ML20054G406

Proposed Revisions to Tech Specs Reflecting Projected Completion of Plant Mods as Required by NUREG-0737

ML20054G406
Person / Time
Site:	Brunswick
Issue date:	06/16/1982
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20054G396	List: ML20054G395 ML20054G406
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8206210526
Download: ML20054G406 (30)

Text

CONTAINMENT SYSTEMS CAS ANALYZER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.4 Two independent gas analyzer systems for the drywell and suppression chamber shall be OPERABLE with each system consisting of an oxygen analyzer and a hydrogen analyzer.

APPLICABILITY: CONDITION 1.

ACTION:

, a. With one oxygen and/or one hydrogen analyzer inoperable, restore at I least two oxygen and two hydrogen analyzers to OPERABLE status within 31 days or be in at least START-UP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.

b. With no gas analyzer OPERABLE for oxygen and/or hydrogen, be in at least START-UP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.6.4 Eachgasanalyzershstem(CAC-AT-4409,DivisionIandCAC-AT-4410, Div1.sion II) shall be demonstrated OPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using standard gas samples containing a nominal:

a. Zero volume percent hydrogen, balance nitrogen, and

b. Seven to ten volume percent hydrogen, balance nitrogen.

c. Twenty-five to thirty volume percent hydrogen, balance nitrogen.

d. Zero volume percent oxygen, balance nitrogen.

e. Seven to ten volume percent oxygen, balance nitrogen.

f. Twenty to twenty-five volume percent oxygen, balance nitrogen.

BRUNSWICK - UNIT 1 3/4 6-30 Amendment No.

8206210526 820616 PDR ADOCK 05000324 PDR p

CONTAINMENT SYSTEMS CAS ANALYZER SYSTEMS LIMITING CONDITIONS FOR OPERATION 3.6.6.4 Two independent gas analyzer systems for the dryws11 and suppression chamber shall be OPERABLE with each system consisting of an oxygen analyzer and a hydrogen analyzer.

APPLICABILITY: CONDITION 1.

l ACTION:

a. With one oxygen and/or one hy~drogen analyzer inoperable, restore at least two oxygen and two hydrogen analyzers to OPERABLE status within 31 days or be in at least START-UP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.

b. With no gas analyzer OPERABLE for oxygen and/or hydrogen, be in at least START-UP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.6.4 Each gas analyzer system (CAC-AT-4409, Division I and CAC-AT-4410, Division II) shall be demonstrated OPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using standard gas samples containing a nominal:

a. Zero volume percent hydrogen, balance nitrogen, and

b. Seven to ten volume percent hydrogen, balance nitrogen.

c. Twenty-five to thirty volume percent hydrogen, balance nitrogen.

d. Zero volume percent oxygen, balance nitrogen.

e. Seven to ten volume percent oxygen, balance nitrogen.

f. Twenty to twenty-five volume percent oxygen, balance nitrogen.

BRUNSWICK - UNIT 2 3/4 6-30 Amendment No.

ATTACHMENT 2

SUBJECT:

Safety-related Hydraulic Snubbers on Control Rod Drive (CRD)

Return Line REASON FOR TECHNICAL SPECIFICATION (TS) CHANGE: Snubbers to be deleted from TS as the CRD return line is being removed (refer to CP&L letter dated October 7, 1981).

JUSTIFICATION FOR CHANGE: Snubbers are only required on operable safety-related lines.

l

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E G TABLE 3.7.5-1 (Continued) g SAFETY RELATED HYDRAULIC SNUBBERS

• s

' SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HICH RADIATION ESPECIALLY DIFFICULT NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE g (A or I) (Yes or No) (Yes or No) y Condensate Drain System IB21-51SS103 Drywel l 29' I No No SISS105 29' I No No SISS106 26' I No No 50SS109 18' I No No 50SSI11 31' sI No No 51SS113 28' 'I No No SISSI15 23' I No No

. 51SSil8 24' I No No 1

liigh Pressure Coolant Injection System ,

u '

' IE41-4SS44 Drywell 40' I No No N 4SS45 35' I No No 4SS47 40' I No No 4SS49 37' I No No 4SS50 50' I No No 4SS51 30' I No No 60SS9 Reactor Building 4' A No No 6SS27 -5' A No No 6SS28 l' A No No 6SS30 -l' A No No 6SS32 -5' A No No g 6SS33 l' A No No g 6SS35 -l' A No No g 6SS36 -5' A No No .

