ML20117P391

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Corrected TS Pages to Amend 167 to License DPR-30,correcting License Condition 3.L.h
ML20117P391
Person / Time
Site: Quad Cities 
Issue date: 09/19/1996
From: Anthony Giambusso
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20117P392 List:
References
NUDOCS 9609230203
Download: ML20117P391 (2)


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3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 167, are hereby incorporated in the license. The licensee shall operate the facility in accordance j

with the Technical Specifications.

3.L Surveillance Reauirements The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be j

performed immediately upon implementation of Amendment No.

I a.

Surveillance Requirement 4.2.A.2 - Logic System Functional Test for Isolation Actuation Instrumentation, Table 4.2.A-1, Item 4.a, Reactor Water Cleanup (RWCU) isolation on Standby i

Liquid Control (SBLC) initiation.

l b.

Surveillance Requirement 4.2.A.2 - Logic System Functional Test for Isolation Actuation Instrumentation, Table 4.2.A-1, l'

Item 2.a, 2.b, 2.c, and 2.d, Secondary Containment isolation.

c.

Surveillance Requirement 4.9.C.2 - Logic System Functional Test for Anticipated Transient Without Scram (ATWS) -

Recirculation Pump Trip (RPT).

d.

Surveillance Requirement 4.1.A.1 - Turbine Stop Valve, closure, RPS Calibration, table 4.1. A-1, Item 9.

Surveillance Requirement 4.4.A.4.a - Standby Liquid Control e.

Initiation, f.

Surveillance Requirement 4.9.A.8.h - Emergency Diesel Generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.

g.

Surveillance Requirement 4.9.A.8.c - Emergency Diesel Generator full load reject test.

h.

Surveillance Requirement 4.1.A.1 - Main Steam Line Isolation Valve Closure, RPS Calibration, Table 4.1.A-1, Item 5.

Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (Q2R14).

9609230203 960919 PDR ADOCK 05000265 P

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a.

Surveillance Requirement 4.4.A.4.a - Standby Liquid Control Initiation.

f.

Surveillance Requirement 4.9.A.8.h - Emergency Diesel Generator 4

24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.

T l

g.

Surveillance Requirement 4.9.A.8.c - Emergency Diesel Generator full load reject test.

h.

Surveillance Requirement 4.1.A.1 - Main Steam Line Isolation Valve closure, RPS Calibration, Table 4.1.A-1, Item 5.

Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the j

fourteenth refueling outage (Q2R14).

l 4.

This license is effective as of the date of issuance, and shall expire at l

midnight, December 14, 2012.

FOR THE ATOMIC ENERGY COMMISSION 1

Original signed by:

i A. Giambusso, Deputy Director j'

for Reactor Projects Division of Licensing

Enclosures:

Appendices A and B -- Technical Specifications Date of Issuance: December 14, 1972 l

Amendment No. 167

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