ML20081B642

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Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Accident Monitoring Instrumentation Per NUREG-0737 & Generic Ltr 83-36
ML20081B642
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/02/1984
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20081B626 List:
References
RTR-NUREG-0737, RTR-NUREG-737 GL-83-36, NUDOCS 8403090260
Download: ML20081B642 (21)


Text

,

ENCLOSURE 3 TO NLS-84-074 Y

RESPONSE TO GENERIC LETTER NO. 83-36 (NUREG-0737 TECHNICAL SPECIFICATIONS)

BRUNSWICK ST5AM ELECTRIC PLANT, UNIT NOS. 1 AND 2 REFERENCE NO. 84TSB01 l

t i

K O!hh4 PDR

(BSEP-1-13)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION...............

3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..................... 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION............

3/4 3-39 3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumentation......................

3/4 3-44 Ramote Shutdown Monitoring Instrumentation.............. 3/4 3-47 Accident Monitoring Instrumentation.....................

3/4 3-50 Source Range Monitors...................................

3/4 3-53 Chlorine Detection System...............................

3/4 3-54 Chloride Intrusion Monitors............................. 3/4 3-55 Fire Detection Instrumentation..........................

3/4 '4-54 Radioactive Liquid Effluent Monitoring Instrumentation.. 3/4 3-62 Radioactive Geseous Effluent Monitoring Instrumentation.

3/4 3-68 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION..... 3/4 3-78 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.....................................

3/4 4-1 Jet Pumps............................................... 3/4 4-2 Idle Recirculation Loop Startup.........................

3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES....................................

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSIEM LEAKAGE Leakage Detection Systems...............................

3/4 4-5 Operational Leakage.....................................

3/4 4-6

  • BRUNSWICK - UNIT 1 V

Amendment No.

(BSEP-1-13)

INSTRtHENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.5.3 The accident monitoring instrumentation channels shown in Table l

3.3.5.3-1 shall be OPERABLE.

APPLICABILITY: As shown in. Table 3.3.5.3-1.

ACTION:

a.

With one or more accident monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3.5.3-1.

b.

The provisions of Specification 3 0.4 are r h applicable.

SURVEILLANCE REQUIREMENTS 4.3.5.3 Each of the above required accident monitoring instrumentation l

channels shall be demonstrated OPERABLE by performinci 6f'ths CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table l

4.3.5.3-1.

i 4

d-BRUNSWICK - UNIT 1 3/4 3-50 Amendment No.

(BSEF-1-13) w TABLE 3.3.5.3-1 l,

ACCIDENT MIMENTATION m

EI

'R MININUM AFFLICARLE REQUIRED NUMBER CHANNELS OPERATIONAL g

INSTRIMENT AND INSTRIMENT NIMBER OF CHANNELS OPERABLE CONDITIONS ACTION i

s"

1. Reactor Vessel Pressure 2

1 1, 2 82 (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,5) i

2. Reactor Vessel Water Level 2

1 1, 2 82 (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and 821-LTM-NO37-1)

3. Suppression Chamber Water Level 2

1 1, 2 82 w

i is (CAC-LT-2601; CAC-LI-2601-1) y (CAC-LT-2602; CAC-1.R-2602) a Ln l

4. Suppression Chamber Water Temperature 2

1 1, 2 82 (CAC-TR-1258-14, 21; and C91-P602) i

5. Suppression Chamber Atmosphere Temperature 2

1 1, 2 82 1

(CAC-TR-1258-17 thru 20; and C91-P602)

6. Drywell Pressure 2

1 1, 2 82 I

(CAC-PI-4176; CAC-PT-4176; E

CAC-PR-1257-1; and CAC-PT-4175)

EI

7. Drywell Temperature 2

1 1, 2 82

{

(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602)

I t

9

8. Drywell Radiation 2

2 1,2,3 81

['

(CAC-AR-1260; CAC-AQH-1260-1,2,3;

)

,o CAC-AR-1261; CAC-AQH-1261-1,2,3; i

CAC-AR-1262; CAC-AQH-1262-1,2,3) l I

a

(BSEF-1-13)

~

,i TABLE 3.3.5.3-1 (Continued)

ACCIDENT MONITORING INSTRIMENTATION s

R MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIOWAL h

INSTRUMENT AND INSTRUMENT NIMBER OF CHANNELS OPERABLE CONDITIONS ACTION H

2 ")

1(*)

1, 2 82 I

~

9. Drywell Oxygen Concentration (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41)

(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC-X-XY-4363-2; CAC-AR-4410-41)

