ML20058Q282

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Proposed Tech Specs Change Re Deletion of Negative Flux Rate Trip
ML20058Q282
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/14/1990
From:
GEORGIA POWER CO.
To:
Shared Package
ML20058Q280 List:
References
NUDOCS 9008220017
Download: ML20058Q282 (9)
v • d • e


Text

.: . ..

4 ENCLOSURE 3

-V0GTLE ELECTRIC GENERATING PLANT

-TECHNICAL SPECIFICATION CHANGE-DELETION OF THE NEGATIVE FLUX RATE TRIP:

INSTRUCTIONS FOR INCORPORATION The proposed amendment to the Technical Specifications would:be, ,

incorporated;as follows: ,

Remove Paae Insert Paae 2-3* and 2-4 2-3 and 2-4 B 2-3* and B 2 B 2 3 and B 2'-4 3/4 3-1* and 3/4 3-2 3/4 3-1--and 3/4 3-2 3/4 3-9 and 3/4 3-10* 3/4=3-9 and 3/4 3-10 518 2

  • 0verleaf page containing no change E3-1 I 9008220017 900814

- gDR ADoCK0500g4

1 TABLE 2.2-1 -

8 S REACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS -

-1 c TOTAL SENSOR j'i ALLOWANCE ERROR d FUNCTIONAL UNIT (TA) Z_ (S) TRIP SETPOINT ALLOWA8LE VALUE b 1. Manual Reactor Trip N.A. N.A. N.A. N.A. N.A.

" 2. Power Range, Neutron Flux 4

N (NI-00418&C, NI-00428&C, NI-00438&C, NI-00448&C)

a. High Setpoint- 7.5 4.56 0 <109% af RTP# <111.3% of RTP#
b. Low Setpoint- 8.3 4.56 0 125%ofRTP# {27.3%ofRTPW

! 3. Power Range Neutron Flux, 1.6 0.50 0 <5% of RTP# with <6.3% of RTP# with l

High Positive Rate 5 time constant a time constant

'(NI-00418&C, NI-00428&C, >2 seconds >2 seconds NI-00438&C,MI-00448&C)

u. - (Delet eco .  :
  • 4. A b; r "_:.g , ... . . . ... . . _ ,
#. ; g tive ete it h enst=t 'i i!n cer.;t...;

.l l (%i G I Z , %i C O 2, -12 5&e.Ja -72 sue.-4; .i XI G C C,MI 00" ".C) -

5. Intermediate Range, . 17.0- 8.41 0 $25% of RTP# $31.1% of RTP#

, Neutron Flux

.(NI-00358,:NI-00368) '

Source Range, Neutron Flux 17.0 10.01 <105 cps -<1.4 x 105 cps

. 6. 0 -

~(NI-00318,NI-00328)-

1 7. Overtemperature ATL- . 6.6 3.37 1.95 See Note 1 See Note 2

-(TOI-411C,TOI-421C, + 0.50 TOI-431C,T01-441C) ,
8. Overpower AT-~ _

4.9 1.54 1.95 See Note 3 See Note 4

-(TOI-4118. TOI-4218, 1 101-4318,10I-4418) '

l M L POWER

1 h -

- - p.N - , ~ -uv u- ,,v,, ,--r--- .s - ~we,. e, x r. + ,--w- --N,, r- e a e es -.e. .

-6 j . .

LIMITING SAFETY SYSTEM SETTINGS BASES i

I REACTOR TRIP SYSTEM INSTRUMINTATION SETPOINTS (Continued) i l

The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or_ calculated level. In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity. The functional capability at the specified trip setting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety

! analysis to enhance the overall reliability of the Reactor Trip System.' The

[ Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is I

initiated. This prevents the reactivity insertion that would otherwise result l from excessive Reactor Cooiant System cooldown and thus avoids unnecessary actuation-of the Engineered Safety Features Actuation System.

Manual Reactor Trip The Reactor Trip System includes manual Reactor trip capability.

