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Category:ARCHIVE RECORDS
MONTHYEARML20217H6331997-07-0202 July 1997 Rev 1 to FC06313, USI A-46/IPEEE,Outlier Resolution & Detailed HCLPF for Tanks AC-1C & AC-10 ML20217H6471997-07-0202 July 1997 Rev 1 to FC06314, USI A-46 Outlier Resolution for Heat Exchanger CH-7 ML20093D2981995-08-15015 August 1995 Rev 3 to Calculation, Operating Temp Limits for DG-1 & DG-2 ML20093F9321995-06-30030 June 1995 OPPD Fort Calhoun Station Decommissioning External Trust Fund Financial Statements & Independent Auditors Rept, for Period of 940701-950630 ML20117C0501994-12-12012 December 1994 USI A-46 Outlier Resolution for Heat Exchanger CH-7 ML20117C0061994-10-31031 October 1994 USI A-46/IPEEE,Outlier Resolution & Detailed HCLPF for Tanks AC-1C & AC-1D ML20116N1141992-11-0909 November 1992 Rev C to Calculation FC-05916, Operating Temp Limits for DG-1 & DG-2 ML20117C0961992-09-28028 September 1992 Seismic Qualification of Diesel Fuel Tanks & Summary of Calculation for Blockwall No 9 ML20099H7531992-08-10010 August 1992 Rev B to Fc 05916, Operating Temperature Limits for DG-1 and DG-2 ML20155J3251992-06-12012 June 1992 ABB-CE Evaluation of CSP NPSH Accounting for Sump Subcooling ML20104A8391992-05-31031 May 1992 Calculation Fc 05428, Safety Injection Valves SI-207/SI-208 Full Open Stroke Data Analysis for SP-SI-7 Apr 1990 Performance ML20079N3371991-11-11011 November 1991 Response to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20094N4511991-09-17017 September 1991 RCS MOVs HCV-150/151 ML20082P5231991-09-0404 September 1991 OPPD Fort Calhoun Station Decommissioning External Trust Fund Financial Statements & Independent Auditor Rept for 900702-910630 ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20236D2291989-03-15015 March 1989 Limiting River Water Temp Vs Raw Water Flow Requirements ML20147B3361988-02-26026 February 1988 Submits Facility Related Info Re Personnel Conduct & Emergency Support Organization Phone List IA-87-498, Submits Facility Related Info Re Personnel Conduct & Emergency Support Organization Phone List1988-02-26026 February 1988 Submits Facility Related Info Re Personnel Conduct & Emergency Support Organization Phone List ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20135H3531984-06-19019 June 1984 Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2 ML19321A5301980-07-0909 July 1980 Photographs of Containment Recirculation Piping Check Valve, SI-159 Following Removal from Sys for Insp ML19323F4611980-05-0707 May 1980 Slide Presentation Entitled, Reactor Vessel Asymmetric Pressure Loads, from 800507 Meeting W/Util 05000285/LER-1976-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve1976-10-0404 October 1976 Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve 05000285/LER-1976-030, Summary of 760902 Telcon on LER 76-30/01L Re Steam Generator Blowdown Radiation Monitor Setpoints Out of Spec.Caused by Use of Unofficial & Incorrect Document as Part of 760804 Surveillance Test1976-09-0202 September 1976 Summary of 760902 Telcon on LER 76-30/01L Re Steam Generator Blowdown Radiation Monitor Setpoints Out of Spec.Caused by Use of Unofficial & Incorrect Document as Part of 760804 Surveillance Test 1997-07-02
[Table view] Category:TELEPHONE OR VERBAL CONVERSATION RECORD
[Table view] |
LER-2076-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve |
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2852076032R00 - NRC Website |
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f* Le ORECORD OF TELEPHONE C ] MUNICATION FC-1127-76 J
DATE: October h, 1976 TIME: 1700 PARTY CALLING: Bill Dermyer OPPD (Name) (Company)
PARTY ANSWERING: Bill Seidle NRC-OIE Region IV (Name) (Company) ' '
SUBJECT:
LER 50_285/76-32 TELECON
SUMMARY
(Including Decisions and Commitments)
.t After the reactor was shutdown for the 1976 refueling outage and during a containment inspection, reactor coolant was observed to be -
spraying from a weld area on the seal leakoff line on Reactor Coolant Pump RC-30. Leak rate could not be determined; however, it is estimated to be less than 0.2 gpm. After the reactor coolant system was cooled to cold shutdown, the leakage was isolated by a manual isolation valve.
This incident is similar to LER 50-285/75-26, however, the leak rate was much smaller. No increase in containment activity or dev point was indi-cated, nor was leakage indicated by a leak rate calculation. This is considered an " abnormal degradation of one of the several boundaries which are designed to contain radioactive materials "
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//tpFcsetC ACTION REQUIRED Prepare LER - R. Andrews .
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05000285/LER-1976-005, Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed | Suppl 1 to LER 76-05/03L:on 770210,recirculation Actuation Pressure Switches Found Out of Tolerance.Cause Not Stated. Switch Will Be Calibr Monthly Until New Switches Installed | | 05000285/LER-1976-010, Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily | Suppl to LER 76-10/03L:on 760401,high Power Margin to Trip Meter B Drifted from 4.2% to 6% Power.Caused by Drift of Feed Back Limiter Module 19-317-2X.Module Calibr & Operated Satisfactorily | | 05000285/LER-1976-019, Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage | Suppl 1 to LER 76-19/03L:on 761001,five of 10 Valve Setpoints Drifted from Tech Spec Tolerance of Plus or Minus 1%.Caused by Change in Environ Condition.Valves Will Be Inspected During Refueling Outage | | 05000285/LER-1976-021, Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received | Suppl 1 to LER 76-21/03L:on 760802,timer Relays for SI-3A, AC-3B & SI-3B Failed to Time Out at Set Times.Caused by Binding Operating Mechanisms.Timers Tested Twice Weekly to Verify Operability Until Replacements Received | | 05000285/LER-1976-030, Summary of 760902 Telcon on LER 76-30/01L Re Steam Generator Blowdown Radiation Monitor Setpoints Out of Spec.Caused by Use of Unofficial & Incorrect Document as Part of 760804 Surveillance Test | Summary of 760902 Telcon on LER 76-30/01L Re Steam Generator Blowdown Radiation Monitor Setpoints Out of Spec.Caused by Use of Unofficial & Incorrect Document as Part of 760804 Surveillance Test | | 05000285/LER-1976-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve | Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve | |
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