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

. _.7

'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

-TABLE 2.2.1-1

- n a

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS E

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

,gg7

'~

c.

Fixed Neutron Flux - High**

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

' 6.

(Deleted) o 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 2 500 psig 2 500 psig Pressure - Low" 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 s 73 gal / min

$7 E$

b.

Area Temperature - High s 150*F ms 150*F c.

Area Ventilation A Temperature - High s 50*F

s 50*F b

d.

SLCS Initiation NA NA i

e.

Reactor Vessel Water Level - Low, Level 2 m + 104.1 inches

2: +

inches"'

i Fj[

f.

A Flow - High - Time Delay s 30 minutes

=s30 air.utes g.

Piping Outside RWCU Rooms Area s 120*F

s120*F r*

Temperature - High y

ed C3 W

i 9

h

+

.w-v

y E

c2 E

TABLE 3.3.3-2 x-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

ig l

=

2.

Recirculation Pump Discharge Valve

?

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 NA i

1 S

~

EE'

E TABLE 3.3.3-2 (Continued)
n '

EMERGEMCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS

?

~'[.

TRIP FUNCTION ALLOWABLE TRIP SETPOINT VALUE

3. HIGH PRESSURE COOLANT INJECTION SYSTEM IDI Reactor. Vessel Water level - Low, Level 2 2 + 104.1 inches" k+

inches" i

a.

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.

1 Suppression Chamber Water Level - High s -2 feet" 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

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

e.

,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 TRIP FUNCTION SETPOINT-.

ALLOWABLE O

TRIP 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

]

FUNCTIONAL UNIT ALLOWABLE 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

Ea 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 DOCKET NOS. 50-325 AND 50 324 i

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

E5cp; 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.

Reactor Vessel Steam Dome Pressure - High s 1067.9 ps'ig s

M i

4.

Reactor Vessel Water Level - Low, level 1 m +153.2 inchas*

2 +153 inchesd I

(

5.

Main Steam Line Isolation Valve - Closure'd s 10% closed s 10% closed 6.

(Deleted)

^

.k 7.

g Drywell Pressure - High s 2 psig l,

s 2 psig

8. -

8.

Scram Discharge Volume Water Level - High s 109 gallons s 109 gallons a

9.

Turbine Stop Valve -: Closure'*

s 10% closed s 10% closed 2

P 10.

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

m 1

?

t

- i m

~

s.

EE '

,,E -

=

TABLE 3.3.2-2 n-e.

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E._i, TRIP TUNCTION ALLOWABLE TRIP SETPOINT VALUE na

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

'b.

Drywell Pressure - High s 2 psig s;2 psig w

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

. N'33%

s;200*F.

t j[

' Condenser Vacuum - Low e.

2: 7.6 inches Hg vacuum 2: 7.5 inches Hg' vacuum I

h.

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

o I

om E

x

.. y

[

TABLE 3.3.2-2-(Continued) n ISOLATION ACTUATION INSTRIJMENTATION SETPOINTS 2

~

[

TRIP FUNCTION ALLOWABLE TRIP SETPOINT VALUE-

.2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High s 11 mr/hr s 11 ar/hr

b. -Orywell Pressure - High s 2 psig s 2 psig-b Reactor Vessel Water Level - Low, Level 2 m + 104.1 inches'd

'd+

inches'd I

c.

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

~

wb y

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

b.

Area Temperature - High s 150*F s 150*F Area Ventilation Temperature A Temp - High s 50*F s 50*F c.

d.

SLCS Initiation NA NA Reactor Vessel Water Level - Low, Level 2 m + 104.1 inches'd i+% inches'd I

e.

  • g f.

A Flow - High - Time Delay s 30 minutes g

s 30 minutes' s

g.

Piping Outside RWCU Rooms Area s 120*F Temperature - High s 120*

.O M

4*

a memo y

4 4

Je

as.

2 E

TABLE 3.3.3-2 x

1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS "z

~

]

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 JD 2 406.7 psig 2

psig I

Drywell Pressure - High s 2 psig 5 2 psig c.

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* -

1.

RHR Pump Start and LCPI Valve p

Actuation M

P

2. ' Recirculation Pt:mp Discharge Valve 2 406.7 psig 2

psig i

2 Actuation 2 306.7 psig g

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

. 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~

c.

Reactor Vessel Water Level - Low, level I h + 153.2 inches" m + 153 inchesN g

1 y

d.

ADS Timer s 83 seconds s 108 seconds

~

l m.

e.

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

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

1. Reactor Vessel Water 4evel -

a + 104.1 inches'd k + h nches

~i id -

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-Si5

>R TABLE 3.3.7-2

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMEhTATION SETP

. i cE j

[

FUNCTIONAL UNIT.

ALLOWABLE NJ C TRIP SETPolNT VALUE 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 i

g.

i E.

l

- g a

' E S

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

~

t emmum

- g.

g-%,,

w 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) 7.

.Drywell Pressure - High s 2 ps19 s 2 psig g

{

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 Pressure. - Low'"

o 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 a.

A Flow - High s 73 gal / min s 73 gal / min 1

e 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 f.

A Flow - High - Time Delay 5 30 minutes s 30 mirstes g

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 Ea 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 *'

d.

Reactor Steam Dome Pressure - Low g

f 1.

RHR Fump Start and LCPI Valve Actuation 2 406.7 psig

= 402 psig I

3 2.

Recirculation Pump Discharge Valve

=

Actuation a 306.7 psig

= 302 psig i

.g 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 EEg TABLE 3.3.3-2 (Continuad) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMF5TATION SETPOINTS Eq 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 e.

Bus Power Monitor FM tm o

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 e.

Core Spray Pump Discharge Pressure - High

= 112.1 psig

= 102 psig g

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 3a

<%a

!?

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

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)

I 7.

Drywell Pressure - High s 2 psig s 2 psig 8.

Scram Discharge Volume Water Level - High s 109 gallons s 109 gallons i

aa

,8 9.

Turbine Stop Valve - Closure'"

s 10% closM s 10% closed o

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.

-E R

TABLE 3.3.2-2

^

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

.E Q

ALLOWABLE

-TRIP FUNCTION TRIP SETPOINT VAllE m

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 e.

Condenser Vacuum - Low a 7.6 inches Hg vacuum

= 7.5 inches Hg vacuum g

f f.

Turbine Building Area Temperature - High s 200*F s 200*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.

EE R

TABLE 3.3.2-2 (Continued) n-ISOLATION ACTUATION INSTRLMENTATION SETPOINTS p

ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALLE y

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 Eq ALLOWABLE TRIP FLOCTION TRIP SETPOINT VALUE m

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 1

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 Actuation a 406.7 psig a 402 psig i

2.

Recirculation Pump Discharge Valve 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 TABLE 3.3.3-2 (Continued) x EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E

p ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE y

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

e.

Bus Power Monitor NA NA o

4. AUTOMATIC DEPRESSURIZATION SYSTEM a.

ADS Inhibit Switch NA NA e

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

  • d.

ADS Timer s 83 seconds s 108 seconds g

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

=_.

I e

TABLE 3.3.6.1-2 i

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 EE R

TABLE 3.3.7-2 n

. REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRlHENTATION SETPOINTS Ea ALLOWABLE FUNCTIONAL UNIT TRIP SETPOINT VALUE y

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 ak Y

E

~

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

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