ML20212F224

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Proposed Tech Specs Revising Certain Instrumentation Allowable Values
ML20212F224
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 10/28/1997
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20212F220 List:
References
NUDOCS 9711040214
Download: ML20212F224 (30)
v • d • e


Text

. .. _ _ _ .. . . _ . _ _ ..

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'i -

ENCLOSURE 5 ,

-s BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 '

DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR 71 AND DPR-62

- REQUEST FOR LICENSE AMENDMENTS INSTRUMENTATION ALLOWABLE VALUE CHANGES -

i MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 T

4 9711040214 971028 PDft ADOCK 03000324 P PDft S

'l_________, 4 . -y--

r ,. . _ _

E E

E

-n -TABLE 2.2.1-1 a

E REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

1. Intermediate Range Moattor, Neutron Flux - High'd s 120 divisions of s 120 divisions of.

full scale full scale.

2. Average Power Range Monitor
a. Neutron Flux - High, 15%*' s 15% of RATED s 15% of RATED THERMAL POWER THERMAL POWER
b. Flow-Blased Simulated Thermal Power - High'***

s (0.06W + 59.6%) s (0.66W'+ 61%) I with a maximum with a maximum -

s 113.6% of RATED s 115.3% of RATED I

'~

{ THERMAL POWER THERMAL POWER

c. Fixed Neutron Flux - High** ,gg7 s 116.3% of RATED s of RATED i THERMAL POWER TH L POWER
3. Reactor Vessel Steam Dome Pressure - High s 1067.9 psig s @ psig I
4. Reactor Vessel Water level - Low, level 1  !

2 +153.2 inches" h +153 inches * .I

5. Main Steam Line Isolation Valve - Closure'd s 10% closed s 10% closed k

o

' 6. (Deleted) g 7. Drywell Pressure - High s 2 psig

" s 2 psig

8. Scram Discharge Volume Water level - High s 109 gallons s 109 gallons

[ 9. Turbine Stop Valve - Closure" s 10% closed s 10% clcied g 10. Turbine Control Valve Fast Closure, Control Oil Pressure - Low" 2 500 psig 2 500 psig N

e

_..__m._.___.____-_____._________________m_ _ _ _ _ _ _ _ a _ e-- tu -- -m ea__ ___

a E

E, v .

((- TABLE 3.3.2-2(Continued [

n ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E.

ALLOWABLE

~[ TRIP FUNCTION TRIP SETPOINT VALUE

2. SECONJARY CONTAINMENT ISOLATION
a. Reactor Building Exhaust Radiation - High s 11 mr/hr s 11 mr/hr
b. Drywell Pressure - High s 2 psig :s 2 psig
c. Reactar Vessel Water Level - Low, Leeel 2 2: + 104.1 inches"' at + inches"' l
3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - High s 73 gal / min

$7 s 73 gal / min E$

b. Area Temperature - High s 150*F ms 150*F
c. Area Ventilation A Temperature - High s 50*F :s 50*F
d. SLCS Initiation NA NA b
e. Reactor Vessel Water Level - Low, Level 2 m + 104.1 inches

F 2: + inches"' i j[ f. A Flow - High - Time Delay s 30 minutes =s30 air.utes r*

g. Piping Outside RWCU Rooms Area s 120*F :s120*F Temperature - High .

y.

ed C3 W

i 9

h

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y E

c 2 .

E x- TABLE 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E~

TRIP FUNCTION ALLOWABLE

[ TRIP SETPOINT VALUE

1. CORE SPRAY SYSTEM

.a. Reactor Vessel Water Level - Low, Level 3 m + 14.1 inches" m + 13 inches 'l

b. Reactor Steam Dome Pressure - Low 2 406.7 psig a g psig I
c. Drywell Pressure - High s 2 psig s 2 psig .