10. Drywell Hydrogen Concentration Analyzer and Monitor-2(a) g(a) 1, 2 82 i

(CAC-AT-4409-38; CAC-AI-4409-32;

[

CAC-X-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)

N l

(CAC-AT-4410-38; CAC-AI-4410-32; CAC-X-XY-4362-1; CAC-X-XY-4363-1;

}

CAC-AR-4410-42)

11. Drywell Area Fadiation Monitors 2

2 1, 2 81 l

(D22-RM-4195; D22-RI-4195)

(D22-RM-4196; D22-RI-4196)

(D22-RM-4197; D22-RI-4197)

(D22-RM-4198; D22-RI-4198)

N g

12. Safety / Relief Valve Position Indication 2/ valve 1/ valve 1, 2 82 0"y a.

Primary - Sonic (B21-FY-4157 thru 4167) b.

Secondary - Temp. (B21-TR-R614, points 1-11) 1 l

j

(Bsse-t-13)

N E

'TABIA 3.3.5.3-1 (coneinued) np ACCIDENT MONITORING INSTRIBfENTATION E

MINIMIM APPLICABLE E

REQUIRED NUMBER CHANNELS OPERATIONAL s-.

INSTRUMENT AND INSTRUMENT MLBfBER OF CHANNELS OPERABLE CONDITIONS ACTION

13. Turbine Building Ventilation Monitorf 1

1 1,2,3 81 (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)

14. Off-gas Stack Ventilation Manitori 1

1 1,2,3 81 (D12-RE-4573; D12-RE-4574:

D12-RR-4599-2; D12-RR-4599-3) w i

U

'fu D'

l l

  1. High range noble gas monitors f (a) An OPERABLE instrument channel shall consist of the AT instrument and either the AI instrument or the o

XY-XY-AR instruments.

g B,,

t


_____l-3

. _ =

=

(BSEP-1-13)

Table 3.3.5.3-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 81 -

4 With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirerents, initiate the preplanned alternate method of monitoring the apptopriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1) either restore at least the minimum number of operable channel (s) to OPERABLE status within 7 days of the event, or 2) prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

ACTION 82 -

s.

With the number of OPERABLE channels one less than the required number of channels shown in Table 3.3.5.3-1, restore the inoperable channel to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 1_2 hours.

b. -

With the number of OPERABLE channels less than the minimum channels OPERABLE requirements of Table 3.3.5.3-1, restore at least the minimum number of operable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4

  • BRUNSWICK - UNIT 1 3/4 3-52b Amendment No.

(BSEP-1-13)

TABLE 4.3.5.3-1 h

ACCIDENT MONITORING INSTR 19tENTATION SURVEILLANCE REQUIREMENTS

.s Q

CHANNEL CHANhEL INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION h

1. Reactor Vessel Pressure M

R (821-PI-R004A,8; C32-LPR-R608; and C32-PT-NOO5A,B)-

H H

2. Reactor Vessel Water level M

R (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A B; B21-LT-NO37; and B21-LTM-N037-1) i

3. Suppression Chamber Water Level M

R (CAC-LT-2601; CAC-LI-2601-1)

(CAC-LT-2602; CAC-LR-2602) i u

Y

4. Suppression Chamber Water Temperature M

R y

(CAC-TR-1258-14, 21; and C91-P602) y

5. Suppression Chamber Atmosphere Temperature o

4 M

R (CAC-TR-1258-17 thru 20; and C91-P602)

6. Drywell Pressure M

R j

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)

7. Drywell Temperature M

R

)

(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) i I

1

8. Drywell Radiation M

R (CAC-AR-1260; CAC-AQil-1260-1,2,3; CAC-AR-1261; CAC-AQll-1261-1,2,3; k

CAC-AR-1262; CAC-AQil-1262-1,2,3) i E.

9. Drywell Oxygen Concentration H

R f,

(CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; 2

CAC-X-XY-4349-2; CAC-AR-4409-41)

(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC-X-XY-4363-2; CAC-AR-4410-41) i

(BSEP-1-13) to TABLE 4.3.5.3-1 (Continued) ag ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

8 CHANNEL CHANNEL f

INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION s

10. Drywell Hydrogen Concentration Analyzer and Monitor M

R (CAC-AT-4409-38; CAC-AI-4409-32; CAC-X-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)

(CAC-AT-4410-38; CAC-AI-4410-32; CAC-I-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-4?)

11. Drywell Area Radiation Monitor M

R*

(D22-RM-4195; D22-RI-4195)

(D22-RM-4196; D22-RI-4196)

(D22-RM-4197; D22-RI-4197)

(D22-RM-4198; D22-RI-4198) i

12. Safety Relief Valve Position Indication u

a.

