ML20132G992

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Errata to Amend 89 to License NPF-42.Change to TS 3.3.3.6 Had Not Been Incorporated Into Revised TS
ML20132G992
Person / Time
Site: Wolf Creek 
Issue date: 12/18/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20132G994 List:
References
NUDOCS 9612270104
Download: ML20132G992 (2)


Text

. _.. _. _ __.. _. _. _

TABLE 4.3-6 i

REMOTE SHUTDOWN MONITORING INSTRUMENTATION I

SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

RCS Pressure - Wide Range M

R 2.

Reactor Coolant Temperature - Cold Leg M

R 3.

Source Range, Neutron Flux #

M R

4.

Reactor Trip Breaker Indication M

N.A.

l 5.

Reactor Coolant Temperature - Hot Leg M

R

~

6.

Reactor Coolant Pump Breakers N.A.

N.A.

7.

Pressurizer Pressure M

R l

8.

Pressurizer Level M

R 4

9.

Steam Generator Pressure M

R

10. Steam Generator Level M

R

11. Auxiliary Feedwater Flow Rate M

R d

12. Auxiliary Feedwater Pump Suction Pressure M

R 1

i i

i

  1. Not required OPERABLE in MODE 1 or in MODE 2 above P-6 Setpoint.

4 WOLF CREEK - UNIT 1 3/4 3-45 Amendment No.89 l

9612270104 961218 PDR ADOCK 05000482 P

PDR

INSTRUMENTATION l

ACCIDENT MONITORING INSTRUMENTATION t

LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 30 days or prepare and submit a Special Report to the Commission pursuant to Technical Specification 6.9.2 within the following 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status, b.

With the number of OPERABLE accident monitoring instrumentation channels, except for instrument functions 10,16 and 18 (Containment Hydrogen Concentration Level, Containment Radiation Level, and the Reactor Vessel Level Indicating System), less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore one channel to OPERABLE status within 7 days; otherwise, be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With the number of OPERABLE channels for instrument functions 16 and 18 (Containment Radiation Level and the Reactor Vessel Level Indicating System), less than the Minimum Channels OPERABLE requirements of Table 3.3-10, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and either restore one inoperable channel to OPERABLE status within 7 days, or prepare and submit a Special Report to the Commission pursuant to Technical Specification 6.9.2 within the following 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status, d.

With the number of OPERABLE channels for the containment hydrogen concentration level monitor less than the Minimum Channels OPERABLE requirement of Table 3.3-10, restore one channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e.

The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-7.

WOLF CREEK - UNIT 1 3/4 3-46 Amendment No. 89 l