w d. Time Delay-Relay 1 14 s t s 16 secs 14 s t s 16 secs *

m. e. ' Bus Power Mon ~1 tor NA NA b 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM
a. Drywell Pressure - High s 2 psig s 2 psig
b. Reactor Vessel Water Level - Low, tevel 3 2 + 14.1 inches" 2 + 13 inches" I
c. Reactor Vessel Shroud Level i 2 - 53 inches" 2 - 53 inches"

@ d. Reactor Steam Dome Pressure - Low n.

h

~

1. RHR Pump Start and LCPi Valve ~

Actuation 2 406.7 psig

= 2. Recirculation Pump Discharge Valve 2 ig l

? Actuation a 3CG.7 psig 2 I

$ e. RHR Pump Start . Time Delay Relay _ 9 s t s 11 seconds 9 s t s 11 seconds

f. Bus Power Monitor NA i NA 1

S

~

E E'

E
n ' TABLE 3.3.3-2 (Continued)

? EMERGEMCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

~

'[. TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE

3. HIGH PRESSURE COOLANT INJECTION SYSTEM IDI
a. Reactor. Vessel Water level - Low, Level 2 2 + 104.1 inches" k+ inches" i
b. Drywell Pressure - High s 2 psig s 2 psig
c. Condensate Storage Tank Level - Lcd a 23 feet 4 inches 2 23 feet 4-inches w d. Suppression Chamber Water Level - High s -2 feet" 1 s -2 feet" '

w e. Bus Power Monitor NA NA

4. AUTOMATIC DEPRESSURIZATION SYSTEM b
a. ADS Inhibit Switch NA NA
b. Reactor Vessel Water Level - Low, Level 3 m + 14.1 inches" d + 13 inches" l
c. Reactor Vessel Water Level - low, Level 1

$ m + 153.2. inches" m + 153. inches" l g d. ADS Timer s 83 seconds s 108 seconds 1

e. Core Spray Pump Discharge Pressure - High a 112.1 psig 2 102 psig I

,5 f. RHR (LPCI MODE) Pump Discharge Pressure - High a 111.1 psig 2 102 psig 1 g g. Bus Power Monitor NA NA e

.c .:

o ,

4 TABLE 3.3.6.1'-2 t ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS O

TRIP ALLOWABLE TRIP FUNCTION SETPOINT-. VALUE /b

1. Reactor Ves'sel Water Level - a + 104.1 inches'd = +' inches'd l Low, Level 2
2. Reactor Vessel Pressure - High s 1137.8 psig sh psig l IN7

'd Vessel water levels .efer to REFERENCE LEVEL ZERO.

..=

BRUNSWICK - UNIT-1 3/43-90 Alrendment No.183 l

E

.g E-

. TABLE 3.3.7-2 x

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

.E ALLOWABLE FUNCTIONAL UNIT I

] TRIP SETPOINT VALUE

1. Reactor Vessel Water Level - Low, level 2 2 + 104.'l. inches" 2+ inches" -l
2. Reactor Vessel' Water Level - High s + 206.8 inches" s + 207 inches" 1
3. Condensate Storage Tank Level - Low a 23 feet 0 inches a 23 feet 0 inches .
t. .

a e.

v e

v I

E a '

an E

w ,

(a) Vessel water levels refer to REFERENCE LEVEL ZERO.

k e

t ENCLOSURE 6 ,

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. I AND 2 i

DOCKET NOS. 50-325 AND 50 324 LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS INSTRUMENTATION ALLOWABLE VALUE CHANGES I

r MARKED UP TECHNICAL SPECIFICATION PAGES - UNIT 2

.+. ik e .

E 5c p; TABLE 2.2.1-1 '-

n .

REACTOR PROTECTION SYSTEM INSTRtHENTATION SETPOINTS E l U FUNCT!0NAL UNIT' TRIP SETPOINT ALLOWABLEVAQQ

1. Inte mediate Range Monitor, Neutron Flux - High'd s 120 divisions of g 120 divisions of full sc le full scale
2. Average Power Range Monitor
a. Neutron Flux - High, 15%" s 15% of RATED s 15% of RATED THERMAL POWER' THERMAL POWER-
b. Flow-Blased Simulated Thermal Power - High'd* s (0.66W + 55.6%) s (0.6EW + 31%) I with a maxists with a maximum s 113.6% of RATED I s 115.3% of RATED I i

j THERMAL POWER THERMAL POWER-

_Jgg,gg

c. Fixed Neutron Flux - High" s 116.3% of RATED s , of RATED I THERMAL POWER T L POWER 3.

