Text

Proposed Tech Specs Re Main Stack Radiation Monitor
	ML20155B161
Person / Time
Site:	Brunswick
Issue date:	09/27/1988
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20155B158	List: ML20155B155; ML20155B161;
References
	NUDOCS 8810060213
	Download: ML20155B161 (21)
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ENCLOSURF 1 BRUNSWICK STEAM ELECTRIC PIANT. UNTTE 1 AND 2 NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT MAIN STACK RADIATION MONITOR l

INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications (Appendix A to Operating Licenses DPR 71 and DPR 62) would be incorporated as follows:

UNIT 1 Remove Pagg Insert Page 3/4 3 12 3/4 3-12 3/4 3 16 3/4 3 16 3/4 3 18 3/4 3 18 3/4 3 18a 3/4 3 21 3/4 3 21 3/4 3 21a 3/4 3-23 3/4 3 23 3/4 3-26 3/4 3 26 UNIT 2 Remove Parc Insert Pare i

3/4 3 12 3/4 3-12 3/4 3 16 3/4 3 16 3/4 3 16a 3/4 3 16a 3/4 3 18 3/4 3 18 3/4 3 18a 3/4 3 21a 3/4 3-21a 3/4 3 23 3/4 3 23 3/4 3 26 3/4 3 26 t

{

8810060213 G80927 PDR P

ADOCK 050CH3324 i

PNU f

E3-1

O

+

ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 6 50 324 OPERATING LICENSES DPR 716 DPR 62 REQUEST FOR LICENSE AMENDMENT MAIN STACK RADIATION MONITOR

SUMMARY

LIST OF REVISIONS UNIT 1 Pages Descrintion of Changes 3/4 3 12 Adds Main Stack Radiation High and applicable information to Table 3.3.2 1.

3/4 3 16 Adds Action 28 and Note (h) to Table 3.3.2-1.

3/4 3 18 Adds Main Stack Radiation High and applicable information to Table 3.3.2 2.

3/4 3 18a Ropagination only.

3/4 3 21 Footnote moved "as is" to Notes portion of Table 3.3.2 2.

3/4 3 21a Adds Nccas section and Note (a) and inco1porates footnote (*) from page 3/4 3 21 to Table 3.3.2 2.

3/4 3 23 Adds Main Stack Radiation High and applicable information to Table 3.3.2-1.

3/4 3 26 Adds Main Stack Radiation High and applicable information to Table 4.3.2 1.

UNIT 2 P8 r.e s Descrintion of changes 3/4 3 12 Adds Main Stack Radiation - High and apr'.acable information to Table J.3.2 1.

E4-1

9 3/4 3 16 Adds Action 28 and corrects editorial errors to Table 3.3.2 1.

3/4 3 16a Adds Note (i),; corrects editorial error and repaginates.

3/4 3-18 Adds Main Stack Radiation High and applicable information to Table 3.3.2 2.

3/4 3 18a Repagination only.

3/4 3.11a Adds Note (c) to Table 3.3.2 2.

3/4 3 23 Adds Main Stack Radiation High and applicable information to Table 3.3.2 3.

3/4 3 26 Adds Main Stack Radiation High to Table 4.3.2-1.

E4 2

ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PIANT, UNIT 1 NRC DOCKETS 50-325 OPERATING LICENSES DPR-71 REQUEST FOR LICENSE AMENDMENT MAIN STACK RADIATION MONITOR TECHNICAL SPECIFICATION PAGES

(BSEP-1-142) j' TABLE 3.3.2-1 (Continued)

E un ISOLATION ACTUATION INSTRUMENTATION N

O VALVE CROUPS MINIMUM NUMBER APPLICABLE 3

OPERATED BY OPERABLE CHANNELS OPERATIONAL TdIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)_

PER TRIP SYSTEM (b)(c)

CONDITION ACTION

U PRIMARY CONTAINMENT ISOLATION (Continued)

~

d.

Main Steam Line Tunnel Temperature - High 1

2(d) 1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-T3-N012A,P,C,D; B21-TS-N013A,B,C,D) u, e.

Condenser Vacuum - Low 1

2 1, 2 ")

I 21 3

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

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

f.

Turbine Building Area Temperature - High 1

4(d) 1 2 3 21 (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,0; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) g.

Main Stack Radiation - High (h) 1 1,2,3 28 a-

.O

(BSEP-1-142)

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21 - Be in at least 3 TART-UP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least START-UP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - Establish SECONDARY CONTAINMENT INTECRITY with the standby gas treatment system operating within one hour.

ACTION 24 - Isolate the reactor water cleanup system.

ACTION 25 - Close the affected system isolation valves and declare the affecced system inoperable.

ACTION 26 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 - Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

ACTION 28 - Close the affected isolation valves within 14 days or b3 in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NOTES When handitng irradiated fuel in the secondary containment.

