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s Attachment 1-'to i;
NLS9100409 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 ID Number                  Ranne            Channels            Is ibt Assured j                              Instrument 1.00E-2 to                  I (Note 1)              A Elevated Release Point (ERP)                PJIP - RM - 3 B Monitor (liigh Range Noble                                      1.00E+5 pc/cc Gas)                                                            (Xe-133 Equivalent) 1 (Note 1)                A Turbine Building Ventilation                RMV-PJ1- 20B            1.00E-2 to 1.00E+5 pc/cc Exhaust Monitor (High Range Noble Gas)                                          (Xc-133 Equivalent) 1.00E-2 to                  1 (Note 1)                A Radwaste/ Augmented Radwaste                RMV-RM-30B Eyhaust Monitor                                                1.00E+5 pc/cc (High Range Noble Gas)                                          (Xe-133
  ~                                                                            Equivalent) 1.0-1.0Et7 R/Hr.            2 (Note 1)              A Primary Containtrent Gross                  RMA-RM-40A Radiation Monitor                        R&\-RM-40B              1.0-1.0E+7 R/Hr.
Primary Containment Hydrogen                PC-AN-H-/0 21          0% to 30%                  2 (Notes 1 and 2)        B Concentration Analyzer                  PC- AN-H    2 /011 2        0% to 30%
* Note:          Other Post-Accident Monitoring Instrunentation is located in Table 3.2.F-Drpell Pressure. PC-PR-1A and 13. Suppression Cha..ber/      m    Torus Water Level PC-LR-1A and 13
 
  ,          -        ,                          . . , .        _    ..._.-...._____._.__m                              _ . _ - .
            .v z .w    .
NOTES:FOR TABLE 3.2.H-Action:-
                              ' With i the number of ' operable components less than required by the minimum
                      'A.-
                              . 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,
(
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        ._            .                              ~                                -
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                                                            ' 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-H2 /0    2 1                Once/ Month            'Once/ Quarter' Concentration Analyzer                                PC-AN-H      2 2/0 II 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 i
_                  _ . . .          ~      -,. .            -    -_ -.            _ . _ _ _      _ - _ =a}}

Revision as of 15:52, 13 May 2020

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)


Text

- - - .. . . .

s Attachment 1-'to i;

NLS9100409 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 ID Number Ranne Channels Is ibt Assured j Instrument 1.00E-2 to I (Note 1) A Elevated Release Point (ERP) PJIP - RM - 3 B Monitor (liigh Range Noble 1.00E+5 pc/cc Gas) (Xe-133 Equivalent) 1 (Note 1) A Turbine Building Ventilation RMV-PJ1- 20B 1.00E-2 to 1.00E+5 pc/cc Exhaust Monitor (High Range Noble Gas) (Xc-133 Equivalent) 1.00E-2 to 1 (Note 1) A Radwaste/ Augmented Radwaste RMV-RM-30B Eyhaust Monitor 1.00E+5 pc/cc (High Range Noble Gas) (Xe-133

~ Equivalent) 1.0-1.0Et7 R/Hr. 2 (Note 1) A Primary Containtrent Gross RMA-RM-40A Radiation Monitor R&\-RM-40B 1.0-1.0E+7 R/Hr.

Primary Containment Hydrogen PC-AN-H-/0 21 0% to 30% 2 (Notes 1 and 2) B Concentration Analyzer PC- AN-H 2 /011 2 0% to 30%

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

, - , . . , . _ ..._.-...._____._.__m _ . _ - .

.v z .w .

NOTES:FOR TABLE 3.2.H-Action:-

' With i the number of ' operable components less than required by the minimum

'A.-

. component operable requirements L initiate the preplanned alternate method of monitoring theJappropriate. 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 - 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

_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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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,

(

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' 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-H2 /0 2 1 Once/ Month 'Once/ Quarter' Concentration Analyzer PC-AN-H 2 2/0 II 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 i

_ _ . . . ~ -,. . - -_ -. _ . _ _ _ _ - _ =a