4.

Reactor Vessel Steam Dome Pressure - High Reactor Vessel Water Level - Low, level 1 s 1067.9 ps'ig m +153.2 inchas*

s M i 2 +153 inchesd I

5. Main Steam Line Isolation Valve - Closure'd s 10% closed
  • s 10% closed '
6. (Deleted) ^

.k 7. Drywell Pressure - High g s 2 psig l, s 2 psig *

8. - 8. Scram Discharge Volume Water Level - High s 109 gallons
  • a s 109 gallons
9. Turbine Stop Valve -: Closure'* s 10% closed 2 s 10% closed  ;

P 10. Turbine . Control Valve fast Closure, Control Oil m m 500 psig a 500 psig Pressure - Low'" .

1  ? ,

t - i m

~

s.

EE '

&=

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n- TABLE 3.3.2-2

. e.

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E._i,

- -* ALLOWABLE na TRIP TUNCTION TRIP SETPOINT VALUE

1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Leval -
1. Low, Level 1 2: + 153.2 inchss a:+ 153 inches"'  !
2. Low, level 3 2: + 14.1 inches a: + 13 inch'es l w

'b. Drywell Pressure - High s 2 psig s;2 psig le c. Main Steam Line

u. 1. (Deleted) ~

.i >

2. Pressure - Low 2: 825 psig at 825 psig
3. Flow - High ,

s 137% of rated flow s;138% of rated flow I

4. Flow - High

, s 30% of rated flow : s@6ll[of rate'd flow 'l

  • d.

N Main Steam Line Tunnel Temperature - High s 200*F s;200*F .N'33% t j[ e. ' Condenser Vacuum - Low 2: 7.6 inches Hg vacuum 2: 7.5 inches Hg' vacuum h.

  • I

~

f. Turbine Building Area Temperature - High s 200*F s 200*F ji g. Main Stack Radiation - High l (b) (b)
h. Reactor Building Exhaust Radiation - High s 11 mr/hr 111 mr/hr i

^

s

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om ,-

E x '

.. y

[

n TABLE 3.3.2-2-(Continued)

ISOLATION ACTUATION INSTRIJMENTATION SETPOINTS 2 ~

[ TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE-

.2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High s 11 mr/hr s 11 ar/hr
b. -Orywell Pressure - High
c. Reactor Vessel Water Level - Low, Level 2 s 2 psig s 2 psig- b m + 104.1 inches'd 'd+ inches'd I w
3. REACTOR WATER CLEANUP SYSTEM ISOLATION b

~

y a.'A' Flow - High s 73 gal / min U s 73 gal / min

b. Area Temperature - High s 150*F s 150*F
c. Area Ventilation Temperature A Temp - High s 50*F s 50*F
d. SLCS Initiation "

NA '

NA .

e. Reactor Vessel Water Level - Low, Level 2 m + 104.1 inches'd
  • i+% inches'd I g f. A Flow - High - Time Delay s 30 minutes s g s 30 minutes'

@ g. Piping Outside RWCU Rooms Area ,

Temperature - High s 120*F s 120*

.O M

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, TABLE 3.3.3-2

. 1 ,

z EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

~

TRIP FUNCTION ALLOWABLE

] TRIP SETPOINT VALUE'

. L CORE SPRAY SYSTEM

a. Reactor Vessel Water Level - Low, Level 3 2 + 14.1. inches" 2 + 13 inches" -

1

b. Reactor Steam Dome Pressure - Low 2 406.7 psig 2 psig JD

' I

c. Drywell Pressure - High s 2 psig 5 2 psig
d. Time Delay-Relay 14 s t s 16 secs 14 s t s 16 secs w e. Bus Power Monitor . '