(a)

See Specification 3.6.3.1. Table 3.6.3.1-1 for valves in each valve group.

(b)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surweillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(c)

With only one channel per trip system. an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

(d)

A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABIE.

(e)

With reactor steem pressure > 500 psig.

(f)

Closes only RWCU outlet isolation valve.

(g)

Alarm only.

(h)

Isolates containment purge and vent valves.

l BRUNSWICK - UNIT 1 3/4 3-16 Amenu a

(BSEP-1-142)

\\

g TABLE 3.3.2-2 (Continued)

Eg ISOIATION ACTUATION INS'ittBIENTATION SETFOINTS E

M ALI#dABLE a

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE E

Q PRIMARY CONTAllDIENT ISOLATION (Continued) d.

risin Steam Line Tunnel emperature - High

< 200*F

< 200*F (521-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS N012A,B,C,D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low

> 7 inches Hg vacuum

> 7 inches Hg vacuum (821-PTM-N056A-1,5-1,C-1,D-1) j w

Y (B21-TS-3225A,B,C,D;

~< 200*F

~< 200*F f.

Turbine soilding Area Temp - High 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-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) g.

Main Stack Radiation - High (a)

(a) a

,a, O

,l

(BSEP-1-143) g TABLE 3.3.2-2 (Continued)

Ey ISOLATION ACTUATION INSTRLHENTATION SETPOINTS E

M ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE E

Q PRIMARY CONTAINMENT ISOLATION (Continued) 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust a.

Radiation - liigh

< 11 mr/hr

< 11 mr/hr (DI2-RM-N010A,B) b.

Drywell Pressure - High

< 2 psig

< 2 psig (C71-PIM-N002A-1,B-1,C-1,D-1)

U c.

Reactor Vessel Water Level -

Y (B21-LTM-NO24A-1,B-1 and

~> + 112 inches *

~> + 112 inches

Iow, Level 2 E

B21-LTM-NO25A-1,B-1) i

(BSEP-1-142)

~.

5 TABLE 3.3.2-2 (Continued)

Eg IS01ATION ACTUATION INSTRLHENTATION SETPOINTS E^

ALLOWABLE TRIP FUNCTION AND INSTRUMENT NLHBER TRIP SETPOINT VALUE E;;

4.

RCIC Steam Line Tunnel Temp - High

< 175*F

< 175*F (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 5.

Bus Power Monitor NA NA (E51-K42 and E51-K43) w 6.

RCIC Turbine Exhaust Diaphragm (E51-PS-N012A,B,C D)

~< 10 psig T

Psessure - High

< 10 psig 7.

RCIC Steam Line Ambient Temp - High

< 200*F

< 200*F (E51-TS-N603A,5) 8.

RCIC Steam Line Area A Temp - High

~< 50*F

~< $0*F (E51-dTS-N604A,B) 9.

RCIC Equipment Room Ambient Temp - High

< 175*F

< 175'P (E51-TS-N602A,B)

(E51-dTS-N601A,B)

~< 50*F

~< 50*F 10.

RCIC Equpment Room A Temp - High o

5.

SHUTDOWN C00LINC SYSTEM ISOLATION a

a.

Reactor Vessel Water Level -

l Low, Level 1

> + 162.5 inches *

> + 152.5 inches *

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

Reactor Steam Dome Pressure - High

< 140 psig

< 140 psig (B32-PS-N018A,B)

- g (BSEP-l*142)

TABLE 3.3.2-2 (Continued)

ISOI.ATION ACTUATION INSTRUMENTATION SETPOINTS NOTES (a)

Establish alarm / trip setpoints per the methodology contained in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

Vessel water levels refer t.o R?,FERENCE LEVEL ZERO.

L BRUNSWICK - UNIT 1 3/4 3-21a Amendment No.

(BSEP-1-142) l TABLE 3.3.2-3 (Continued)

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

PRIMARY CONTAINMENT ISOLATION (Continued) f.

Turbine Building Area Temperature - High NA (521-TS-3225A,8,C,D)

B21-TS-3226A,B.C Dt 521-TS-3227A,B,C,DI B21-TS-3225A,B,C,DI B21-TS-3229A,B,C,DI B21-TS-3230A,B,C,DI B21-TS-3231A,B,C,DI B21-TS-3232A,B,C,D)

Main Stack Radiation - High(b)

$ 1.0*

3 2.

SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b)

$g3 a.

(D21-RM-N010A,5) b.

Drywell Pressure - High

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

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

Reactor Vessel Water Level - Low, Level 2 11.0*

(B21-LT-N024A-1,5-1 and 821-LT-N025A-1,5-1)

(521-LTM-N024A-1,B-1 and 521-LTM-N025A-1,8-1) 3.

REACTOR WATER CLEANUP SYS'.EM ISOLATION a.