E n

e

TABLE 3.7.5-1 (Continu:d) (

, SAFETY-RELATED HYDRAULIC SNUBBERSA ,

E M SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

$ NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE Q v

, Reactor Water Cleanup System 2G31-ISS3 Drywell 54' A No No 5 Condensate Drains System

" 2821-51SS103

, Drywell 29' I No No 51SS105 26' I No No 51SS106 18' I No No i

SISS109 31' I No No 51SSill 28' I No No 51SSil3 23' I No No l SISSil5 24' \ I No No l

SISSil8 24' I No No liigh Pressure Coolant Injection System R 2E41-4SS44 Drywell 40' I No No e 4SS45 35' I No ( No y 4SS47 40' I No No g 4SS49 37' I No No 4SS50 40' I No No 4SS51 30' I No No

< a n

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ATTACHMENT 3

SUBJECT:

Turbine Building Ventilation Radiation Monitoring System REASON FOR TECHNICAL SPECIFICATION (TS) CHANGE: NUREG-0737, Item II.F.1.1 and II.F.1.2.

JUSTIFICATION FOR CHANCE: The equipment being installed is more reliable and can monitor a wider range of radioactive gas concentrations than the previously installed equipment. The margin of safety is not reduced, and more reliable information will be available during adverse conditions.

SUBJECT:

Post-Accident Monitoring Instrumentation REASON FOR TECHNICAL SPECIFICATION (TS) CHANGE: NUREG-0737, Item II.F.1.5.

TS changes also reflect instrument tag number changes.

JUSTIFICATION FOR CHANGE: The increased measurement range and more reliable instrumentation ensure a safer and more accurate overall measurement monitoring system. Additionally, added instrumentation increases margin of safety.

SUBJECT:

Post-Accident Sampling System REASONFORTECHNICALSPECIFIdATION(TS) CHANGE: NUREG-0737, Item II.B.3 JUSTIFICATION FOR CHANGE: This change reflects:

1. A more reliable design for obtaining liquid and gaseous samples from primary containment in the event of a LOCA.

2. An increase in the margin of safety by making available critical analytical data necessary for core and containment condition evaluation.

3 Increased sampling capabilities.

, INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1.3.5.3 The post-accident monitoring instrumentation channels shown in Table 3.3.5.3-1 shall be OPERABLE.

APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

~

With the number of OPERABLE posc-accident monitoring channels less than required by Table 3.3.5.3-1, take the ACTION required by Table i 3.3.5.3-1.

SURVEILLANCE REQUIREMENTS i

4.3.5.3 Each of the above required post-accident monitoring instrumentation channels shall be demonstrated operable by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.3-1.

< o' BRUNSWICK - UNIT 1 '/4 3-50 Amendment No.

TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION ,

MINIMUM NO.

OF OPERABLE INSTRUMENT

, INSTRUMENT AND INSTRUMENT NUMBER CHANNELS ACTION

1. Reactor Vessel Water Level 2 1 (B21-LITS-N026A,B; B21-LR-615; B21-LI-R604A,B; B21-LT-N037 and B21-LTM-NO37-1)'

2. Reactor Vessel Pressure 2 1 (B21-PI-R004A,B; C32-LPR-R608 and C32-PT-N005A,B)

3. Containment Pressure 2 1 (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1 and i

CAC-PT-4175)

4. Containment Temperature 2 1 (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)

5. Suppression Chamber Atmosphere Temperature 2 1 (CAC-TR-1258-17 thru 20 and C91-P602) 1 6. Suppression Chamber Water Level 2 1 (CAC-LI-2601-1, CAC-LR-2602, CAC-LT-2601, CAC-LT-2602) ,

,/

7. Suppression Chamber Water Temperature 2 1 l (CAC-TR-1258-14, 21 and C91-P602) i 8. Containment Radiation 2 1

! (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; l CAC-A0H-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3)