Primary - Sonic (B21-FY-4157 thru 4167)

M R

h b.

Secondary - Temp. (B21-TR-R614, points 1-11)

M R

o.

13. Turbine Building Ventilation Monitorf M

R (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)

14. Off-gas Stack Ventilation Monitorf M

R (D12-RE-4573; D12-RE-4574; D12-RR-4599-2; D12-RR-4599-3)

EI E

  • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the k

detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr g

with an installed or portable gamma source.

  1. High range noble gas monitors.

e.

INSTRLMENTATION CRLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.5.5 A chlorina detection system shall be OPERABLE with the alarm setpoint adjusted to actuate at a chlorine concentration of less than or equal to 5 ppe.

APPLICABILITY:

OPERATIONAL CONDITIONS 1*, 2*, and 3*.

ACTION:

a. With the chlorine detection system inoperable, restore the inoperable detection system to OPERABLE status within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or be in at least BOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUIDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. The provisions of Specification 3.0.4 are not applicable.

SIRVEILLANCE REQUIREMENTS 4.3.5.5 The chlorine detection system (K-AT-2977) shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 acnths.

  • With chlorine within the Exclusion Area.

BRUNSWICK - INIT 1 3/4 3-54 Amendment No.

(BSEP-1-13)

INSTRIMENTATION BASES-MONITORING INSTRtMENTATION (Continued)

J/4.3.5.2 REMOTE SHUTDOWN MONITORING INSTRIMENTATION The OPERABILITY of the remote shutdown conitoring instrumentation ensures that sufficient capability is available to permit shotdown and maintenance of BOT SHUTDOWN of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of CFR 50.

J 3/4.3.5.3 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that l

sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recomm6ndations of Regulatory Guide 1.97, " Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Tern Recommendations."

3/4.3.5.4 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status'of the neutron level in the core at very low power levels during start-up. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale edequate information is available without the SRMs and they can be retracted.

3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for ccatrol room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically isolate the control room and initiate operation in the recirculation mode to provide the required protection. The detection systems required by this specification are consistent with the recomeendations of Regulatory Guide 1.95 " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."

s BRUNSWICK - UNIT 1 5 3/4 3-3 Amendment No.

(BSEP-2-12)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTLUMENTATION 3/4.3.I REACTOR PROTECTION SYSTEN INSTRUMENTATION................... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................... 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION......

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION................ 3/4 3-39 3/4.3.5 MONITORING INSTRIMENTATION f

Seismic Monitoring Ins trumentation.......................

3/4 3-44 Remote Shutdown Monitoring Instrumentation............... 3/4 3-47 Accident Monitoring Instrumentation......................

3/4 3-50 Source Range Monitors.................................... 3/4 3-53 Chlorine De tec tion Sys tem................................

3 /4 3-54 Chloride Intrusion Monitors.............................. 3/4 3-55 Fire Detection Instrumentation...........................

3/4 3-59

~

Radioactive Liquid Effluent Monitoring Instrumentation.... 3/4 3-62 Radioactive Gaseous Effluent Monitoring Instrumentation...

3/4 3-68 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation...... 3/4 3-78 End-of-Cycle Recirculation Pump Trip System Instrumentation........................................ 3/4 3-82 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops......................................

3/4 4-1 Jet Pumps................................................ 3/4 4-2 Idle Recirculation Loop Startup..........................

3/4 4-3 3.4.4.2 SAFETY / RELIEF VALVES........................................

3/4 4-4

  • BRUNSWICK - UNIT 2 V

Amendment No.

+

(BSEP-2-12)

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION

' LIMITING 'ONDITION FOR OPERATION 3.3.5.3 The accident monitoring instrumentation channels shown in Table

{

3.3.5.3-1 shall be OPERABLE.

APPLICABILITY: As shown iE Table 3.3.5.3-1.

ACTION:

WitM one or more accident monitoring instrumentation channels a.

inoperable, take the ACTION required by Table 3.3.5.3-1.

u~

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS.-

4.3.5.3 Each of the above required accident monitoring instrumentation

(

channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operation's at the frequencies shown in Table 4.3.5.3-1.

  • BRUNSWICK - UNIT 2 3/4 3-50 Amendment No.