L NA NA

2. LOW PRESSURE COOLANT INJECTION NODE OF RHR SYSTEM
a. Drywell Pressure - High \

s 2 psig s 2 psig

b. Reactor Vessel Water Level - Low, Level 3 2 + 14.1 inches" d + 13 inches""

I

c. Reactor Vessel Shroud Level W

2 - 53 inches" m - 5'3 inches" g d. Reactor Steam Dome Pressure - Low .

a

  • - p
1. RHR Pump Start and LCPI Valve Actuation ' M '

2

2. ' Recirculation Pt:mp Discharge Valve 2 406.7 psig 2 psig P i Actuation 2 306.7 psig

% e. RHR Pump Start - Time Delay Relay g i 9 s t s 11 seconds 9 s t s 11, seconds

. f. Bus Power. Monitor HA NA 4

i .

as ,.

E

.z-E p; TABLE 3.3.3-2 (Continued) sw e

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS g

ALLOWABLE

[- J2_tP FUNCTION TRIP SETPOINT VALUE

3. HIGH PRESSURE COOLANT INJECTION SYSTEM mi
a. Reactor Vessel Water Level - Low, level 2 2 + 104.1 inches" m + h inches" I
b. Drywell Pressure - High s 2 psig s 2 psig
c. Condensate Storage Tank Level - Low 2 23 feet 4 inches- 2 23 feet.4 inches
d. . Suppression Chamber Water Level - High s -2 feet
  • s -2 feet"'
e. Bus Power Mon'itor NA NA
4. AUTOMATIC DEPRESSURIZATION SYSTEM
a. ADS Inhibit Switch NA NA
b. Reactor Vessel Water Level - Low, level 3 m + 14.1 inches" d + 13 inches" .

I~

g c. Reactor Vessel Water Level - Low, level I h + 153.2 inches" m + 153 inchesN 1 y d. ADS Timer s 83 seconds s 108 seconds

'~

m. .,-

l

% e. Core Spray Pump Discharge Pressure - High a 112.1 psig i

= 2 102 psig ,

I'.

l

. f. RHR (LPCI MODE) Pump Discharge Pressure - High a 111.1 psig d 102 psig- l 3 g. Bus Power Nonitor NA NA 4

G e

O 4

TABLE 3.3.6.1-2 .

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS-

-TRIP , -ALLOWABLE Jolj .

-TRIP FUNCTION . SETPOINT VALUE id -

1. Reactor Vessel Water 4evel - a + 104.1 inches'd k + h nches ~i Low, level 2 *
2. Reactor Vessel Pressure - High s 1137.8 psig s psig: l

, /NT

'd Vessel water levels refer to REFERENCE LEVEL ZERO.

' BRUNSWICK - UNIT 2 3/4 3 Amendment No. 214 1

g, .

. 3

= . . .

~

g- ,

Si 5 ,

>R TABLE 3.3.7-2

.i .,

c  : REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMEhTATION SETP E .

j

[ FUNCTIONAL UNIT.

TRIP SETPolNT ALLOWABLE VALUE NJ C 1.- Reactor Vessel Water Level.- Low, level 2. '#

m + 104.1 inches" 2+ inches" l.

2. Reactor. Vessel Water Level - High s +206.8 inches" ;s +207 inches" 'I-3e . Condensate Storage Tank. Level - Low a 23 feet 0 inches = 23 feet O' inches

-3 i  !

y l El-ra .

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(a) Vessel water levels refer to REFERENCE LEVEL ZERO.  ! -

t emmum

- g.

w g-%,, g _ q+9.sy.- a yto w w - + e-M 't r a-<mn a- *1 _ m_- aA - _ - - - -

il'

\

ENCLOSURE 7:

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 --

DOCKET NOS. 50-325 AND 50-324 *

- LICENSE NOS. DPR AND DPR REQUEST FOR LICENSE AMENDMENTS - ,

INSTRUMENTATION ALLOWABLE VALUE CHANGES T

7 TYPED TECilNICAL SPECIFICATION PAGES - UNIT 1 1

.' \ .

