LER#78-026/03L-1 on 780830:Bchannel RPS Variable Overpwr Trip Reset Demand Alarm Actuated & Would Not Reset.Then,Hi Pwr & Thermal Margin/Low Pressure Trip Units Failed,Both Due to Failure of Devar19-601A,18volt Pwr Supply| ML20071F488 |
| Person / Time |
|---|
| Site: |
Fort Calhoun  |
|---|
| Issue date: |
09/15/1978 |
|---|
| From: |
Connolley J, Gordon Peterson
OMAHA PUBLIC POWER DISTRICT |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20071F480 |
List: |
|---|
| References |
|---|
| LER-78-026-03L, LER-78-26-3L, NUDOCS 7810110117 |
| Download: ML20071F488 (3) |
|
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1998-003, Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted1998-06-23023 June 1998
Re Individual Leaving High Radiation Area (HRA) Door Unlocked & Uncontrolled While in Hra. LER 98-003-00 Retracted
05000285/LER-1990-0071990-08-0101 August 1990
LER 90-007-02:on 900228,determined That Main Feedwater & Main Steam Piping Outside Design Basis.Caused by Design Deficiency & Failure of Engineer to Consider Loads Induced on Piping.Piping Supports modified.W/900801 Ltr
05000285/LER-1990-0101990-07-0303 July 1990
LER 90-010-01:on 900327,unplanned Attempted Start of Emergency Diesel Generator Occurred While Plant in Refueling Shutdown.Caused by Low Air Pressure in Diesel Start Sys. Instructions Re auto-start Signals changed.W/900703 Ltr
ML20071G3271978-12-22022 December 1978
/03L-0 on 781124:during Shutdown Cooling Interlock Test Noted That PC-105B Was Not Operating.Caused by Valve Closing Relay 94-347/348 Not Being Wired to PC-105B; Inadvertently Disconnected in 1977
ML20071G2671978-12-22022 December 1978
/03L-0 on 781204:during Inspec of Discharged Fuel Assemblies,A Single Fuel Pin Was Observed to Have Failed, Assoc W/Manufacture & Exposure of Present Day Nuc Fuel
ML20071G2381978-12-21021 December 1978
/03X-1 on 780918:during Refueling Outage,D Channel Hot Leg Temp Indication Was Investigated to Determine Cause of 780918 Failure.Failure Caused by Rosemount Model 104VC RTD Having Water in the Pothead
ML20071G2201978-12-20020 December 1978
/03L-0 on 781122:noted That Level Transmiter for C Channel (C/LT-901) for Steam Generator RC-2A Level Instrumentation Not W/In Specs.Caused by Calibr Drift of Ge/Mac Model 555 Transmitter
ML20071G2791978-12-19019 December 1978
/03L-0 on 781214:during 1978 Refueling Outage, Certain Surveillance Tests Req by Tech Specs Could Not Be Performed Because of Shutdown Condition.Facil Lic Change 77-11 Submitted to NRC on 781109 to Delete Requirements
ML20071G0701978-12-12012 December 1978
/03L-0 on 781113:during Test of Ventilation Isolation Actuation Signal,Lockout 86B1/VIAS Did Not Trip. Cause Unidentified,Since Relay Retested & Found to Be Operating Normally.Relays Will Continue to Be Tested
ML20071G0851978-12-0808 December 1978
/01T-0 on 781127:Diesel Generator 2 Failed to Auto Close Onto the Bus;Breaker Mode Switch Contracts 27-27c Failed to Make Contact.Caused by Contact Failure
ML20071G1011978-12-0505 December 1978
/03L-0 on 781116:during Refueling,All Limitorque Valves Were Inspec for Proper Staking of the Lock Nut on the Motor operator.30 of 65 Valves Exhibited Unstaked Lock Nuts.Lock Nuts Were Staked IAW Manufacturer'S Instructions
ML20071F9281978-11-27027 November 1978
/03L-0 on 781101:auxiliary Feedwater Check Valve FW-164 Found to Be Oriented in Wrong Position.Caused by Missing Valve Disk Plate Which Was Subsequently Located & Recovered
ML20071F9061978-11-25025 November 1978
/03L-0 on 781026:repeated Tripping of Stack Particulate Process Monitor.Caused by Trip Set in Accordance W/Tech Specs Table 2-1 at 9.6x10-2,rather than More Conservative Release Rates 2x10-3
ML20071F8541978-11-0202 November 1978
/03L-0 on 781014:Reactor Coolant Cold Leg Temp Indicator B/122C Failed High Off Scale Because of an Open Circuited Rosemount Model 104VC Rtd.The RTD Will Be Replaced During Present Refueling Outage
ML20071F4821978-10-0606 October 1978
/03L-0 on 780908:Inadvertent Radioactive Gas Release to Atmosphere Caused by Leakage Past Check Valve CH-284,HG-100 & Relief Valve HG-105.Valves Will Be Inspected & Replaced or Repaired During Next Refueling Outage
ML20147B1901978-10-0303 October 1978
/01T-0 on 781003:During Oper Check on Auxiliary Steam Driven Feed Pump,The Steam Inlet Valve YCV-1045 Did Not Open Due to Closed Air Supply
ML20071F4671978-09-27027 September 1978
/03L-0 on 780831:failure of Tri-x Weather Tower'S 100 Meter Delta-T Sensor Sys to Rept Stability Class Info. Calibrations Revised to Ensure Instruments Detect Subsequent Sensor Sys Failures
ML20071F4881978-09-15015 September 1978
