ML20073A636

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Replacement Tech Spec Pages Re Accident Monitoring Instrumentation
ML20073A636
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/18/1991
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20073A631 List:
References
NUDOCS 9104230288
Download: ML20073A636 (8)
v • d • e


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ATTACHMENT ll TO JPN 91-014 REPLACEMENT TECHNICAL SPECIFICATION PAGES ACCIDENT MONITORING INSTRUMENTATION AMENDMENT (JPTS-89015) l l

l' New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 i

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l. l 9104230288-91041s PDR ADOCK 05000333 F PDR

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JAFNPP 3.2 (cont'd) 42 (cont'd) ,

E Drywell Leak Detection E Drywell Leak Detection The limiting conditions of operation for the instrumentation that instrumentation shall be calibrated and checked as indicated in monitors drywell leak detection are given in Table 32-5. Table 42-5 F. (Deleted) F. (Deleted)

G. Recirculation Pump Trip G. Recirculation Pump Trip The limiting conditions for operation for the instrumentation that Instrumentation sha!! be functionally tested and calibrated as trip (s) the recirculation pumps as a means of limiting the indicated in Table 42-7 consequences of a failure to scram during an anticipated transient are given in Table 32-7. System logic shall be functiona!!y tested as indicated in Table 42-7.

H. Accident Monitoring instrumentation H. Accident Monitoring Instrumentation The limiting conditions for operation of the instrumentation that

. provides accident monitoring are given in Table 32-8' instrumentation shall be demonstrated operable by performance of a channel check and channel calibration as indicated in Table

1. 4kv Emergency Bus Undervoltage Trip 42-8.

3 The limiting conditions for opera' ion for the irstrumentation that prevents damage to electrical equipment or circuits as a result of either a degraded or loss-of-voltage condition on the emergency efectrical buses are given in Table 32-2.

Amendment No.1jiMS, ti!6 54

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JAFNPP

, TABLE 3.2-8  !

[  ;

i-ACCIDENT MONITORING INSTRUMENTATION i .

No.of Channels Minirnum No. of Mode in Which Provided by Operable Channels Instrument Must j instrument l Design Required be Operable Action l '

1. Stack High Range Effluent Monitor 2 1 Note H Note 8
j (17RM-53A)

(17RM-538)

2. Turbine Building Vent High Range Effluent Monitor 2 Note H

, 1 Note B

1. (17RM-434A)  ;

i (17RM-4348) '

3. Radwaste Building Vent High Range Effluent Monitor . 2 1 Note H Note B

' (17RM-463A)  :

(17RM-4638)

' 4. Containment High Range Radiation Monitor 2 1 Note H Note A

, (27RM-104A)

(27RM-1048) 5.' Drywell Pressure (narrow range) 2

' 1 NoteJ Note A I

'(27PI-115A1 or 27PR-115A1)

(27PI-11581 or 27PR-11581) i

6. Drywell Pressure (wide range) -

2 1 Note J Note A  :

(27PI-115A2 or 27PR-115A2) i (27PI-11582 or 27PR-11582) ' '

7. DrywellTemperature 2 1 Note J Note A j- .(16-1TR-107) -

(16-1TR-108) .

f J

  • At less than or equal to 450 R/hr, closes vent and purge valves

' Amendment No.}36 77a i J

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, JAFNPP  !

j .

j TABLE 3.2-8 (cont'd)  ?

i i

ACCIDENT MONITORING INSTRUMENTATION No.of Channels Minimum No.of Mode in Which

Provided by Operable Channels Instrument Must ,

j instrument Design Required be Operable Action  ;

4

8. Torus Water Level (wide range) 2 1 Note J Note A I (230-202A or 23LR-202A/203A)

(23U-2028 or 23LR-202B/2038) -

9. . Torus Bulk Water Temperature 2 1 Note J Note A  !

(16-1TI-131 A or 16-1TR-131 A)

(16-1TI-1318 or 16-1TR-1318)

10. - Torus Pressure 2 1 Note J Note A ,

(27PR-101 A)- '

(27PR-10181)

~

~

11. Drywell Hydrogen / Oxygen Concentration 2.

1 NoteJ Note F (27PCR-101 A) .

' (27PCR-1018)

.12. - ReactorVessel Pressure 2 1-4- . Note J . Note A (06PI-61 A or 06PR-61 A) 1 (06PI-61B or 06PR-618) 13.. Reactor Water Level (fuel zone) . 2 1 Note J Note A (02-3U-091) . '

t

. (02-3LR-098) .  !

14. Reactor Water Level (wide range) 2 Nc,*o J '

1 Note A (02-3U-85A) '

(02-3LR-858) j.

e

!- ' Amendment No M - .