~

.C z

.?E.

T; _ TABLE 2.2.1-1 x

J' REACTOR PROTECTION SYSTEM INSTRUMENTATION SETP0INTS g

FUNCTIONAL UNIT ' TRIP SETPOINT ALLOWABLE VALUES

1. Intermediate Range Monitor. Neutron Flux - High"' s 120 divisions of s 120-divisions of-full scale full scale
2. Average Power Range Monitor
a. Neutron Flux - High.15%'d s 1.5% of RATED s 15% of RATED.

THERMAL POWER THERMAL POWER

b. Flow-Biased Simulated Thermal Power - High"* s (0.66W + 59.6%) s (0.66W + 61%)

with a maximum with a maximum s 113.6% of RATED s 115.3% of. RATED  !

2 THERMAL POWER THERMAL POWER

c. Fixed Noutron Flux - High'* s 116.3% of RATED s 118.5% of RATED I .l THERMAL POWER THERMAL POWER  :
3. Reactor Vessel Steam Dome Pressure - High 5 106/.9 psig ~s 1077 psig I
4. Reactor Vessel Water Level - Low. Level 1 2 +153.2 inches'O 2 +153 inches'"
5. Main Steam Line Isolation Valve - Closure") s 10% closed 5 10% closed
6. (Deleted) g 7. .Drywell Pressure - High s 2 ps19 s 2 psig

{ 8. Scram Discharge Volume Water Level - High 5 109 ga'lons s 109 gallons

@ 9. Turbine Stop Valve - Closure'" s 10% closed s 10% closed

[ l'1 Turbine Control Valve Fast Closure. Control Oil = 500 psig = 500 psig o Pressure . - Low'"

---___L '_ _ . 2 g-g7 w y

.sg h

TABLE 3.J.2-2 (Continue M n

JSOLATION ACTUATION Ift;1 JMENTATION SETPOINTS -

E ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE

2. SECONDARY CONTAINMENT ISOLATION P
a. Reactor Building Exhatst Radiation - High s 11 mr/hr s 11 mr/hr
b. Drywell Pressure - High s 2 psig s 2 psig
c. Reactor" Vessel Water Level - Low. Level 2 z + 104.1 inches 2 + 101 inches  !

-$ 3. REACTOR WATER CLEANUP SYSTEM ISOLATION 1

e

a. A Flow - High s 73 gal / min s 73 gal / min l b. Area Tenperature - High 5 150*F s 150*F' t c. Area Ventilation A Temperature - High s 50*F s 50*F
d. SLCS Initiation NA NA
e. Reactor Vessel Water Level - Low. Level 2 = + 104.1 inches = + 101 inches I ,

g f. A Flow - High - Time Delay 5 30 minutes s 30 mirstes h g. Piping Outside RWCU Rooms Area s 120*F s 120*F g Temperature - High '

e T

i i

___. _ _ _ _ _ _ . . . _ . _ - . . . - . - _ . . _ . . _ . _ . . . ~ . . . , _ . . - , _ . _ _ _ _ _ . . -

~

p; TABLE 3.3.3-2

-n EMERGENCY CORE C00LItG SYSTEM ACTUATION INSTPUMENTATION SETPOINTS E

a ALLOWABLE

,_. TRIP FUNCTION _T_ RIP SETPOINT VALUE 1 CORE SPRAY SYSTEM ,

a. Reactor Vessel Water Level - Low. Level 3 = + 14.1 inches *' 2 + 13 inches *'
b. Reactor Steam Dome Pressure - Low 2 406.7 psig a 402 psig 1

-c. Drywell Pressure - High s 2 psig s 2 psig

$ d. Time Delay-Relay 14 s t s 16 secs 14 5 t s 16 secs

[ e. Bus Power Monitor NA NA e

2 LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a. Drywell Pressure - High s 2 psig 5 2 psig
b. Reactor Vessel Water Level - Low. Level 3 = + 14.1 inches *' = + 13 inches *'
c. Reactor Vessel Shroud Level = - 53 inches *' = - 53 inches *'

g d. Reactor Steam Dome Pressure - Low f

3 1.