9. Containment Oxygen 2 1 (CAC-AT-4409-37, CAC-X-XY-4348-2, a CAC-X-XY-4349-2, CAC-AR-4409-1, CAC-AT-4410-37, CAC-X-XY-4362-2, CAC-X-XY-4363-2, CAC-AR-4410-1)

10. Containment Hydrogen 2 1 (CAC-AT-4409-38, CAC-X-XY-4348-1.

CAC-X-XY-4349-1, CAC-AR-4409-2, 3

CAC-AT-4410-38, CAC-X-XY-4362-1, CAC-X-KY-4363-1, CAC-AR-4410-2)

I

11. Safety relief valve position indication: 1/ valve 1 Primary - Sonic (B21-FY-4157 through 4167) 2 Secondary - Temp. (B21-TR-R614 points 1-11) 1 BRUNSWICK - UNIT 1 3/4 3-51 Amendment No.

TABLE 3.3.5.3-1 (continued)

POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS ACTION

12. Post-accident sampling a) Gaseous ,,

1 2 b) Liquid 1 2

13. Drywell Area Radiation Monitors 2 1 (D22-RM-4195, D22-RM-4196, D22-RM-4197, D22-RM-4198, D22-RI-4195, D22 'tI-4196, D22-RI-4197, D22-RI-4198)

14. Turbine Building Ventilation Radiation Monitor 1 1 (D12-RE-4561, D12-RE-4562, D12-RE-4563 and D12-RR-4548)

,a' i

i BRUNSWICK - UNIT 1 3/4 3-51a Amendment No.

l l

l TABLE 3.3.5.3-1 (Continued)

POST-ACCIDENT MONITORING INSTRUMENTATION ACTION ACTION 1 - With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3.5.3-1, either restore the inoperable channels to OPERABLE 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 />.

The provisions of Specification 3.0.4 are not applicable.

ACTION 2 - When the ability to provide a liquid and/or gaseous sample to the post-accident sample station has been lost, Restore the capability 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 />.

When the ability to sample and Analyze a liquid and/or gaseous sample has been lost, Reconfirm within 7 days that alternate arrangements for sampling and analysis of the required samples can be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event that such an analysis is needed 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 />, then Restore the complete sampling and analysis capability within 90 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 />.

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BRUNSWICK - UNIT 1 3/4 3-51b Amendme nt No .

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m CHANNEL CHANNEL E INSTRUMEKr AND INSTRUMENT NUMBER CHECK CALIBRATION U! 1. Reactor Vessel Water Level M R 5 (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; 9 B21-LT-NO37 and B21-LTM-NO37-1) a c: 2. Reactor Vessel Pressure M R d

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

3. Containment Pressure M R (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1 and CAC-PT-4175)

4. Containment Temperature M R (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)

N'

5. Suppression Chamber Atmosphere Temperature M R (CAC-TR-1258-17 thru 20 and C91-P602)

6. Suppression Chamber Water Level M R ki (CAC-LI-2601-1, CAC-LR-2602, CAC-LT-2601, CAC-LT-2602) I s~

Y l

7. Suppression Chamber Water Temperature M R

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

8. Containment Radiation M R (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3)

9. Containment Oxygen Concentration M R (CAC-AT-4409-37, CAC-X-XY-4348-2, CAC-X-XY-4349-2, CAC-AR-4409-1, CAC-AT-4410-37, CAC-X-XY-4362-2, CAC-X-XY-4363-2, CAC-AR-4410-1) g 10. Containment Hydrogen Concentration M R m (CAC-AT-4409-38, CAC-X-XY-4348-1, CAC-X-XY-4349-1, CAC-AR-4409-2, S. CAC-AT-4410-38, CAC-X-XY-4362-1, CAC-X-XY-4363-1, CAC-AR-4410-2)

E 11. Safety relief valve position indication (Primary-Sonic) M R z (B21-FY-4157 thru 4167)

12. Safety relief valve position indication (Secondary-Temperature) M R (B21-TR-R614 points 1 thru 11)

m TABLE 4.3.5.3-1 (Continued) jgb POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' i$

lQ CHANNEL CHANNEL

, INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION IhH

13. Post-Accident Sampling a) Gaseous N/A R H

b) Liquid N/A R

14. Drywell Area Radiation Monitors M R (D22-RM-4195, D22-RM-4196, D22-RM-4197, D22-RM-4198, s D22-RI-4195, D22-RI-4196, D22-RI-4197, D22-RI-4198)

w 15. Turbine Building Ventilation Radiation Monitor M R

!) (D12-RE-4561, D12-RE-4562, ,

y D12-RE-4563 and D12-RR-4548) '

a

~a

,8n

. .O

i INSTRUMENTATION POST-ACCIDENT MONITrAING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.5.3 The post-accident monitoring instrumentation channels shown in Table 3.3.5.3-1 shall be OPERABLE.

APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3.5.3-1, take the ACTION required by Table 3.3.5.3-1.

SURVEILLANCh REQUIREMENTS 4.3.5.3 Each of the above required post-accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.3-1.

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

l TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS ACTION

1. Reactor Vessel Water Level 2 1 (B21-LITS-N026A,B; B21-LR-615; B21-LI-R604A,B; and B21-LITS-NO37)

2. Reactor Vessel Pressure 2 1 (B21-PI-R004A,B; C32-LPR-R608;,and C32-PT-N005A,B)

3. Containment Pressure 2 1 (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)

4. Containment Temperature 2 1 (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602)

5. Suppression Chamber Atmosphere Temperature 2 1 (CAC-TR-1258-17 thru 20, and C91-P602)

6. Suppression Chamber Water Level 2 1 (CAC-LI-2601-1; CAC-LT-2601; CAC-LR-2602; and CAC-LT-2602)

7. Suppression Chamber Water Temperature 2 1 (CAC-TR-1258-14, 21;,and C91-P602)

/

8. Containment Radiation 2 1 (CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3)

9. Containment Oxygen 2 1 (CAC-AT-4409-37; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-1; CAC-AT-4410-37; CAC-X-XY-4362-2; CAC-X-XY-4363-2; CAC-AR-4410-1)

10. Containment Hydrogen 2 1 (CAC-AT-4409-38; CAC-X-XY-4348-1, CAC-X-XY-4349-1; CAC-AR-4409-2; CAC-AT-4410-38; CAC-X-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-2)

11. Safety relief valve position indication: 1/ valve 1 Primary - Sonic (B21-FY-4157 thru 4167)

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

BRUNSWICK - UNIT 2 3/4 3-51 Amendment No.

i TABLE 3.3.5.3-1 (Continued)

POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS ACTION

12. Post-accident sampling a) Gaseous 1 2 b) Liquid 1 2

13. Drywell Area Radiation Monitors. 2 1 (D22-RM-4195, D22-RM-4196, D22-RM-4197, D22-RM-4198, D22-RI-4195, D22-RI-4196, D22-RI-4197, D22-RI-4198)

14. Turbine Building Ventilation Radiation Monitor 1 1 (D12-RE-4561, D12-RE-4562, D12-RE-4563 and D12-RR-4548)

/

1

}

BRUNSWICK - UNIT 2 3/4 3-51a Amendment No.

TABLE 3.3.5.3-1 (Continu:d)

POST-ACCIDENT MONITORING INSTRUMENTATION ACTION ACTION 1 - With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3.5.3-1, either restore the inoperable channels to OPERABLE 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 />.

The provisions of Specification 3.0.4 are not applicable.

ACTION 2 - When the ability to provide a liquid and/or gaseous sample to the post-accident sample station has been lost, Restore the capability 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 />.

When the ability to sample and Analyze a liquid and/or gaseous sample has been lost, Reconfirm within 7 days that alternate arrangements for sampling and analysis of the required samples can be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event that such an analysis is needed 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 />, then Restore the complete sampling and analysis capability within 90 days or be in at least EOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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l BRUNSWICK - UNIT 2 3/4 3-51b Amendment No.

i

TABLE 4.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

z CHANNEL CHANNEL h INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION o 1. Reactor vessel water level M R (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; and B21-LITS-NO37)

E 2. Reactor vessel pressure M R U (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-NOOSA,B) w

3. Containment pressure M R (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)

4. Containment temperature M R (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602)

N.