/03L-1 on 780830:Bchannel RPS Variable Overpwr Trip Reset Demand Alarm Actuated & Would Not Reset.Then,Hi Pwr & Thermal Margin/Low Pressure Trip Units Failed,Both Due to Failure of Devar19-601A,18volt Pwr Supply
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 Installed1977-02-10010 February 1977
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-1976-019, 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 Outage1976-10-14014 October 1976
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 Received1976-08-0909 August 1976
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-1976-010, 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 Satisfactorily1976-04-0808 April 1976
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
1998-06-23
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999
Safety Evaluation Supporting Amend 193 to License DPR-40
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With
ML20211J9321999-09-0202 September 1999
Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1
LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With
ML20216E6431999-08-26026 August 1999
Rev 19 to TDB-VI, COLR for FCS Unit 1
ML20210R1961999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Fcs,Unit 1
ML20210G2181999-07-27027 July 1999
Safety Evaluation Supporting Amend 192 to License DPR-40
ML20210D9951999-07-22022 July 1999
Safety Evaluation Supporting Amend 191 to License DPR-40
ML20216E6361999-07-21021 July 1999
Rev 18 to TDB-VI, COLR for FCS Unit 1
ML20210R2081999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1
LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20210P5461999-06-0808 June 1999
Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included
ML20195B4581999-05-31031 May 1999
Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts
ML20207H7401999-05-31031 May 1999
Performance Indicators Rept for May 1999
LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1
ML20195B4521999-05-17017 May 1999
Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr)
ML20206L4241999-05-10010 May 1999
Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07
ML20206M2601999-05-0606 May 1999
SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History
LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With
ML20195E8621999-04-30030 April 1999
Performance Indicators, for Apr 1999
ML20205Q5831999-04-15015 April 1999
Safety Evaluation Supporting Amend 190 to License DPR-40
ML20210J4331999-03-31031 March 1999
Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59
ML20206G2641999-03-31031 March 1999
Performance Indicators Rept for Mar 1999
LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With
ML20205J8181999-02-28028 February 1999
Performance Indicators, for Feb 1999
LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With
ML20207F3291999-01-31031 January 1999
FCS Performance Indicators for Jan 1999
ML20203B0991998-12-31031 December 1998
Performance Indicators for Dec 1998
LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998
1998 Omaha Public Power District Annual Rept. with
LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With
ML20198S3771998-12-31031 December 1998
Safety Evaluation Supporting Amend 189 to License DPR-40
ML20198S4831998-12-31031 December 1998
Safety Evaluation Supporting Amend 188 to License DPR-40
ML20196G2251998-12-18018 December 1998
Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment
ML20198M3141998-11-30030 November 1998
Performance Indicators Rept for Nov 1998
LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With
LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998
Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated
ML20203B0721998-11-16016 November 1998
Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion
ML20196E4981998-10-31031 October 1998
Performance Indicators Rept for Oct 1998
ML20196G2441998-10-31031 October 1998
Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59
LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With
ML20154M4881998-10-19019 October 1998
Safety Evaluation Supporting Amend 186 to License DPR-40
ML20154N2411998-10-19019 October 1998
Safety Evaluation Supporting Amend 187 to License DPR-40
LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With
ML20155G4261998-09-30030 September 1998
Performance Indicators for Sept 1998
ML20154A1251998-08-31031 August 1998
Performance Indicators, Rept for Aug 1998
LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With
ML20238F7231998-08-17017 August 1998
Owner'S Rept for Isis
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
1999-09-30
[Table view] |
Text
- - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
17 77) .