(BSEP-2-12)

TABLE 3.3.5.3-1 E

ACCIDENT MONITORING INSTRIMENTATION B

O NININUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL E

INSTRUMENT AND INSTRUMENT NLMBER OF CHANNELS OPERABLE CONDITIONS ACTION i

1 u
1. Reactor Vessel Pressare 2

1 1, 2 82 (B21-PI-R004A,B; C32-Ll'F,-R608; and C32-PT-N005A,5)

2. Reactor Vessel Water Level 2

1 1, 2 82 (B21-LITS-N026A,8; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) g

3. Suppression Chamber Water Level 2

1 1, 2 82 (CAC-LT-2601; CAC-LI-2601-1)

(CAC-LT-2602; CAC-LR-2602)

]

4. Suppression Chamber Water Temperature 2

1, 1, 2 82

~

]

(CAC-TR-1258-14, 21; and C91-P602)

I

5. Suppression Chamber Atmosphere Temperature 2

1 1, 2 82 (CAC-TR-1258-17 thru 20; and C91-P602) q

6. Drywell Pressure 2

1 1, 2 82 i

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) i

7. Drywell Temperature 2

I 1, 2 82 f

(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602) 4 m

[

8. Drywell Radiation 2

2 1, 2, 3 81 m

(CAC-AR-1260; CAC-AQH-1260-1,2,3;

[

CAC-AR-1261; CAC-AQH-1261-1,2,3; j

,o CAC-AR-1262; CAC-AQH-1262-1,2,3) i e

e S

(BSEP-2-12)

TABLE 3.3.5.3-1 (Continued) we h

ACCIDENT MONITORING INSTRUMENTATION

?!

M M

MINIMUN APPLICABLE 8

REQUIRED NUMBER CHANNELS OPERATIONAL Ei INSTRUMENT AND INSTRUMENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION u

9. Drywell Oxygen Concentration 2(*)

1(*)

1, 2 82 (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-Ad-4409-41)

(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC*X-XY-4363-2; CAC-AR-4410-41)

I

10. Drywell Hydrogen Concentration Analyzer and Monitor,

2(a) g(a) 1, 2 82 u,

30 (CAC-AT-4409-38; CAC-AI-4409-32; CAC-X-XY-4348-1; CAC-X-XY-4349-1; u,

b CAC-AR-4409-42) w (CAC-AT-4410-38; CAC-AI-4410-32; CAC-X-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-42)

11. Drywell Area Radiation Monitors 2

2 1, 2 81 (D22-RM-4195; D22-RI-4195) i l

(D22-RM-4196; D22-RI-4196)

(D22-RM-4197; D22-RI-4197) i (D22-RM-4198; D22-RI-4198)

12. Safety / Relief Valve Position Indication

~

2/ valve 1/ valve 1, 2 82 E

Primary - Sonic (B21-FY-4157 thru 4167) a.

]

,Ef b.

Secondary - Temp. (B21-TR-R614,, points 1-11)

?

6

(&3EP-2-12)

~

E TABLE 3.3.5.3-1 (Continued) e f

ACCIDENT MONITORING INSTR'.NENTATION i

E

.MINIMUN APPLICABLE N

REQUIRED NUMBER CHANNELS OPERATIONAL N

INSTRUMENT AND INSTRUMENT NUMBER OF CHANNELS OPERABL.E CONDITIONS ACTION

13. Turbine Building Ver.tilation Monitori 1

1 1,2,3 81 (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)

I I

14. Off-gas Stack Ventilation Monitori 1

1 1,2,3 81 (D12-RE-4573; D12-RE-4574; s

D12-RR-4599-2; D12-RR-4599-3)

(

M.

s Y

I M

m

  1. High range noble gas monitors.

k (a) An OPERABLE instrument channel shall consist of the AT instrument and either the AI instrument or' the

[

XY-XY-AR instruments.

E

.F

+

o.

I

l (BSEP-2-12)

Table 3.3.5.3-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 81 -

With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1) either restore at least the minimum number of operable channel (s) to OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

ACTION 82 -

s.

With the number of OPERABLE channsis one less than the required number of channels shown in Table 3.3.5.3-1, restore the inoperable channel to OPERABLR status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With the number of OPERABLE channels less than the minimum channels OPERABLE requirements of Table 3.3.5.3-1, restore at least the minimum number of operable channel (s) to OPERABLE status within 7 days or be in at least HOT. SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i l

i l

i i

l l

l

  • BRUNSWICK - UNIT 2 3/4 3-52b Amendment No.