L Power Range, Neutron Flux

  • In each of the Power Range Neutron Flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip '

, setting. The Low Setpoint trip provides protection during suberitical and low power operations to mitigate the consequences of a power excursion beginning i

] from low power, and the High Setpoint trip provides protection during power operations to mitigate the consequences of a reactivity excursion from all l power levels, i.

The Low Setpoint trip may b2 manually biccked-above P-10 (a power level of approximately 10% of RATED TFERMAL POWER) and is~ automatically reinstated below the P-10 Setpoint.

. Power Range Neutron Flux, High Rates j The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a control rod drive housing.  !

Specifically, this trip complements the Power Range Neutron; Flux High'and Low trips to ensure that the criteria are met for rod ejection.from mid power.

I FE W TT , .I V g wb T% g% bI iWV I WD bb W 5 W . ,D W Ww W

id;nt;. "t Fish p; ;
;ingi; er ;;1 tipi; red drep ;;;id;nt ;;.'d ;;;;;

1;;;1 11;; p;; king .hi;h ;;.id ;;;;; :n an;;n;;rs;tig; ',e;;i OMOR t,;;i;t. 'h; b"I[5""_5N!*"M

'. ' . ' I '". .

.o L' ~

'.1 ' ~ ' ' v_ u' N"?!25

- - . . ... ' . .' " y"' o' u_ ' U L

.. u

!!.".".1 T L T. 'f". 55:55'hY'lf

'7!.' < ' L7.a ". ".'. ' , ','" "*N9"LI'i"!!!'~'51h!E535 nisu -non . v. ' ".' " .._' .' ' . < ." . . ' ;. . L '

vi . u -.

V0GTLE UNITS - 1 & 2 B 2-4

. _ _ _ - - . = _

~

. TABLE 3.3-1 f

S REACTOR TRIP SYSTEM INSTRUNENTATION ".

E .

c MININUM-5 TOTAL NO. CHANNELS CHANNELS APPLICABLE d FUNCTIONAL UNIT. OF CHANNELS TO TRIP OPERABLE MODES ACTI_0N b 1. Manual Reactor Trip 2 1 2 1, 2 - 1

" 8 4*, a 2 1 2 3 , 5 13 ro

2. Power Range, Neutron Flux (NI-00418&C,-NI-0042B&C, NI-0043B&C, NI-00448&C)

~

b

a. High Setpoint 4 2 3 1, 2 2 d b
b. Low Setpoint 4 2 3 I2 2 b

R

3. Power Range, Neutron Flux, 4 -2 3 1, 2 2 w

High Positive Rate 4 .(NI-00418&C,NI-0042B&C, NI-0043B&C,-NI-00448&C)

( D e leted) _ _ , _ , _ _ _ , , _ , , , , ,

.b

4. A g s.

,_ ..g,..,g . ...

, , c ., i,& c

,,,3,.-3. ..m -. .

{%; ^6 C , -~ ^^^^^^.C.

= =c , :: = := > - ,
5. Intermediate Range, Neutron Flux (NI-90358,0&E-NI-00368,98G) d
a. Power Operation ~ 2 1 2 I , 3 b.- Startup 2 1 _2 2 3
6. Source Range, Neutron Flux (NI-00318,0&E, NI-00328,0&G)
a. Startup 2 1 2 25 4
b. Shutdown 2 1 2 3 3 , 4, 5 5

. . ~_ - . - . -- _ - _ . = - _ _ - _ _ _ . _

TABLE 4.3-1 .

, REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS .

8 TRIP ANALOG ACTUATING IWDES FOR ~ "..

CHANNEL DEVICE WHICH ~

@ CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION S'JRVEILLANCE

= _ FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED

m -

8 8

1. Manual Reactor Trip N.A. N.A. N.A. R(14) N.A. 1 3

2, 3 ,.4 ,

" 5 l

    • 2. Power Range, Neutron Flux i

N (NI-0041BaC, NI-0042B&C, NI-0043B&C, NI-0044B&C)-

i

-a. High.Setpoint 5 0(2,4), Q(17) N.A. N.A. 1, 2 M(3, 4),

Q(4, 6),

. R(4, 5) d

b. Low Setpoint S R(4) S/U(1) N.A. N.A. 1,2 i R h.A. .N.A.

j

  • 3. Power Range, Neutron Flux, 'N.A. R(4) Q(17) 1, 2 4

y High Positive Rate

  • (NI-00418&C, NI-0042B&C.

