A a 55.9 HE j 16.

Turbine Trip d'l

"'***P'***

M l

~

o a.

Low Control Valve EH N.A.

N. A.

N.A.

1550 psig 1500 psig m

Pressure ro S

b.

Turbine Stop Valve N.A.

N.A.

11% open 11% open

]

Closure cs 17.

Safety Injection Input N.A.

N.A.

k' from ESF i

RIP = RATED THERMAL POWER

TABLE 3.3-4 (Continued) g i

y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E

SENSOR TOTAL ERROR g

FUNCTIONAL UNIT ALLOWANCE (TA) Z (S)

TRIP SETPOINT ALLOWABLE VALUE Z

10. Loss of Power g

4 kV Bus Undervoltage-N.A.

N.A.

R3500 W

> 3200 volts a-Less

[ ' " 1,.

"J Voltage volts ".;iit. e o e. - r_

w.. za kv Sus undeevolky-

ae UL "A-s,.a 4 4 s q aA-9 A-m

11. Control Room Area Ventilation

- 37t.p/ vo(fs 2 36l9 Vo[b Isolation

~~

w u

}

a.

Manual Initiation N.A.

N.A.

ca

' 3 Y

c3 b.

N Automatic Actuation Logic and Actuation Relays N.A.

N.A.

=3 c.

Loss-of-Offsite Power N.A.

N.A.

Q

12. Containment Air Return and r-is flydrogen Skimmer Operation "i5 c3 c3 a.

Manual Initiation N.A.

N.A.

N. A.

N.A.

u b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays r

,/, 2.

'l c.

Containment Pressure-M 0.71

1. 5 53 psig

<3.PK ps g liigh-High 12.T 8

TABLE 3.3-4 (Continued) n 2,

d ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E

2 SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) Z (S)

TRIP SETPOINT ALLOWABLE VALUE a

/

8. Auxiliary Feedwater (Continued) w 9%

15.~b'la

)

s c.

Steam Generator Water 12 12.18 1.S of spa

>1Ike6% of /

Level - Low-Low rom 0% to span f 0% to 30% RTP TP inc i ing

~~f

- creasing linearly o >5Gr M,g 5 6 E 7+

linea ys to of span fr m 3G% tu 5147,'

>y4,4%of 100% RTP 5 pan irom 30%

to 100% RTP d.

Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

w 35cc 3100 f

e.

Loss-of-Offsite Power N.A.

N.A.

> 4estney V

>My

ts f.

Trip of All Main Feedwater C

Pumps N.A.

N.A.

Cm g.

Auxiliary Feedwater Suction N.A.

N.A.

-> 2 psig

-> 1 psig Pressure-Low MO

9. Containment Sump Recirculation M

M a.

Automatic Actuation Logic N.A.

N.A.

o and Actuation Relays O

Lou b.

Refueling Water Storage N.A.

N.A.

> 120 inches

> 114 inches Tank Level-Low Coincident With Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

THIS PAGE 0?E i PE1 min RECEIPT OF INFORMAil0N. El i.IE AP?LICANT

TABLE 3.3-4 (Continued) g 8

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E

SENSOR TOTAL ERROR E

FUNCTIONAL _ UNIT ALLOWANCE (TA) Z (S)

TRIP SETPOINT ALLOWABLE VALUE l

4

. j

6. Turbine Trip g

a.

Manual Initiation N.A.

N.A.

N. A.

N.A.

N. A.

b.

Automatic Actuation N.A.

N.A.

N. A[

Logic and Actuation Relays

[

8 V.Z 7 c.

Steam Generator Water 5.4 2.18

1. 5

<82.4% of o

rrow Level-High-High (P-14) iiarrow range 3

ment instrument span

]

span c3 d.

Trip of All Main N.A.

N.A.

c:-)

Feedwater Pumps T

w J,

e.

Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable

=ca o

Values.

[]

res

7. Containment Pressure Control G

System a

c.. 3 a.

Start Permissive N.A.

N.A.

1 0.25 psig 1 0.25 psig y

b.

Termination N.A.

N.A.

1 0.25 psig 1 0.25 psig

8. Auxiliary Feedwater a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays l

1

h TABLE 3.3-4 (Continued) h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP'SETPOINTS E

SENSOR TOTAL ERROR E

FUNCTIONAL UNIT ALLOWANCE (TA) Z (S)

TRIP SETPOINT ALLOWABLE VALUE

~t s

4. Steam Line Isolation a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays m

.I

a c.

Containment Pressure-High-High MIL 3 0.71

1. 5

$3

53. W sig t.&l 726 (di m

Of4.6 d.

Steam Line Pressure - Low

1. 5

>W e psi

>fWrpsi no

-<*111.3 psi w

e.

Steam Line Pressure-8.0

0. 5 0

M

-<a100 psiAs 1

Negative Rate - liigh

7:1. e Isi 5,

r-r

5. Feedwater Isolation M

e C"3 a.

Automatic Actuation Logic N.A.

N. A.

N.A.

Actuation Relays g4 26 b.