5. Suppression chamber atmosphere temperature M R (CAC-TR-1258-17 thru 20, and C91-P602) t; 6. Suppression chamber water level M R ,

d (CAC-LI-2601-1; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602) i l w

h 7. Suppression chamber water temperature M R (CAC-TR-1258-14, 21; and C91-P602)

8. Containment radiation M R (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262; and CAC-AQH-1262-1,2,3)

9. Containment oxygen concentration M R (CAC-AT-4409-37, CAC-X-XY-4348-2, CAC-X-XY-4349-2, CAC-AR-4409-1, CAC-AT-4410-37, CAC-X-XY-4362-2, CAC-X-XY-4363-2, CAC-AR-4410-1) k 10. Containment hydrogen concentration M R g, (CAC-AT-4409-38, CAC-X-XY-4348-1, CAC-X-XY-4349-1, CAC-AR-4409-2, g CAC-AT-4410-38, CAC-X-XY-4362-1, CAC-X-XY-4363-1, CAC-AR-4410-2) o

[ 11. Safety relief valve position indication (Primary-Sonic) M R f (B21-FY-4157 thru 4167)

12. Safety relief valve position indication (Secondary-Temperature) M R (B21-TR-R614 points 1 thru 11)

g TABLE 4.3.5.3-1 (Continued)

E v>

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS N

O CHANNEL CHANNEL i INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION E

s 13. Post-Accident Sampling

" a) Gaseous N/A R b) Liquid N/A R

14. Drywell Area Radiation Monitors M R (D22-RM-4195, D22-RM-4196, D22-RM-4197, D22-RM-4198, s, D22-RI-4195, D22-RI-4196, D22-RI-4197, D22-RI-4198)

15. Turbine Building Ventilation Radiation Monitor M R ti (D12-RE-4561, D12-RE-4562, D12-RE-4563 and D12-RR-4548) i.

Y PJ u

'6 8

8 n

9 ATTACHMENT 4

SUBJECT:

Scram Discharge Volume I REASON FOR TECHNICAL SPECIFICATION (TS) CHANGE: Addition of diverse equipment to the existing scram discharge instrument volumes (refer to CP&L letter dated January 13, 1981).

JUSTIFICATION FOR CHANGE: This modification adds to an existing system without changing the designed intent. The new devices to be installed are IEEE, seismically and environmentally qualified. Since the new devices are of fail safe design, no new type of accident is created.

/

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w TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION -

s Q APPLICABLE MINIMUM NUMBER

, OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)(b) ACTION N 6. Main Steam Line Radiation - liigh H

(D12-RM-K603A,B,C,D) 1, 2(d) 2 7

7. Drywell Pressure - High (C71-PS-N002A,B,C,D) 1, 2(*) 2 6

8. Scram Discharge Volume Water Level -

Iligh (Cl l-LSil-N013A, B ,C,D) 1, 2, 5(f) 2 5 (Cll-LSil-4516A,B,C,D) N. l t' 9. Turbine Stop Valve - Closure 1(8) 4 8

• (EllC-SVOS-IX,2X,3X,4X)

Y

" 10. Turbine Control Valve Fast Closure, i Control Oil Pressure - 14w I I8) 2 8 (EllC-PSL-1756,1757,1758,1759)

11. Reactor Mode Switch in Shutdown Position (C71A-51) 1,2,3,4,5 1 9

12. Manual Scram (C71A-S3A,B) 1,2,3,4,5 1 10 a

8 n

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TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES m

W

@ FUNCTIONAL UNIT AND INSTRUMENT NUMBER RESPONSE TIME (Seconds) k 7:

1. Intermediate Range Monitors (C51-IRM-K601A,B,C,D,E,F,G,H):

' a. Neutron flux - liigh* NA

@ b. Inoperative NA U

g 2. Average Power Range Monitor * (CSI-APRM-Cll.A,B,C,D,E,F):