LICENSEE EVENT REPORT CONTROL BLOCX: l 1
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(PLEASE PRINT 02 TYPE ALL REQUIRED INPORMATl!NI IoIillNlIIFlCISI1l@l010l0IOIOl010 14 15 UCENSE NUMBER 1010l0IOl@lklilil11il@l JS 26 UCENSE Typt 40 51 CAT 68 I
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7 4 9 UCENSEE CCCE CON'T 10111 g i L l@l o l 5 l o l o 10121815 l@l 68 o 1813101718 69 EVENT QATE l@l 0) o!REPORT 74 75 11 DATE 917181@ 83 7 6 60 61 DOCKET NypSER EVENT CESCRIPTION AND PRO 8 A8LE CONSEQUENCES h IC i: 1 I Dring ne ._al steadv state rever eneration. "B" chrnel reaeter tretectiv. . rme.- Ince1 l0i3i I variable overpcVer trip reset da-and alarm actuated and vould not reset. eh e-+ 1-r !
Io64l l after this alarm came in, the Hi pcver and the: nal =arrin/ lev cressu e trie u .its fer I
,oi5i i"3" cha'nel PSS failed to the tripped condition. The three remaining ??S channels 1 J 66 l l remain *d Operable throughout this event. See LER 78-026 Revisien 0. I 1017 l 1 I
l o . f_] l do 7 s9 COMP. VALVE SYSTEM CAUSE CAUSE CODE CCDE SUSCODE COMPONENT CODE SUSCCOE SLSCOCE 10691 7 8 III A l@ IIl@ lo l@ l Il nl Si Tl al ul@ IP l@ 12 l@
9 10 '
12 13 18 19 20 SEQUENTI AL CCOUR R ENCE REPORT REVISION EVENT YE AR REPORT NO. COCE TvPL NO.
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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
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t i 101 lSe tevar Model 19-601A.18 velt tovar sur:1v w s the c0 renert irich " m =4.
,ii1 ; l believed to have been an intermittent failure =f this pever surelv vhich resu1*ad 1- 1
{ g gthe failure of two a=plitude selector =edules (see LIR 73-026 Revisic: 0) as the ;cverI i, ,3l l supply cutput was noted to be as high as 27 volts while troubleshooting this failure. !
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- . POWER OTMER STATVS OtSCOV E R Y D'SCOVERY OESCRIPT:CN STATLS lAl@l46 overator Cbse vation 1 isist121@ l01of91@l 7 g 9 to 1: 11 NA 44 l
45 83 ACT1vtTY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LCCATION CF RELEASE -
3A NA i l'l6ll3I I 31 l l 44 45 40 7 4 9 to 11
- ERSONNEL EXPOSU R E S Nuv8ER TYPE OESCRtPTtON l1 hI **
80 8 9 11 12 13
- ERSONNE L INJL AIES NLVSER OESCRIPTION I
11 !a8 l9l o l o l o l@l12 3A 7 11 30 LOSS 08 OR Q AMAGE ?O F ACILITY Tvet 3 E SCRIPTION li191[,j@l 3A 30 I
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l LIR 78-026 Revision 1 Onaha Public Power District Fort Calhcun Station Unit no. 1 Docket No. 05000285 Attachment No. 1 Safety Analysis
'"he reactor protective system (PSS) is so designed that no single failure can prevent the safe shutdown of the plant if required.
During the time the "3" channel RPS for High power and thermal margin / low pressure were considered inoperable, the PSS vas in a 2 cut of 3 logic providing adequate protection of the reactor.
The apparent cause of this failure was a faulty 18 volt power supply. The output of this power supply was noted, at times during this event, to be as high as 27 volts (or approximately 10 volts over rating) which is ample overload to have caused the previous failure of two amplitude selector modules (rated at 18 volts). See LER 78-026 Revision O. Rovever, the higher than rated output voltage of this power supply was not seen during the a=plitude selector module failures of August 21, 1978.
The PSS vill continue to be checked by visual inspection and by surveill-ance testing in an effert to discover and correct future events of this type.
'. !a:
, i .
f ..j
1ER 78-026 Revision 1 Omaha Public Power District -
Fort Oalhoun Station Unit No.1 Docket No. 05000285 Attachment No. 2 Failfre Data See LIR 78-026 Revision O. This is the first reportable event for an 18 volt Devar power supply.
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__ _ _ _ _ .