Steam Generator Water 5.4 2.18

1. 5

<82.4% of

-<8SnW narrow Level-High-High'(P-14) iiarrow range 2 instrument instrument span span I*

i' 40

' 5G 2 "Y c.

T

-Low

_( -)- '

d.

O g ouse Water Level-High

-(

)cl.O M'

'j 'A' 12 in,L4 a 6.u_

)-

level c,L 37 No e kvd e.

Safety Injection See Item 1. above for all Safety Inje

~_n htnn' an a1Ues.

f 1

l

'THIS PAGE 0?i'! PENN!T; RECEIPT OF i

INFORMA fldN. n.i TA A?.>: lCANT

f O

TABLE'3.3-4 (Continued)

Y ENGINEERED SAFETY FEATURES ACTUdTION SYSTEM INSTRUMENTATION TRIP SETPOINTS i

5 SENSOR TOTAL ERROR E

FUNCTIONAL UNIT ALLOWANCE (TA)

(S)

TRIP SETPOINT ALLOWABLE VALUE Z

q s

3. Containment Isolation a.

Phase "A" Isolation

1) Hanual Initiation N.A.

N.A.

N:A.

t

2) Automatic Actuation Logic N.A.

N.A.

and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

b.

Phase "B" Isolation (Nuclear w

j h

Service Water Operation) w t3 I

7.3 A

1) Manual Initiation N.A.

N.A.

C3 oo C3 r1

2) Automatic Actuation N.A.

N.A.

Logic and Actuation g

^

1 Relays g

@7

<=:

3) Containment Pressure-

=4i4P 0.71 1.5 5 3 psig 5 3.bK psig

<fj f

High-High s

i c3 c.

Purge and Exha.ust Isolation Q

i

1) Manual Initiation N.A.

N.A.

2) Automatic Actuation N.A.

N.A.

Logic and Actuation Relays i

i

3) Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

-m,,

+ - -

4 rm n.-

-w.

h b

TABLE 3.3 4 r.>

2M GINEERED SAFETY FEATURES ACTUATION SYSTE INSTRUMENTATION ggIP SETPOINTS 2

SENSOR E

TOTAL ERROR y

FUNCTIONAL UNIT ALLOWANCE (TA) Z (S)

TRIP SETPOINT ALLOWABLE VALUE w

1. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Auxiliary Feedwater-Motor-Driven Pump, Purge &

Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Ventilation Isolation, Emer-c gency Diesel Generator Opera-tion, Component Cooling Water, c3 Turbine Trip, and Nuclear 9

w)

Service Water Operation)

!?o w

~o 4

a.

Manual Initiation N.A.

N.A.

Q b.

Automatic Actuation Logic N.A.

N.A.

N. A.

N.A.

]

and Actuation Relays c.

Containment Pressure-High 0.71

.5 5 1.2 psig u

d.

Pressurizer Pressure-Low

1. 5

> 1845 psig 183fp e.

Steam Line Pressure-Low 1.5

> M6 psig

> M psig 7zs L91

2. Containment Spray (Nuclear Service Water Operation) l a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation Logic N.A.

N.A.

and Actuation Relays 7

Containment Pressure-High-Hig [

0.71

1. 5 1 3 psig 5 3.

sig

}

c.

V(f yibute b* ~\\

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PERIMETER FENCE NSW 6 ' *~

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NUCLEAR SERVICE j

WATER POND 4

2500 FT. R.

(

EXCLUSION l

i B0UNDARY N

I

)

INTAKE STRUCTURE l::i....i.!.:: :ll::::::!: !!; :lllllllll TURBINEBLDGS.J BL m

SWITCH g

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BLDG.

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a",ll'.", '. _. ~t

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. a.t, o is O ettat a vsenat enout s O CownsE #Csat OR.fts.60VS ESfagusastst.fS h.N.-.*._.._.j ~~ "'

O CATAWBA NUCLEAR ST LOW POPULATION ZONE Figure 5.1-2

SITE B0UNDARY/

PERIMETER FENCE A

i g;3y

, DAM f-FtGRRE S l~3 g y p wenTJ O

NUCL S%CE g 6 ~N

\\

2500 FT. R.

i EXCLUSION B0UNDARY y

INTAKE STRUCTURE

i11Ii;;II!,;;;;;;;;!!IiI!II REACTOR TURBINEBLDGS.g BLDGS.

5"E" Y

,-ACCESS ROAD x

o i

1 a

VISITOR'S J OVERLOOK C

TOWER yAR kTR E

(LIQUID ELEASE.

SITE B0UNDARY/

6Y A

PERIMETER FENCE ggf#

?N*get tiSW s

'U^"

Wgo l:

6

s /

@ g -5 "NhR 2500 FT. R.

I EXCLUSION B0UNDARY INTAKE STRUCTURE

iiiiiiii'

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(GASE0US RELEASE POINT) ll

^

SWITCH i

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K -ACCESS ROAD y

N, o

a VISITOR'S _

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ML20084L257

Text

Dear Mr. Denton:

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