a. Neutron Flux - High, 15% < 0.09

b. Flow Biased Neutron Flux - High IEL

c. Neutron Flux - High, 120% < 0.09

d. Inoperative \ -

ILL

e. Downscale NA

f. LPRM NA u, 3. Reactor Vessel Steam Dome Pressure - High

]; (B21-PT-N023A,B,C,D) i < 0.55 u, (B21-PTM-N023A-1,B-1,C-1,D-1) _

S

4. Reactor Vessel Water Level - Level #1

( B 21-LT-N017A-1, B-1,C-1, D-1 ) < 1.05 (H21-LTM-N017A-1,B-1 C-1,D-1) ~

5. Main Steam Line Isolation Valve-Closure (B21-F022A,B,C,D and B21-F028A,B,C,D) j( 0.06

6. Main Steam Line Radiation - liigh (D12-RM-K603A,B,C,D) NA p 7. Drywell Pressure - liigh g (C71-PS-N002 A,B,C,D) NA n

a. <

@ 8. Scram Discharge Volume Water Level - liigh

$ (C i l-LS11-N013A , B ,C , D)

(Cll-LSil-4516A, B ,C, D)

, z NA l

9. Turbine Stop Valve - Closure (EllC-SVOS-lX,2X,3X,4X)  ;<_ 0.06

TABLE 3.3.1-1 (Continu:d) to

@ REACTOR PROTECTION SYSTEM INSTP.UMENTATION 5

$ APPLICABLE MINIMUM NUMBER Q OPERATIONAL OPERABLE CHANNELS

, FUNCTIONAL UNIT AND INSTRUMEhr fiUMBER CONDITIONS PER TRIP SYSTEM (a)(b) ACTION h 7. Drywell Pressure - High 1, 2 I* ) 2 6 H (C72-PS-N002 A,B,C,D) w

8. Scram Discharge Volume Water Level -

High (C12-LSH-N013 A,B,C,D) 1, 2, 5(f) 2 5 (Cl2-LSH-4516A,B,C,D) l

9. Turbine Stop Valve - Closure ' 1(g) 4 8 (EHC-SVOS-IX,2X,3X,4X)

10. Turbine Control Valve Fast Closure, i t', Control Oil Pressure - Low 1(8) 2 8

• (EHC-PSL-1756,1757,1758,1759) '

i

11. Reactor Mode Switch in Shutdown Position (C72A-SI) 1, 2,:3, 4, 5 1 9

12. Manual Scram (C72A-S3A,B) 1,'2, 3, 4, 5 1 10 ,

4 N

it a <.

n

,i -

i a x

i 4,

k g

m TABLE 3.3.1-2

o R

h REACTOR PROTCCTION RESPONSE TIMES -

y j FUNCTIONAL UNIT AND INSTRUMENT NUMBER RESPONSE TIME

, (Seconds)

1. Intermediate Range Monitors (C51-IRM-K601 A,B,C,D,E,F,G,H):

h H

a. Neutron Flux - liigh* NA

b. Inoperative NA w

2. Average Power Range Monitor * (CSI-APRM-Cll. A,B,C,D,E,F):

a. Neutron Flux - High, 15% < 0.09

b. Flow-Biased Neutron Flux - High -NA

c. Neutron Flux - liigh, 120%

~< 0.09

d. Inoperative NA

e. Downscale NA

f. LPRM NA N

3. Reactor Vessel Steam Dome Pressure - High (B21-PS-N023 A,B,C,D) < 0.55 g 4. Reactor Vessel Water Level - Level #1 (B21-LIS-N017 A,B,C,D) < 1.05 s

5. Main Steam Line Isolation Valve-Cloaure (B21-F022 A,B,C,D and B21-F028 A,B,C,D) i < 0.06

6. Main Steam Line Radiation - High (D12-RM-K603 A,B,C,D) NA

7. Drywell Pressure - High (C72-PS-N002 A,B,C,D) NA

8. Scram Discharge Volume Water Level - liigh (Cl2-LSH-N013 A,B,C,D) NA (Cl2-LSH-4516A,B,C,D) l

9. Turbine Stop Valve - Closure (EHC-SVOS-lX,2X,3X,4X) < 0.06

10. Turbine Control Valve Fast Closure, Control Oil Pressure - Iow (EHC-PSL-1756,1757,1758,1759) < 0.08 g 11. Reactor Mode Switch in Shutdown Position (C72A-SI) NA g 12. Manual Scram (C72A-S3 A,B) NA y

• Neutron detectors are exempt from response time testing. Response time shall be measured from detector output or input of first electronic component in channel.