2.

RHR Fump Start and LCPI Valve Actuation Recirculation Pump Discharge Valve 2 406.7 psig = 402 psig I

= Actuation a 306.7 psig

.g = 302 psig i

e. RHR Pump Start - Time Delay Relay 9 s + s 11 seconds 9 s t s 11 seconds
f. Bus Power Monitor NA NA

E E

E g TABLE 3.3.3-2 (Continuad) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMF5TATION SETPOINTS E

q ALLOWABLE

- TRIP FLHCTION TRIP SETPOINT VALUE

3. HIGH PRESSURE COOLANT INJECTION SYSTEM
a. Reactor Vessel Water Level - Low. Level 2 = + 104.1 inches *' = + 101 inches ** I
b. Drywell Pressure - High s 2 psig s 2 psig
c. Condensate Storage Tank Level - Low = 2'l feet 4 inches = 23 feet 4 inches

$ _d. Suppression Chamber Water level - High s -2 feet"' s -2 feet

e.>

a o

e. Bus Power Monitor FM tm
4. AUTOMATIC DEPRESSURIZATION SYSTEM
a. ADS Inhibit Switch fM NA

-b. Rei.ctor Vessel Water Level - Low. Level 3 = + 14.1 inches *' = + 13 inches *'

c. Reactor Vessel Water Level - Low. Level 1 = + 153.2 inches *' = + 153 inches **

g d. ADS Timer s 83 seconds s 108 seconds 3 3 g e. Core Spray Pump Discharge Pressure - High = 112.1 psig = 102 psig ,

A f. RHR (LPCI MODE) Pump Discharge Pressure - High = 111.1 psig = 10m psig z

P g. Bus Power Monitor NA iM f

9

TABLE 3.3.6.1 2

. A NS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS i

TRIP ALLOWABLE IFIPFUNCTION SETPOINT VALUE

1. Reactor Vessel Water Level - = + 104.1 inches (d = + 101 inches (d l Low. Level 2 .

I

2. Reactor Vessel Pressure - High 5 1137.8 psig s 1147 psig r

'" Vessel water levels refer to REFERENCE LEVEL ZERO, BRUNSWICK - UNIT 1 3/4 3 90 Amendment No.

I- _._ __

O s .

.jg h.

j. TABLE 3.3.7-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRbHEhTATION SETPOINTS

!E Q- ALLOWABLE ,

- FUNCTIONAL UNIT TRIP SETPOINT VALUE

1. Reactor Vessel Water Level - Low. Level 2 = + 104.1 inches"' = + 101 inches"' - I
2. Reactor Vessel Water Level - High r + 206.8 inches s + 207 inches"'
3. Condensate Storage Tank Level - Low = 23 feet 0 inches = 23 feet 0 inches u

2 '

Y R

3 a

a

!?

(a) Vessel water levels refer to REFERENCE LEVEL ZERO. I

- . . y. - - . . - - - . .

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

d

  • i i

ENCLOSURE 8

'~

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS,1 AND 2 DOCKET NOS. 50 325 AND 50 324

. LICENSE NOS. DPR 71 AND DPR 62 >

REQUEST FOR LICENSE AMENDMENTS

INSTRUMENTATION ALLOWABLE VALUE C11ANGES ,

l T

i TYPED TECllNICAL SPECIFICATION PAGES - UNIT 2 b

t 1

)

, ~ , - . ..,e .-, -. ,--w'_,,.---<c--w-., . - - , ,,.,,-,------,.rs62--- ,.N., . _ -,y.y ,n ,. , , , , mre ,,. , . _ , -, , , , . - -. ~ , . * . , -

a E '

