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* -'to NLS9100409 i;
Page 4 of 4 l.
REVISED TECHNICAL SPECIFICATIONS PAGES i.-.
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?11C150334 911007 PDR.. ADOCK 05000298 P
PDR 1
 
4 COOPER NUCLEAR STATION TABLE 3.2.11 POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS
* Minicm Number of Action Required Wen Instrument Operable Instru:nent Cmponent Cperability Instrument ID Number Ranne Channels Is ibt Assured j
Elevated Release Point (ERP)
PJIP - RM - 3 B 1.00E-2 to I (Note 1)
A Monitor (liigh Range Noble 1.00E+5 pc/cc (Xe-133 Gas)
Equivalent)
Turbine Building Ventilation RMV-PJ1-20B 1.00E-2 to 1 (Note 1)
A Exhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas)
(Xc-133 Equivalent)
Radwaste/ Augmented Radwaste RMV-RM-30B 1.00E-2 to 1 (Note 1)
A Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas)
(Xe-133 Equivalent)
~
Primary Containtrent Gross RMA-RM-40A 1.0-1.0Et7 R/Hr.
2 (Note 1)
A Radiation Monitor R&\\-RM-40B 1.0-1.0E+7 R/Hr.
Primary Containment Hydrogen PC-AN-H-/0 1 0% to 30%
2 (Notes 1 and 2)
B 2
Concentration Analyzer PC-AN-H /011 0% to 30%
2 2
* Note:
Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Suppression Cha..ber/ Torus Water Level PC-LR-1A and 13 Drpell Pressure. PC-PR-1A and 13.
m
 
..._.-...._____._.__m
.v z.w NOTES:FOR TABLE 3.2.H-Action:-
'A.-
' With i the number of ' operable components less than required by the minimum
. component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. parameter (s):within 72 hours, and:
1)-
Either - res tore the inoperable : component (s)- to operable 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 action taken, the cause of: the inoperabilityL'and the plans. and schedule: for restoring - the system to operable _ status.
B.
The following -- actions will. be taken -l if the minimum number of operable instrument _ channels as required are not operable:
1)
Vith th'e' number -of operable channels one less than-the minimum number of
. operable ' channels - shown, l restore. the inoperable channel to operable status'within 30 days or be in at least hot shutdown within the next' 12 hours.
_2);
-With no operable channels available,. restore at.least one channel to operable status within 7 dayr or be in at least hot shutdown'within the next 12 hours.
Notes:
l-1.
These instruments are required'to be' operable at all times except w'c.en the -
' reactor is in-cold shutdown or in the REFUEL mode during a refueling outage.
2,-
With two channels operable, the normal. condition is with one analy::er. in the standby _ mode,
(
k (n
l r
i-
-67b-l
_._-.,,c_
 
~
i;.
q-c; u
' COOPER NUCLEAR STATION TABLE 4. 2.11-
: CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION
* Instrument:
LFunction-
' Calibration Instrument ID' Number' Test'Freauency' Frecuenev' Elevated Release Point l(ERP)
. Monitor (High Range Noble'
:RMP-RM-3B:
.Once/ Month;
'Once/ Cycle:
Gas)
Turbine Building Ventilation RMV-RM-20B
'Once/ Month Once/Gycle' Exhaust Monitor' (High Range Noble Cas)
Radwaste/ Augmented Radwaste-'
RMV-RM-30B.
Once/ Month Once/ Cycle-Exhaust Monitor ~
(Iligh Range Noble Gas)
Primary Containment Gross RMA-RM-40A'
'Once/ Month
-Once/ Cycle 7
Radiation Monitors **
RMA-RM-40B; l'
Primary Containment Hydrogen
.'PC-AN-H /0 1 Once/ Month
'Once/ Quarter' 2 2 Concentration Analyzer PC-AN-H /0 II 2 2 i
* Note:
Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2..F-Drywell' Pressure, i
PC-PR-1A and 13, Suppression Chamber / Torus Water ' Level PC-IR-1A and 1B.
-i 5
+
** CHANNEL CALIBRATION shall consist of an electronic ' calibration of the channel,. not.
including.the.
detector, for range decades above 10.R/hr and a one point calibration check of the' detector below 10 R/hr with an installed or portable gamma source.
i h
i
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Latest revision as of 03:44, 14 December 2024