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

4. A .g,

{; . Fh;, M.A R(?) Q(17) M.A. Md. 1, 2

".':.T'. ';c::".:.~ :. --

1",

m 'ou,_""Zi"".*.

,, ->" oo ' - ",',i""", '

d

5. Intermediate Range, S R(4. 5) S/U(1) N.A. N.A. I 2

'Aeutron Flux

. (NI-00358,D&E, j NI-00368,D&G)-

0

6. Source Range, Neutron' Flux 5 R(4., 5) S/U(1)',Q(9,17) N.A. N.A.
  • 2 ,'3, 4, 5 (NI-00318,0&E, NI-00328,0&G)
7. Overtemperature AT S R(12) - Q(17) N.A. N.A. 1, 2 (101-0411C, 101-0421C.-

TDI-0431C, T01-0441C) i A. .. , , a ss ._

Y._ > ..n -- a, . . . . - a n -w ~n ,,m. - . , , . ,_ s,,. _ _ . . _ . _ _ , _ _ _ _ , _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ . _

~ TABLE 2.2-1  ; ,

g REACTOR TRIP SYSTEN INSTRUMENTATION TRIP SETPOINTS *

"I TOTAL SENSOR p ALLOWANCE ERROR-TRIP SETPOINT ALLOWABLE VALUE c (TA) ._ Z (S) 3 FUNCTIONAL UNIT a N.A. N.A. N.A. N.A.

Manual Reactor Trip N.A.

1.

2. Power Range, Neutron Flux

[ (NI-00418&C, MI-00428&C, f NI-00438&C, NI-00448&C) 7.5 4.56 0 $109% of RTP# $111.3% of RTPS

a. High Setpoint 4.56 0 $25% of RTP# $27.3% of RTPS '
b. Low Setpoint 8.3 1.6 0.50 0 $5% of RTP# with 56.3% of RIP # with
3. Power Range, Neutron Flux, a time constant a time constant High Positive Rate >2 seconds. >2 seconds (NI-00418&C, NI-00428&C, NI-00438&C, NI-00448&C) 4 m 4. (Deleted) 17.0 8.41 0 125% of RTP# $31.1% of RTP#
5. Intermediate Range, Neutron Flux (NI-00358, NI-00368) 10.01 0 $105 cps l$1.4 x 105 . cps Source Range, Neutron Flux 17.0 6.

(NI-00318, NI-00328) 3.37- 1.95 See Note 1 See Note 1 0vertemperature aT 6.6

7. + 0.50 (T01-4110. TOI-421C,
  • TOI-431C,-TOI-441C)-

1.54 1.95 See Note 3 See Note 4 Overpower AT. 4.9 8.

(TOI-4118 TDI-4218 TOI-4318 -TOI-4410)

  1. MIF = MAILU iHtHRAI. PWER

_ . _ . . . . . _ _ _ _ . . . _ . . . _ _ _ _ _ . _ . -_ __ ._ __ _ _ =_ _ . . _ . . . _ _ _

-(IMITINGSAFETYSYSTEMSETTINGS BASES REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS (Continued) ,

The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by*the Reactor Trip System reaches a preset or calculated level. In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity. The functional capability at the specified trip setting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. This prevents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unr n essary actuation of the Engineered Safety Features Actuation System. .

Manual Reactor TriD The Reactor Trip System includes manual Reactor trip capability.