M TABLE 2.2.1-1 n

REACTOR PROTECTION SYSTEN INSTRUMENTATION SETPOIKTS

- E-  :

-FUNCTIONAL UNIT

[ TRIP SETPOINT ALLOWABL VALUES

.1. Interr.ediate Range Monitor. Neutron Flux - High* s 120 divisions of s 120 divisions of full scale full scale I 2. Average Power Range Monitor

a. Heutron Flux - High. 15%* s 15% of RATED s 15% of RATED  :

. THERMAL POWER THERMAL POWER

b. Flow-Biased Simulated Thermal Power - High""" s (0.66W + 59.6%) s (0.66W + 61%)

with a maximum with a maximum s 113.6% of RATED s 115.3% of RATED  ;

THERMAL POWER

{ THERMAL POWER i i- c. Fixed Neutron Flux - High* s 116.3% of RATED s 118.5% of RATED I THERMAL POWER ThTRMAL P0wER  !

3. Reactor Vessel Steam Dome Pressure - Hign s 1067.9 psig 5 1077 psig i  ;
4. Reactor Vessel Water Level - Law. Level 1 = +153.2 inches'# = +153 inches'" [
5. Main Steam Line Isolation Valve - Closure
  • s 10% closed 5 10% closed
6. (Deleted)
7. Drywell Pressure - High s 2 psig s 2 psig I a 8. Scram Discharge Volume Water Level - High s 109 gallons s 109 gallons i a

,8o 9. Turbine Stop Valve - Closure'" s 10% closM s 10% closed

" i

10. Turbine Control Valve Fast Closure. Control Oil = 500 psig = 500 psig l

,5 Pressure - Low'"

I L

I i

i . , _ . . _ .- _ . , - - . _ . . . _ _ _ - _ _ - . _ _ - _ . . - . , . - _ , _ .

._,-.__-..,._,_-_...__--_,..I

m - - .

~

5 E. ,

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^

TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

.E Q ALLOWABLE m -TRIP FUNCTION TRIP SETPOINT VAllE

1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Level -
1. Low. Level 1 2 + 153.2 inches = + 153 inches
2. Low. Level 3 = + 14.1 inches = + 13 inches
b. Drywell Pressure - High s 2 psig s 2 psig ca c. Main Steam Line
4. 1. (Deleted) co
2. Pressure - Low a 825 psig = 825 psig
3. Flow - High 5137% of rated flow s 138% of rated flow
4. Flow - High s 30% of rated flow s 33% of rated flow I
d. Main Steam Line Tunnel Temperature - High 5 200*F s 200*F g e. Condenser Vacuum - Low a 7.6 inches Hg vacuum = 7.5 inches Hg vacuum
f. Turbine Building Area Temperature - High s 200*F s 200*F f

A g. Main Stack Radiation - High (b) (b) 5

h. Reactor Building Exhaust Radiation - High s 11 mr/hr 5 11 mr/hr

s .

E.

E E

R n-TABLE 3.3.2-2 (Continued)

, ISOLATION ACTUATION INSTRLMENTATION SETPOINTS p ALLOWABLE y TRIP FUNCTION TRIP SETPOINT VALLE

2. SECONDARY CONTAINMENT ISOLATION
a. Reactor Building Exhaust Radiation - High s 11 mr/hr s 11 mr/hr
b. Dryrell Pressure - High 5 2 psig s 2 psig
c. Reactor Vessel Water Level - Low. Level 2 = + 104.1 inches = + 101 inches I

$ 3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High s 73 gal / min s 73 gal / min
b. Area Temperature - High s 150*F s 150*F
c. Area Ventilation Temperature A Temp - High 5 50*F s 50*F
d. SLCS Initiation NA NA
e. Reactor Vessel Water Level - Low. Level 2 = + 104.1 inches = + 101 inches I g f. A Flow - High - Time Delay s 30 minutes s 30 minutes

.h g. Piping Outside RWCU Rooms Area s 120*F s 120' g Temperature - High n

O r - - - , . . - + - - - - - - . , . , - - . - -

s .