~

TABLE 4.3.1-1 (Concinued)

E

{

m REACT 6R PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS P'

s CHANNEL OPERATIONAL 6 IUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH Q AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a) SURVEILLANCE REQUIRED

6. Main Steam Line Radiation-High S M(I) R(3) 1, 2 (D12-RM-K603A,B C.D)

7. Drywell Pressure - High (C71-PS-N002A,B,C D) NA M 0 1, 2

+

8. Scram Discharge Volutte Water

Level - High NA Q R 1, 2, 5 (C 11-LSil-No 13A ,B ,C ,D) ,

! (Ci l-LSil-4516A, B ,C, D) s .

l

9. Turbine Stop Valve - Closure NA M R(h) g y (EllC-SVOS-lX,2X,3X,4X) m ,

10. Turbine Control Valve Fast Closure, Control Oil Pressure-Low (EHC-PSL-1756,1757,1758, NA M R 1 1759)

11. Reactor Mode Switch In Shutdown NA R NA 1,2,3,4,5 Position (C71A-SI)

12. Manual Scram NA Q NA 1,2,3,4,5 (C71A-S3A,B)

$ a. Neutron detectors Ey be excluded from CHANNEL CALIBRATION.

, $ h. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to start-up, if not performed within the previous 7 days.

8' c.

The LRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each

, 3 start-up, if not performed within the previous 7 days.

d. When changing from CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter j @

entering CONDITION L e.

l This calibration shall consist of the adjustment of the APRM readout to conform to the power values -

calculated by a heat balance during CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.

TABLE 4.3.1-1 (Continued)

, REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

o E CHANNEL OPERATIONAL

$ FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

8. Scram Discharge Volume Water E Level - High NA Q R 1, 2, 5 U (C12-LSH-N013 A,B,C,D) w (Cl 2-LSil-4516A, B ,C, D) f

9. Turbine Stop Valve - Closure NA M R 1 (EllC-SVOS-lX,2X,3X,4X)

10. Turbine Control Valve Fast Closure, Control Oil Pressure - N.

Low (EHC-PSL-1756,1757,1758,1759) NA M R 1

11. Reactor Mode Switch in Shutdown NA R NA 1,2,3,4,5 g Position (C72A-SI) s~  ;

y 12. Manual Scram NA Q NA 1,2,3,4,5 cn (C72A-S3A,B)

a. Neutron detectors may be excluded from CHANNEL CALIBRATION.

b. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to start-up, if not performed within the previous 7 days.

c. The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each start-up, if not performed within the previous 7 days.

d. When changing from CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering CONDITION 2.

e. This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.

f . This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a k calibrated flow signal.

g g. The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.

g h. This calibration shall consist of a physical inspection and actuation of these position switches.

g 1. Instrument alignment using a standard current source.

J. Calibration using a standard radiation source.

ATTACHMENT 5

SUBJECT:

Post-Accident Monitoring Instrumentation (Drywell Area Radiation Monitors)

REASON FOR TECHNICAL SPECIFICATION (TS) CHANGE: NUREG-0737, Item II.F.1 3 JUSTIFICATION FOR CHANGE: The design and installation of this equipment meets Class 1E standards and meets or exceeds all applicable criteria for Brunswick Steam Electric Plant. The interface with, and potential impact on existing plant systems is extremely minimal. The information made available by this instrumentation will assist the operator in detection and evaluation of potential safety hazards and therefore will have a net positive effect on overall plant safety.

/

TABLE 3.3.5.2-1 N

@ REMOTE SHUTDOWN MONITORING INSTRUMENTATION 2

R MINIMUM M READOUT CHANNELS

' FUNCTIONAL UNIT AND INSTRUMENT NUMBER LOCATION OPERABLE E

[j 1. Reactor Vessel Pressure RSP* 1 g (C32-PI-3332 and C32-PT-3332)

2. Reactor Vessel Water Level RSP* 1 (B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A, B21-LT-N017D-3, and 821-LSH-N017D-3) i

3. Suppression Chamber Water Level RSP* 1 (CAC-LI-3342 and CAC-LT-3342) s,

4. Suppression Chamber Water Temperature RSP* 1  ;

(CAC-TR-778-7) c2 l 3: 5. Drywell Pressure RSP* 1 u, (CAC-PI-3341 and CAC-PT-3341) '