Power Rance. Neutron Flux l In each of the Power Range Neutron Flux channels there are two independent

bistables, each with its own trip setting used for a High and Low Range trip I setting. The Low Setpoint trip provides protection during suberitical and low power operations .to mitigate the consequences of a power excursion beginning f rom low power, and the High Setpoint trip provides protection during power I operations to mitigate the consequences of a reactivity excursion from all power levels.

The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is-automatically reinstated below the P-10 Setpoint.

Power Rance. Neutron Flux. Hich Rates The Power Range Positive Rate trip provides protection against-rapid flux increases which are characteristic of a rupture of a control rod drive housing, Specifically, this trip complements the Power Range: Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid-power. i V0GTLE UNITS - 1 & 2 B 2-4

l

\ -.

TABLE 3.3-1 -

= . ,

REACTOR TRIP SYSTEN INSTRUNENTATION MINIMUN

'- 8 CHANNELS APPLICA8LE  ;

TOTAL NO. CHANNELS N

'" OF CHANNELS TO TRIP OPERA 8LE NODES i ACTION FUNCTIONAL UNIT

S. 2 1, 2 1 Manual Reactor Trip 2 1 M 1. 2 3a, 4a. Sa 11

' " 2 1

" ' Power Range, Neutron Flux o-2.

1

" (NI-0041B&C,;NI-0042B&C,

.4 NI-0043B&C, NI-00448&C) 4 2 3 1, 2 2b

_ a. High Setpoint 3 d I,2 2b

~

Low Setpoint 4 2 b.

2 3 1, 2 2b .i Power Range,. Neutron Flux, 4 3.

High Positive Rate 2 (NI-00418&C, NI-00428&C,-

w NI-0043B&C, NI-00448&C) k -

4. (Deleted) 5 ~. Intermediate Range, Neutron Flux j.

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

2 1 2 1d , 3

a. Power Operation 2 2 3 2 1
b. Startup j- 6. Source Range, Neutron Flux (NI-00318,0&E, NI-00328 D&G) 2 2C - 4 2 1
33. 4, 5
g. gtargup

. hut own- 2 1 :2 5 s , - , - - .- . , . -, . . . - - -w. , .m. e - -- ., .. . . ~ .,

1 x ,

TABLE 4.3-1 &

  • ~ * 'i I REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1 RIP y'

ACTUATING MODES FOR ANALOG.

w . DEVICE gWHICH E CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE c- CHANNEL EHANNEL TEST LOGIC TEST _ IS REQUIRED 5 FUNCTIONAL UNIT CHECK CALIBRATION TEST d N.A. N.A. R(14) N.A. 1, 2, 3a, 4a,

1. Manual' Reactor Trip N.A. 58 Y

'. Q9 'i ro 2. Power Range, Neutron Flux

'(NI-0041B&C, NI-0042B&C,  :

l MI-0043B&C, NI-0044B&C) i N.A. II . A . I, 2

a. High Setpoint S- 'D(2, 4), Q(17)

'M(3, 4), :l ,

Q(4. 6),

R(4, 5) 4 N.A. .1,2d  !

R(4) S/U(1) N.A.

... b. Low Setpoint S  ;

.N.A. Q(17) N.A. N.A. 1, 2-

$ 3. Power Range, Neutron Flux, High Positive Rate' R(4) w .

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

4. (Deleted) l N.A. I,2d S- 'R(4, 5) S/U(1) N.A.
5. Intermediate Range,

' Neutron Flux -;

j (NI-00358,0&E, -

MI-00368,D&G)

S/U(1),0(9.17) N.A. . N.A. 20 , 3, 4, 5 i 6. Source Range, Meutron Flux 5 ~ R(4, 5).

1

-(NI-00318,0&E, NI-0032P,,D&G)

Q(17) N.A. M.A. 1, 2' 4 7. Overtemperature AT S R(12)

(TDI-0411C. TDI-04210, i 101-0431C, TOI-0441C) q l

_ . . _ . . . . . , v. .m -- r..  :..m ._-r . , m, , , . , s - ,_ _. . . . , _ _ _ _ _ _ __ _ _ _ . , _ _ _ _ _ _ _ , , . ,

_

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