A Flow - High

<13

~

(C31-dFS-N603-1A,15) b.

Area Temperature - High

$13 (C31-TS-N600A,B,C.D.E.F) c.

Area Ventilation Temperature AT - High

$13 (C31-TS-N602A,B,C.D E,F) d.

SLCS Initiation NA (C41A-51) e.

Reactor Vessel Water Level - Low, Level 2 11.0*

(B21-LT-NO24 A-1,B-1 and B21-LT-N025 A-1,B-1)

(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1)

BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.

I (BSEP-1-142) g TABLE 4.3.2-1 (Continued)

Ey ISOLATION ACTUATION INS"RUMENTATION SURVEILLANCE REQUIRDENTS E^

GANNEL OPERATIONAL l

GANWFL FUNCTIONAL GANKL CONDITIONS IN WHIG E

TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED U

l PRIMARY CONTAIIstENT ISOLATION (Continued) d.

Main Steam Line Tunnel i

Temperature - High NA M

R 1, 2, 3 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) w e.

Condenser Vacuum - Low NA *}

NA R(b) y, yg I

3 (B21-PT-N056A,B,C,D)

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

D M

M 1, 2#

u f.

Turbine Building Area Temp-High NA M

R 1, 2, 3 (821-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-322BA,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) g.

Main Stack Radiation - High NA Q

R 1,2,3

$n.

E E

o

'E o

ENCIDSURE 6 BRUNSVICK STEAM ELECTRIC PIANT, UNIT 2 NRC DOCKETS 50 324 OPERATING LICENSES DPR 62 REQUEST FOR LICENSE AMENDMENT MAIN STACK RADIATION MONITOR TECHNICAI, SPECIFICATION PAGES

(ESEP-2-144)

A TABLE 3.3.2-1 (Continued)

Ey ISOLATY7N ACTUATION INSTRUMENTATION E

X VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)

PER TRIP SYSTEM (b)(c) CONDITION ACTION U

PRIMARY CONTAINMENT ISOLATION (Continued) u 4.

Flow - High 1

2 2, 3 21 (B21-PDTS-N00dA-2; B21-PDTS-N007B-2; B21-PUTS-N008C-2; B21-PDTS-N009D-2) d.

Main Steam Line Tunnel ti Temperature - High 1

2(d) 1, 2, 3 21 (B21-TS-N010A,B,C,D; y

B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D)

I 1, 2 *)

21 e.

Condenser Vacuum - Low 1

2 (B21-PT-N056A,B,C,D)

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

Turbine Building Area Temperature - High 1

4(d) 1, 2, 3 21 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; 5.

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

. f*

B21-TS-3229A,B,C,D; E

B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; z

B21-TS-3232A,B,C D) g.

Main Stack Radiation - High (i) 1 1,2,3 28

e (BSEP-2-144)

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - Establish SECONDARY CONTAINHENT INTEGRITY with the standby gas treatment system operating within one hour.

ACTION 24 - Isolate the reactor water cleanup system.

ACTION 25 - Close the affected system isolation valves and declare the affected system inoperable.

ACTION 26 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 - Deactivate the shutdown cnoting supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

ACTION 28 - Close the affected isolation valves within 14 days or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NOTES When handling irradiated fuel in the secondary containment.

(a) See Specification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve group.

(b) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition psovided at least one other OpERABLC channel in the same trip system is monitoring that parameter.

(c) With only one channel per trip system, an inoperable channel need not be placed in the tripped condition where thia would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

(d) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

BRUNSWICK - UNIT 2 3/4 3-16 Amendment No.

o

'6 (BSEP-3-144)

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION NOTES (e)

With reactor steam pressure > 500 psig.

(f)

Closes only RWCU outlet isolation valve.

(g)

Alarm only.

(h)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of rated thermal power, the normal full power radiation background level and associated trip setpoints may be changed based on a calutated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and the assoelated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor power levels below 22% of rated thermal power, while these functions are required to be operable.

(i)

Isolates containment purge and vent valves.

l BRUNSWICK - UNIT 2 1/4 3-16a Amendment No.

(BSEP-2-144) a TABLE 3.3.2-2 (Continued)

Ey ISOLATION ACTUATION INSTRUMENTATION SETPOINTS n

M ALIANABLE TRIP FUNCTION AND INSTRUMENT NtBfBER TRIP SETPOI:."T VALUE E

Q PRIMARY CONTAIIStENT ISOLATION (Continued) os d.

Main Steam Line Tunnel Temperature - High

< 200*F

< 200*F (821-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS N012A,s,C,D; B21-TS-N013A,B,L,D) e.

Condenser Vacuum - Low 3 7 inches Hg vacuum 3 7 inches Hg vacuum (B21-P"Dt-N056A-1,8-1,C-1,D-1) w E

f.