E

.g .

E

.;; TABLE 3.3.3-2 n

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E

q ALLOWABLE m TRIP FLOCTION TRIP SETPOINT VALUE

1. CORE SPRAY SYSTEM
a. Reactor Vessel Water Level - Low. Level 3 = + 14.1 inches *' = + 13 inches *'
b. Reactor Steam Dome Pressure - Low a 406.7 psig a 402 psig I
c. Drywell Pressure - High s 2 psig s 2 psig

$ d. Time Delay-Relay 14 s t s 16 secs 14 s t s 16 secs

[ e. Bus Power Monitor fM NA e -

2. LOW PRESSURE COOLANT ,;UECTION MODE OF RHR SYSTEM
a. Drywell Pressure - High s 2 psig s 2 psig
b. Reactor Vessel Water Level - Low. Level 3 = + 14.1 inches *' = + 13 inches *'
c. Reactor Vessel Shroud Level 2 - 53 inches ** = - 53 inches *'

> d. Reactor Steam Dame Pressure - Low R

E- 1. RHP, Pump Start and LCPI Valve

" 2.

Actuation Recirculation Pump Discharge Valve a 406.7 psig a 402 psig i y Actuation = 306.7 psig a 302 psig i

e. RHR Pump Start - Time Delay Relay 9 s t s 11 seconds 9 s t s 11 seconds
f. Bus Power Monitor NA tM 4

, . , , .--r. m,,, . - , - - - ..

1 s .

?

M x .> .

TABLE 3.3.3-2 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E

. p ALLOWABLE

TRIP FUNCTION TRIP SETPOINT y VALUE
3. HIGH PRESSURE COOLANT INJECTION SYSTE'i

! a. Reactor Vessel Water Level - Law. Level 2 = + 104.1 inches *' = + 101 inches *' I

b. Drywell Pressure - High 5 2 psig s 2 psig.
c. Condensate Storage Tank Level - Low = 23 feet 4 inches = 23 feet 4 inches

$ d. Suppression Chamber Water Level - High 5 -2 feet s -2 feet

o

e. Bus Power Monitor NA NA
4. AUTOMATIC DEPRESSURIZATION SYSTEM
a. ADS Inhibit Switch e NA NA
b. Reactor Vessel Water Level - Low. Level 3 = + 14.1 inches *' = + 13 inches *
c. Reactor Vessel Water Level - Low. Level 1 = + 153.2 inches * = + 153 inches
  • g d. ADS Timer s 83 seconds s 108 seconds E e. Core Spray Pump Discharge Pressure - High = 112.1 psig = 102 psig 8

A f. RHR (LPCI MODE) Pump Discharge Pressure - High = 111.1 psig = 102 psig z

P g. Bus Power Monitor NA NA

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

e

  • I i

TABLE 3.3.6.1-2 elWS_ RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATLON_ SETPOINTS TRIP ALLOWABLE TRIP FUNCTIQ1{ SETPolNT VALUE

1. Reactor Vessel Water Level - a + 104.1 inches (*) = + 101 inches (*) I r Low, level 2
2. Reactor Vessel Pressure - High s 1137.8 psig s 1147 psig 1-

Vessel water levels refer to REFERENCE LEVEL ZERO, BRUNSWICK - UNIT 2 3/4 3-91 Amendment No,

.o O

E '

E E

R n

TABLE 3.3.7-2

. REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRlHENTATION SETPOINTS E

a ALLOWABLE y FUNCTIONAL UNIT TRIP SETPOINT VALUE

1. Reactor Vessel Water Level - Lcw. Level 2 a + 104.1 inches = + 101 inches I
2. Reactor Vessel Water Level - High s +206.8 inches s +207 inches
3. Condensate Storage Tank Level - Low a 23 feat 0 inches a 23 feet 0 inches a

k Y

E

~

a if (a) Vessel water levels refer to REFERENCE LEVEL ZERO.

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