L

• 6. Drywell Temperature RSP* 1 (CAC-TR-778-1,3,4)

7. Residual Heat Removal Head Spray RSP* 1 Flow (Ell-FT-3339 and Ell-F1-3339)

8. Residual Heat Removal System Flow RSP* 1 (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)

9. Residual Heat Removal Service Water RSP* 1 Discharge Differential Pressure l hf (Ell-PDT-N002BX and Ell-PDI-3344)

• Remote Shutdown Panel, Reactor Building 20' Elevation e

1 l

$ TABLE 4.3.5.2-1 Q REMOTE SilUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS M

M CHANNEL CHANNEL

' FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION E

y 1. Reactor Vessel Pressure M Q g (C32-PI-3332 and C32-PT-3332)

2. Reactor Vessel Water Level M Q (B21-LI-3I31, B21-LI-R604AX, B21-LT-3331, B21-!.T-N026A, B21-N017D-3, and B21-LSil-N017D-3)

3. Suppression Chamber Water Level M R (CAC-LI-3342 and CAC-LT-3342) s,

4. Suppression Chamber Water Temperature M R R. (CAC-TR-778-7) c y 5. Drywell Pressure (CAC-PI-3341 and CAC-PT-3341) M Q

6. Drywell Temperature (CAC-TR-778-1,3,4) M R

7. Residual lieat Removal Head Spray Flow (Ell-FT-3339 and Ell-FI-3339) M Q

8. Residual lleat Removal System Flow M - Q (E11-FT-3338, El1-F1-3338, and El1-FY-3338) l

9. Residual lleat Removal Service Water Discharge M Q Differential Pressure (E.'l-PDT-N002BX g and Ell-PDI-3344)

B n

.O

, TABLE 3.3.5.2-1 REMOTE SilUTDOWN MONITORING INSTRUMENTATION ,

e p MINIMUM

, READOUT CilANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBEa LOCATION OPERABLE E 1. Reactor Vessel Pressure RSP* 1 N - (C32-PI-3332 and C32-PT-3332)

2. Reactor Vessel Water Level RSP* 1 (B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A, B21-LT-N017D-3, and B21-LSil-N017D-3)

! 3. Suppression Chamber Water Level RSP* 1 l (CAC-LI-3342 and CAC-LT-3342) ',

4. Suppression Chamber Water Temperature RSP* 1 g (CAL TR-778-7) s~

y 5. Drywell Pressure RSP* 1 ,

g (CAC-PI-3341 and CAC-PT-3341)

6. Drywell Temperature RSP* 1

( CAC-TR-7 78--1,3,4 )

7. Residual lir.oc Removal llead Spray RSP* 1

[

Flow (Ell-FT-3339 and Ell-FI-3339)

8. Residual lleat Removal System Flow RSP* 1 3

(Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)

9. Residual lleat Removal Service Water RSP* 1 l

k Discharge Differential Pressure g (El1-PDT-N002BX and El1-PDI-3344)

N

$

• Remote Shutdown Panel, Reactor Building 20' Elevation 5

e

, TABLE 4.3.5.2-1 REMOTE SilUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS -

s n CHANNEL CHANNEL FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION S 1. Reactor Vessel Pressure M Q U (C32-PI-3332 and C32-PT-3332) w

2. Reactor Vessel Water Level M Q (B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A, B21-LT-N017D-3, and B21-LSil-N017D-3)

3. Suppression Chamber Water level M R (CAC-LI-3342 and CAC-LT-3342)

N'

4. Suppression Chamber Water Temperature M R (CAC-TR-778-7)

5. Drywell Pressure (CAC-PI-3341 and CAC-PT-3341) M Q Y i g 6. Drywell Temperature (CAC-TR-778-1,3,4) M R

7. Residual lleat Removal Head Spray Flow (Ell-FT-3339 and Ell-FI-3339) M Q l

8. Residual Heat Removal System Flow (EIl-FT-3338, El1-FI-3338, and El1-FY-3338) M Q l

9. Residual lieat Removal Service Water Discharge M Q Differential Pressure (Ell-PDT-N002BX g and Ell-PDI-3344) 9 a

n

.O U - , *