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MONTHYEARML19320C0351980-07-10010 July 1980 Forwards Suppl to 800211 Reload Rept Describing Info Supporting Repairs Made to Failed Springs in Fuel Assemblies Project stage: Other ML20041G3831982-02-28028 February 1982 Cycle 3 - Reload Rept Project stage: Other ML20041G3791982-03-0505 March 1982 Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3 Project stage: Request ML20041G3811982-03-0505 March 1982 Application to Amend License NPF-3,allowing Rector Startup W/O Trip & Changing Tech Specs for safety-grade Anticipatory Reactor Trip Sys Project stage: Request ML20041E7421982-03-0505 March 1982 Advises That Inclusion of Emergency Diesel Generator Fuel Oil in QA Program Should Be Completed by 820415 Project stage: Request ML20041G3821982-03-0505 March 1982 Proposed Tech Spec Tables 4.3-15 & 3.3-15 Re Anticipatory Reactor Trip Sys Instrumentation Project stage: Other IR 05000346/19820101982-03-23023 March 1982 IE Insp Rept 50-346/82-10 on 820301-04.No Noncompliance Noted.Major Areas Inspected:Collection of Samples,Qa & QC of Analytical Measurements Project stage: Request ML20050A5131982-03-23023 March 1982 Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept) Project stage: Request ML20050A5081982-03-23023 March 1982 Forwards Revised Application for Amend to License NPF-3 Consisting of Changes to Tech Specs Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept) Project stage: Request ML20050A5151982-03-23023 March 1982 Tech Spec Changes to Figures 3.1-2a & 3.1-3a of Cycle 3 Reload Rept BAW-1707 (Figures 8-5 & 8-10 of Rept).Safety Evaluation Encl Project stage: Other ML20053B0061982-05-11011 May 1982 Forwards Request for Addl Info in Order to Complete Application for License Amend Re Cycle 3 Reload.Response Needed by 820528 Project stage: RAI ML20053D5841982-06-0101 June 1982 Forwards Application for Amend to License NPF-3 Re Reactor Protection Sys Trip Setpoints Contained in Cycle 3 Reload Rept Project stage: Request ML20053D9731982-06-0101 June 1982 Tech Specs,App A,Reflecting Changes Contained in Cycle 3 Reload Rept Project stage: Other ML20053D9701982-06-0101 June 1982 Application for Amend to License NPF-3,revising Reactor Protection Sys Trip Setpoints Project stage: Request ML20054J6571982-06-21021 June 1982 Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707,Feb 1982 Project stage: Request ML20054J6501982-06-21021 June 1982 Forwards Application for Amend to License NPF-3,revising Tech Specs to Reflect Proposed Changes Re Reactor Protection Sys Response Time Omitted in Cycle 3 Reload rept,BAW-1707 Project stage: Request ML20054J6581982-06-21021 June 1982 Proposed Tech Spec Table 3.3.2 Re Reactor Protection Instrumentation Response Times Project stage: Other ML20054L1841982-06-28028 June 1982 Informs That Util 820305 Submittal Contained Table 6-2, Including Basis for Determining Worst Case Rod Bow Penalty, Per NRC Request Re License Amend Application Project stage: Other ML20062D5001982-07-28028 July 1982 Safety Evaluation Supporting Amend 45 to License NPF-3 Project stage: Approval 1982-05-11
[Table View] |
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"8 cU RS TABLE 4.3-15 Om ANTICIPATORY REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS gy ou CHANNEL MODES IN MIICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS
$$O FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED m o-1.
Turbine Trip S
N.A.
M 1,
2.
Main Feed Pump Turbine Trip S
N.A.
M yy 3.
Output Logic N.A.
N.A.
M 1,2 O Applicable only above 25% reactor power
- In Mode 2, applicable when main feed pump is the only source of feedwater.
TABLE 3.3-15
. ANTICIPATORY REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL TOTAL NO.
CHANNELS MINIMUM APPLIC-UNIT OF TO CilANNELS ABLE CHANNELS TRIP OPERABLE
_ MODES ACTION
- 1. Turbine Trip 4
2 3
1*
16
- 2. Main Feed Pump Turbine Trip 4
2 3
1,2n *
-17
- 3. Output Logic 4
2 3
1,2 18 ACTION 16 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, restore the inoperable 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 /> or reduce reactor power to less than 25% full power within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 17 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, restore the inoperable 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 /> or 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 />.
ACTION 18 - With the number of OPERABLE channels one less than the Total Num I
of Channels, STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied:
a) The control rod drive trip breaker associated with the inoperable channel is placed in the tripped condition within one hour.
b) The Minimum Channels OPERABLE requirement is met; however, one..
- - - ~ ~ - - -
additional control rod drive trip breaker associated with another channel may be tripped for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.for surveillance l
testing per Specification 4.3.2.3, after reclosing the control I
rod drive trip breaker opened in a) above.
- Applicable only above 25% reactor power.
- In Mode 2, applicable when main feed pump is the only source of feedwater.
i I
(
l 1