Turbine Building Area Temp - High

< 200*F

< 200*F y

(B21-TS-3225A,B,C,D; g

B21-TS-3226A.B,C,D; B21-TS-3227A,B,C,D; 821-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) g.

Main Stack Radiation - High (c)

(c) 0 8

~

(BSEP-2-144) e gl TABLE 3.3.2-2 (Continued)

Ey ISOLATION ACEfATION INSTRUMENTATION SETPOINTS E

ALLO' ABLE J

X 8

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE

~

Eq PRIMARY CONTAINMENT ISOLATION (Continued) u 2.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High

-< 11 mr/hr

< 11 mr/hr (D12-R M-N010A, B)

~

b, Drywell Pts.ssure - High

< 2 psig

< 2 psig (C72-PTM-N002A-1,B-1,C-1,D-1) c.

Reactor Vessel Water Level -

Low, Level 2

> + 112 inches (a)

AI y

(B21-LTM-NO24A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1)

!T 9

2

.?

i.

(BSEP-2-144) o TABLE 3.3.2-2 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SEIPOINTS NOTES (a)

Vessel water levels refer to REFERENCE LEVEL ZERO.

(b)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of rated thermal power, the normal full power radiation background level and associated trip setpoints may be changed based on a calutated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and the associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiction levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor power levels below 22% of rated thermal power, whlie these functions are required to be operable.

(c)

Establish alarm / trip setpoints per the methodology contained in the OFFSITE DOSE CALCULATION HANUAL (ODCH).

i i

.i BRUNSWICK - UNIT 2 3/4 3-21a Amendment No.

(BSEP-2-144) o E

TABLE _3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l

TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

PRIMARY CONTAINMENT ISOLATION (Continued) f.

Turbine Building Area Temperature - High NA l

(B21-TS-3225A,B,C,DI B21-TS-3226A,B,C,DI 521-TS-3227A,B,C,D)

B21-TS-3228A,B,C,DI B21-TS-3229A,B,C,DI B21-TS-3230A,B C.DI g

B21-TS-3231A,B,C,DI 3

521-TS-3232A,B,C,D)

Main Stack Radiation - High(b)

< 1.0*

3 2.

SECONDARY CONTAINMENT ISOLATION f

[

Reactor Building Exhaust Radiation - High(b) ig3 a.

]

(D12-RM-N010A,B) b.

Daywell Pressure - High

$13 h

j (C72-PT-N002A,B C,D) 1 (C72-PTM-N002A-1,5-1,C-1,D-1) l c.

Reactor Veasel Water Level - Low, Level 2

<1.0*

l i

(821-LT-N024A-1,5-1 and l

B21-LT-NO25A-1,B-1) l (821-LTM-N024A-1-1,5-1-1 and B21-LTM-N025A-1-1 B-1-1) l 1

3.

REACTOR WATER CLEANUP SYSTEM ISOLATION l

h 1

a.

A Flow - High

<13 l

~

(C31-dFS-N603-1A,18) i b.

Area Temperature - High

<13 l

(C31-TS-N600A,B,C,D E F) l Area Ventilation Temperature & T - High (13 c.

l (C31-TS-W602A,B,C,D,E,F) f

~

j d.

SLCS Initiation NA l

i (C41A-S1) l a

i l

e.

Eeactor Vessel Water Lent a Low, Level 2

<1.0*

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

(

~

1 521-LT-N025A-1,B-1) i (521-LTM-N024A-1-1,B-1-1 and

(

j B21-LTM-N025A-1-1,B-1-1)

I i

i l

1

?

I j

BRUNSWICK - UNIT 2 3/4 3-23 Amendment N.o.

l l

i 4

(BSEP-2-144) g g

4 TABLE 4.3.2-1 (Continued)

E E

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

OPERATICNAL

^

GANNEL GANNEL FUNCTIONAL GANNEL CONDITIONS IN WHIG TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED ll PRIMARY CGNTAINMENT ISOLATION (Continued) w 4.

Flow - High D

M M

2, 3 (B21-PDTS-MOO 6A-2; B21-PDTS-NOO7B-2; B21-PDTS-NOO8C-2; B21-PDTS-NOO9D-2) d.

Main Steam Line Tunnel Temperature - High NA M

R 1, 2, 3 w

3:

(B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; v

d, B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.

Condenser Vacuum - Low (B21-PT-N056A,B,C,D)

NA(a)

NA R(b) 1, 2#

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

D M

M 1, 2#

f.

Turbine Building Area Temp-High NA M

R 1, 2, 3 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D ;

B21-TS-3228A,B,C,D; 3I B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; I

B21-TS-3231 A,B,C,D ;

B21-TS-3232A,B,C,D) x g.

Main Stack Rsdiation - High Na Q

R 1, 2, 3 3

um____.

ML20155B161

Text

SUMMARY

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