Proposed Tech Spec Table 3.2.H Re post-accident Monitoring Instrumentation Requirements & Table 4.2.H Re Calibr Frequency for post-accident Monitoring Instrumentation
ML20085D203
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/07/1991
From:
NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20085D200 List:
References
NUDOCS 9110150334
Download: ML20085D203 (4)
v • d • e


Text

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  • -'to NLS9100409 i;

Page 4 of 4 l. REVISED TECHNICAL SPECIFICATIONS PAGES i.-. l l ~ ?11C150334 911007 PDR.. ADOCK 05000298 P PDR 1

4 COOPER NUCLEAR STATION TABLE 3.2.11 POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS

  • Minicm Number of Action Required Wen Instrument Operable Instru:nent Cmponent Cperability Instrument ID Number Ranne Channels Is ibt Assured j

Elevated Release Point (ERP) PJIP - RM - 3 B 1.00E-2 to I (Note 1) A Monitor (liigh Range Noble 1.00E+5 pc/cc (Xe-133 Gas) Equivalent) Turbine Building Ventilation RMV-PJ1-20B 1.00E-2 to 1 (Note 1) A Exhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) (Xc-133 Equivalent) Radwaste/ Augmented Radwaste RMV-RM-30B 1.00E-2 to 1 (Note 1) A Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) (Xe-133 Equivalent) ~ Primary Containtrent Gross RMA-RM-40A 1.0-1.0Et7 R/Hr. 2 (Note 1) A Radiation Monitor R&\\-RM-40B 1.0-1.0E+7 R/Hr. Primary Containment Hydrogen PC-AN-H-/0 1 0% to 30% 2 (Notes 1 and 2) B 2 Concentration Analyzer PC-AN-H /011 0% to 30% 2 2

  • Note:

Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Suppression Cha..ber/ Torus Water Level PC-LR-1A and 13 Drpell Pressure. PC-PR-1A and 13. m

..._.-...._____._.__m .v z.w NOTES:FOR TABLE 3.2.H-Action:- 'A.- ' With i the number of ' operable components less than required by the minimum . component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. parameter (s):within 72 hours, and: 1)- Either - res tore the inoperable : component (s)- to operable 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 action taken, the cause of: the inoperabilityL'and the plans. and schedule: for restoring - the system to operable _ status. B. The following -- actions will. be taken -l if the minimum number of operable instrument _ channels as required are not operable: 1) Vith th'e' number -of operable channels one less than-the minimum number of . operable ' channels - shown, l restore. the inoperable channel to operable status'within 30 days or be in at least hot shutdown within the next' 12 hours. _2); -With no operable channels available,. restore at.least one channel to operable status within 7 dayr or be in at least hot shutdown'within the next 12 hours. Notes: l-1. These instruments are required'to be' operable at all times except w'c.en the - ' reactor is in-cold shutdown or in the REFUEL mode during a refueling outage. 2,- With two channels operable, the normal. condition is with one analy::er. in the standby _ mode, ( k (n l r i- -67b-l _._-.,,c_

~ i;. q-c; u ' COOPER NUCLEAR STATION TABLE 4. 2.11-

CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION
  • Instrument:

LFunction- ' Calibration Instrument ID' Number' Test'Freauency' Frecuenev' Elevated Release Point l(ERP) . Monitor (High Range Noble'

RMP-RM-3B:

.Once/ Month; 'Once/ Cycle: Gas) Turbine Building Ventilation RMV-RM-20B 'Once/ Month Once/Gycle' Exhaust Monitor' (High Range Noble Cas) Radwaste/ Augmented Radwaste-' RMV-RM-30B. Once/ Month Once/ Cycle-Exhaust Monitor ~ (Iligh Range Noble Gas) Primary Containment Gross RMA-RM-40A' 'Once/ Month -Once/ Cycle 7 Radiation Monitors ** RMA-RM-40B; l' Primary Containment Hydrogen .'PC-AN-H /0 1 Once/ Month 'Once/ Quarter' 2 2 Concentration Analyzer PC-AN-H /0 II 2 2 i

  • Note:

Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2..F-Drywell' Pressure, i PC-PR-1A and 13, Suppression Chamber / Torus Water ' Level PC-IR-1A and 1B. -i 5 +

    • CHANNEL CALIBRATION shall consist of an electronic ' calibration of the channel,. not.

including.the. detector, for range decades above 10.R/hr and a one point calibration check of the' detector below 10 R/hr with an installed or portable gamma source. i h i ~ =a}}

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