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

-l 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.

The limiting conditions for opera' ion for the irstrumentation that 3

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

1

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l 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 l

j instrument Design Required be Operable Action l

1.

Stack High Range Effluent Monitor 2

1 Note H Note 8 (17RM-53A) j (17RM-538) 2.

Turbine Building Vent High Range Effluent Monitor 2

1 Note H 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 I

(27RM-104A)

(27RM-1048)

I 5.'

Drywell Pressure (narrow range) 2 1

NoteJ Note A I

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

(27PI-11581 or 27PR-11581)

I 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) i f

J

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

' Amendment No.}36 77a i

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l JAFNPP j

j TABLE 3.2-8 (cont'd)

?

i ACCIDENT MONITORING INSTRUMENTATION

[

i I

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)

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~

11.

Drywell Hydrogen / Oxygen Concentration 2.

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

' (27PCR-1018)

.12. -

ReactorVessel Pressure 2

1-

. Note J.

Note A 4-(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).

. (02-3LR-098).

t Reactor Water Level (wide range) 2 1

Nc,*o J Note A 14.

(02-3U-85A)

(02-3LR-858) j.

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' 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 15.

Core Spray Flow N/A Once/ Operating Cycle Once/ day l

16. -

Core Spray Discharge Pressure N/A Once/ Operating Cycle Once/ day 17.

LPCI (RHR) Flow N/A Once/ Operating Cycle Once/ day 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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