4

,--,-*w--,*re, w

m-e,-n 1

--w-,-

w 1

'-~'-* *

~w

~ '

v' w

v

-~~ *~-

(BSEP-2-12) g TABLE 4.3.5.3-1 ACCIDENT MONITORING INSTRIMENTATION SURVEILLANCE REQUIREMENTS l

0 CHANNEL CHANNEL l'

INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION Ey

1. Reactor Vessel Pressure M

R (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) y

2. Reactor Vessel Water Level M

R (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-N037; and B21-LTM-NO37-1)

3. Suppression Chamber Water Level M

R (CAC-LT-2601; CAC-LI-2601-1)

(CAC-LT-2602; CAC-LR-2602) h*

4. Suppression Chamber Water Temperature M

R (CAC-TR-1258-14, 21; and C91-P602) l j'

M

5. Suppression Chamber Atmosphere Temperature M

R o

(CAC-TR-1258-17 thru 20; and C91-P602)

6. Drywell Pressure M

R (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)

7. Drywell Temperature M

R (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602)

8. Drywell Radiation M

R (CAC-AR-1260; CAC-AQil-1260-1,2,3; y

CAC-AR-1261; CAC-AQll-1261-1,2,3;

{

CAC-AR-1262; CAC AQil-1262-1,2,3)

9. Drywell Oxygen Concentration M

R (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41)

(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC-X-XY-4363-2; CAC-AR-4410-41)

~

(BSEP-2--12) es

'g g

TABLE 4.3.5.3-1 (Continued)

N Q

ACCIDENT MONITORING INSTRIBfENTATION SURVEILLANCE n_gnnIRgMENTS

.'h t

CHANNEL CHANNEL INSTRIDfElff AND INSTRLBfENT NIDfBER CHECK CALIBRATION t

a

10. Drywell Hydrogen Concentration Analyzer and Monitor M

R N

i (CAC-AT-4409-38; CAC-AI-4409-32; CAC-I-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)

(CAC-AT-4410-38; CAC-AI-4410-32;,CAC-X-XY-4362-1; j

CAC-X-XY-4363-1; CAC-AR-4410-42) i I1. Drywell Area Radiation Monitor M

R*

1 (D22-RM-4195; D22-RI-4195)

(D22-RM-41%; D22-RI-4196) j (D22-RM-4197; D22-RI-4197)

(D22-RM-4198; D22-RI-4198) w)

j

12. Safety Relief Valve Position Indication g

j a.

Primary - Sonic (B21-FY-4157 thru 4167)

M R

j g

b.

Secondary - Temp. (B21-TR-R614, points 1-11)

M t

R

\\

13. Turbine Building Ventilation Monitor #

M R

l (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)

)

14. Off-gas Stack Ventilation Monitorf M

R j

(D12-RE-4573; D12-RE-4574; j

D12-RR-4599-2; D12-RR-4599-3) i i

l lii 4

m D

  • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the k,

detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr 7

with an installed or portable gamma source.

  1. Eigh range noble gas monitors.

4 1

9 3-c

1,.

INSTRIBEENTATION CHIARINE IETECTION SYSTEM LIMITING CONDITION POR OPERATION 3.3.5.5 A chlorine detection system shall be OPERABLE with the alarm setpoint adjusted to actuate at a chlorine concentration of less than or eqtal to 5 ppa.

APPLICABILITY:

OPERATIONAL CONDITIONS 1*, 2*, and 3*.

I 1

ACTION:

a. With the chlorine detection system inoperable, restore the inoperable detection system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least BOT SHITfDOWN within 12 hcurs and in COLD SHITfDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l l

b. The provisions of Specification 3.0.4 are not applicable.

SIEtVEILLANCE REQUIREMENTS 4.3.5.5 The chlorine detection system (X-AT-2977) shall be demonstrated OPERABIZ by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least occe per 18 months.

  • With chlorine within the Exclusion Area.

I BRIMSWICK - IBIIT 2 3/4 3-54 Amendment No.

\\

(BSEP-2-12)

IM5TRIMENTATION RASES

  • O MONITORING INSTRIMENTATION (Continued) 3/4.3.5.2 REMOTE SHUTDOWN MONITORING INSTRIMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficiert capability in available to permit shutdown and maintenance of 50T SHUTDOWN of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost, and is, l

consistent with General Design Criterion 19 of CFR 50.

3/4.3.5.3 -ACCIDENT MONITOP.ING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that l

l sufficient information is available on selected plant parameters to monitor i

and assere important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tern Recommendations."

3/4.3.5.4 SOURCE RANGE MONITORS l

The source range monitors provide the operator with information on the status-of the neutron level in the. core at very low power levels during start-i up. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SENs and they can be retracted.

3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the necessary

-i protective actions will be automatically initiated to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically isolate the i

control room and initiate operation in the recirculation mode to provide the required protection. The detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."

'nkUNSWICK - UNIT 2 8 3/4 3-3 Amendment No.

L

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