Letter Sequence Other |
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Results
Other: 05000298/LER-1983-011-01, /01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced, 05000368/LER-1982-020-03, /03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D01, A830019, Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code, ML20024D981, ML20027B539, ML20080D807, ML20080D823
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MONTHYEAR05000368/LER-1982-020-03, /03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D011982-06-25025 June 1982
/03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D01
Project stage: Other
ML20027B5391982-09-13013 September 1982
Forwards Requested Info Re Auxiliary Feedwater Stabilized Internal Header.Includes B&W Info Re Commitment to Prepare Design Rept for Modified Steam Generator & Auxiliary Feedwater Piping Sys
Project stage: Other
05000298/LER-1983-011-01, /01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced1983-07-20020 July 1983
/01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced
Project stage: Other
ML20024D9811983-07-28028 July 1983
Advises That Responsibility for Evaluating Proposed Actions Re IE Bulletin 83-02 Concerning Recirculation Sys Pipe Cracks Transferred to Div of Licensing
Project stage: Other
A830019, Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code1983-08-23023 August 1983
Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code
Project stage: Other
ML20080D8231983-08-25025 August 1983
Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage During Cycle 9 Operation
Project stage: Other
ML20080D8071983-08-25025 August 1983
Forwards Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage, During Cycle 9 Operation,Per 830824 Request
Project stage: Other
1983-07-20
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o LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C.
Coolant Leakage C.
Ceclant Leakage 1.
Any time irradiated fuel is in 1.
Reactor coolant system leakage shall i
the reactor vessel and reactor be checked by the air samp-ll coolant temperature is above 212*F, ling system and recorded at least reactor coolant leakage into the once per day, primary containment from unidentified sources shall not exceed 5 gpm.
In 2.
Reactor coolant system leakage shall addition, the identified reactor cool-be checked by the sump system and ant system leakage into the primary recorded at least once per 4 hours.
containment shall not exceed 25 gpm.
2.
The containment atmospheric radiation monitor and the containment at-mospheric sampling systems shall be operable during reactor power operation.
From and after the date that one of these systems is made or found to be inope.rable for any reason, reactor power operation is permissible only during the succeeding 30 days unless tha system is made operable sooner.
3.
If the specifications 3.6.C.1 & 2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours.
4.
After the first 24 hours in the run mode following startup, reactor coolant system leakage into the primary con-tainment from unidentified sources shall be limited to a 2 gpm increase within the previous 24-hour period.
If this specification cannot be met, identify the source of leakage or be in a Cold Shutdown Condition within 24 hours.
5.
The sump flow measuring system shall be operable during reactor power operation.
From and after the time that this system is made or found to be inoperable for any reason, reactor power operation is permissible only during the succeeding 24 hours unless the system is made operable sooner.
NOTE:
This page of the Technical Specifications is applicable to Cycle 9 operation only and supersedes page 135 issued with 8308300597 830825 Amendment 7 to the license.
PDR ADOCK 05000298 P
PDR
-135-
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