77b

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pp TABLE 3.2-8 (cont'd) .

t ACCIDENT MONITORING INSTRUMENTATION No. of Channels Minimum No. of Mode in Which Provided by Operable Channels instrument Must lastrument Design Required be Operable Action

15. Core Spray Row 1 per loop 1 per loop Ns 'e J Note A

!~Jp A (14F1-50A) loop B (14R-508)

16. Core Spray discharge pressure 1 per loop 1 per loop Note J Note A loop A (14PI-48A) loop B (14PI-488)
17. LPCI (RHR) Row 2 per loop 1 per loop Note J Note A loop A (t0FI-133A)

(10FR-143 - red pen) loop B (10R-1338)

(10FR-143 - black pen)

, 18. RHR Service Water Flow 1 per loop 1 per loop Note J Note A l loop A (10Fi-132A) loop B (10R-1328) l 19. Safety / Relief Valve Position Indicator 2 1 Note J Notes D, E (See Note C)

20. Torus Water Level (narrow range) 2 1 Note J Note B (23LI-201 A or 27R-101 - red pen or EPIC A-1258)

(EPIC A-1260)

(See Note G) -

21. Drywell-Torus Differential Pressure 2 1 Note J Note B (16-1DPR-200 or EPIC A-3554)

(EPIC A-3551)

(See Note G)

Amendment No.

77c

l

. l JAFNPP i l

TABLE 3.2-8 (Cont'd)

ACCIDENT MONITORING INSTRUMENTATION l l

NOTES FOR TABE 3.2-8 A.- With tee number of operable channels less than the required minimum, either restore the inoperable channels to operable status within 30 days, or be in e cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

.B. With the number of OPERABE channels less than required by the minimum channels OPERABE requirements, initiate an alternate method of monitoring the appropriate parametar(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 the inoperable channel (s) to OPERABE status within 7 days of the event, or '2) prepare and submit a Special Report to the Commission within 14 days following the event outlining the cause of the

-inoperability, he action taken, and the plans and schedule for restoring the system to OPERABE status.-

C. Each Safety / Relief Valve is equipped with two acoustical detectors, one of which is in service. Each SRV also has a backup thermocouple detector. In the ev=t that a thermocouple is inoperable, SRV performance shall be monitored daily with the associated in service acoustical

' detector.

D. From and after the date that both of the acoustical detectors are inoperable, continued operation is' permissible until the next outage in which a primary containment entry is made provided that the thermocouple is operable. Both acoustical detectors shall be made operable prior to restart.

E. In the event that both pr: mary (acousticai detectors) and secondary (thermocouple) indications of this parameter for any one valve are disabled

^ and neither indication can be restored in forty-eight (48) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in twelve (12) hours and in a Cold Shutdown within the next twenty-four (24) hours.

F. Refer to Specification 3.7.A.9.

G. This parameter and associated instrumentation are not part of post-accident monitoring.

. H. ~ This instrument shall be operab;e in the Run, Startup/ Hot Standby, and Hot Shutdown modes.

J.' This instrument shall be operable in the Run and Startup/ Hot Standby modes.

l Amendment No.

.77d

l JAFNPP TABLE 4.2-8 .

MINIMUM TEST AND CALIBRATION FREQUENCY FOR ACCIDENT MONITORING INSTRUMENTATION Instrument instrument Instrument Instrument . -

Functional Test Calibration Frequency Check

. Stack High Range Effluent Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day

2. Turbine Building Vent High Range Effluent FAcnitor Once/ Operating Cycle Once/ Operating Cycle Once/ day
3. Radwaste Building Vent High Range Effluent Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day
4. Containment High Range Radiation Monitor Once/ Operating Cycle Once/ Operating Cycle Once/ day ,
5. Drywell Pressure (narrow range) N/A Once/ Operating Cycle Once/dcy l 6. Drywell Pressure (wide range) N/A Once/ Operating Cycle Once/ day
7. Drywell Temperature N/A Once/ Operating Cycle Once/ day j
8. Torus Water Level (wide range) ',q/A Once/ Operating Cycle Once/ day
9. Torus Bu!k Water Temperature N/A Once/ Operating Cycle Once/ day 1
10. Torus Pressure N/A Once/ Operating Cycle Once/ day
11. . Drywell Hydrogen / Oxygen Concentration Analyzer N/A Once/3 months Once/ day
12. Reactor Vessel Pressure N/A Once/ Operating Cycle Once/ day l
13. Reactor Water Level (fuel zone) N/A Once/ Operating Cycle Once/ day l
14. Reactor Water Level (wide range) N/A Once/ Operating Cycle Once/ day Amendment No. 25 86

JAFNPP TABLE 4.2-8 (cont'd) ,

l MINIMUM TEST AND CAllBRATION FREQUENCY FOR ACCIDENT MONITORING INSTRUMENTATION Instrument instrument Instrument Instrument Functional Test Calibration Frequency Check Core Spray Flow N/A Once/ Operating Cycle Once/ day l 15.

16. - Core Spray Discharge Pressure N/A Once/ Operating Cycle Once/ day
17. N/A Once/ Operating Cycle Once/ day LPCI (RHR) Flow
18. RHR Service Water Row N/A Once/ Operating Cycle Once/ day
19. Safety / Relief Va!ve Position Indicatar Once/ Operating Cycle N/A Once/ month (Primary and Secondary)  ;
20. Torus Water Level (narrow range) N/A Once/ Operating Cycle Once/ day
21. Drywell-Torus Differential Pressure N/A Once/ Operating Cycle Once/ day .

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Amendment No. L'Ad l 86a l

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