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| =Text= | | =Text= |
| {{#Wiki_filter:' | | {{#Wiki_filter:r =% |
| r =% -- | | GPU Nuclear Y O ?,Y Q |
| GPU Nuclear Y O ?,Y w-a,$ i Q &&( U EC' AO~ | | &&( |
| : f. A:c..e ::e y .sy. .y.g c.p | | : f. A:c..e ::e y.sy..y.g U EC' AO~ |
| '*7 944 762:
| | w-a,$ |
| Wnte s Onect Diat Nruer 717-H. E- S002 re bruary 11, 1951 3200-y3-059 | | i c.p |
| ' r. Monald C. F.ayner. , Recional .id::inistrator Office of Ins;'arrien and .;f o rce rent
| | '*7 944 762: |
| : Mien . | | Wnte s Onect Diat Nruer 717-H. E-S002 r bruary 11, 1951 3200-y3-059 e |
| N*:21 ear t..c ;nter" ..'- . i = : c - | | ' r. Monald C. F.ayner., Recional.id::inistrator Office of Ins;'arrien and |
| b.il Fu rk Aver.uc Ung of Prusuia, PA 19 'es Lthj ec t : Licensee Event F.epo r t W. 53-003 Octr Mr. !!avnes : | | .;f o rce rent |
| i.e : .yw rating Licencoe DPR-50 Da n.e t 50 *'P9 This telecerv is to .enfirn L: e c.nversatien between Mr. F. Youne , Rc;;1on 1 NRC | | : Mien. |
| .nv '!r M. . Nelson, Suocrviser '. nit i Eeview Prograt., ril-1. at 1115 hours en Fecrt.ary 1 , 1933. 2he event dem.:ti' rec below van declared reportable at 1100 hours.
| | N*:21 ear t..c |
| At 1500 hours en 2''.O.'C'. ini M -1 disasse. bit and inspection of the Power Operated Erlicf valve O'C- P.Y 2 ) .:as cc 7 e: vel. This inspection was beinP nerformed to con- | | ;nter"..'-. i = : c - |
| -ir ths; the corresion reptr:ed ic the FRC by LER ':c. 82-011 on''an earlier nodel of this valve was n0 recurring in "!T-l's Extended cold shutdown environment. Th.15 i t: spec tie:: has ider:tified .ha . cerrosten has occurred in the incencl and cartentd tic r,asi aarts in the .rresently :nstalled valve. Furtherr. ore, althounh the main vc.1vc tisc was found ir, thu cold pnsitinn, the pilet valve piston and sorint were fcund ccrroded in the full coen nosition. Tne corroded condition of this valve is considered to require renedial action er corrective measures te prevent potential r..alfunction of
| | b.il Fu rk Aver.uc Ung of Prusuia, PA 19 'es Lthj ec t : |
| 'Lis valve, and ix .onsidered in he reportable within 24 hours in accordance .with
| | Licensee Event F.epo r t W. |
| ~e::hnical Spec i f i er.t ien 6. 9. 2.i . 9. Ihis was determined to be repertable nt 1100 hours or February 11, 198 3 by T"T-1 Pl n r.t Review r;roup.
| | 53-003 Octr Mr. !!avnes : |
| | i.e : |
| | .yw rating Licencoe DPR-50 Da n.e t 50 *'P9 This telecerv is to.enfirn L: e c.nversatien between Mr. |
| | F. Youne, Rc;;1on 1 NRC |
| | .nv '!r M. |
| | . Nelson, Suocrviser '. nit i Eeview Prograt., ril-1. at 1115 hours en Fecrt.ary 1, 1933. |
| | 2he event dem.:ti' rec below van declared reportable at 1100 hours. |
| | At 1500 hours en 2''.O.'C'. |
| | ini M -1 disasse. bit and inspection of the Power Operated Erlicf valve O'C-P.Y 2 ).:as cc 7 e: vel. |
| | This inspection was beinP nerformed to con- |
| | -ir ths; the corresion reptr:ed ic the FRC by LER ':c. 82-011 on''an earlier nodel of this valve was n0 recurring in "!T-l's Extended cold shutdown environment. |
| | Th.15 i t: spec tie:: has ider:tified.ha. cerrosten has occurred in the incencl and cartentd tic r,asi aarts in the.rresently :nstalled valve. |
| | Furtherr. ore, althounh the main vc.1vc tisc was found ir, thu cold pnsitinn, the pilet valve piston and sorint were fcund ccrroded in the full coen nosition. |
| | Tne corroded condition of this valve is considered to require renedial action er corrective measures te prevent potential r..alfunction of |
| | 'Lis valve, and ix |
| | .onsidered in he reportable within 24 hours in accordance.with |
| | ~e::hnical Spec i f i er.t ien 6. 9. 2.i. 9. |
| | Ihis was determined to be repertable nt 1100 hours or February 11, 198 3 by T"T-1 Pl n r.t Review r;roup. |
| Faliure analysis of the ccrreded parts is beint. intiated to dercrmine the cause and atprepriate corrective actions necessnry tc assure future valve onerabilitv. | | Faliure analysis of the ccrreded parts is beint. intiated to dercrmine the cause and atprepriate corrective actions necessnry tc assure future valve onerabilitv. |
| Tree details of this occurrence and the ccrrective actions to prevent its recurrence vili 'ce provided within l' day?t. | | Tree details of this occurrence and the ccrrective actions to prevent its recurrence vili 'ce provided within l' day?t. |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20202F2341986-07-0303 July 1986
Ro:On 860621,canister Seal Installation Tool Removed from Reactor Vessel Following Seal Installation on Defueling Canister D200.Radiological Survey Not Performed Prior to Storage.Caused by Task Supervisor Failure to Require Survey
ML20133C4691985-09-16016 September 1985
Ro:On 850821,make-up Auto Power Failure Resulted in Partial Loss of Instrumentation & Control sys/non-nuclear Instrumentation Power.Caused by Shortage Due to Worn Insulation on Coiled Connector Cable.Cable Replaced
ML20083F1451983-12-14014 December 1983
RO 83-046:on 831213,review of Cable Separation for Makeup Pump Low Lube Oil Pressure Trip Circuit Revealed That Cables for Makeup Pumps a & C Improperly Separated & Circuits Improperly Classified
ML20082H1041983-11-15015 November 1983
RO 83-044:on 831114,AE Site Walkdown Revealed Redundant Circuits in Emergency Feedwater Auto Initiation Circuitry Found Installed/Routed in Same Cable Bundle.Cables Will Be Separated in Jan 1984
ML20082A8721983-11-0808 November 1983
RO 83-043:on 831106,motor Driven Emergency Feedwater Pump EF-P-2A Found Inoperable for Greater than 48 H W/Rcs at Greater than 250 F.Cause Under Investigation
ML20081M7731983-10-25025 October 1983
RO 83-040:on 831014,radiation Monitor RM-L-12 Not Installed on Industrial Waste Filter Sys Common Discharge Per Tech Specs,Due to Failure to Receive Amend 88 to License DPR-50, Changing Tech Specs.Public Safety Maintained
ML20082K9621983-10-19019 October 1983
RO 83-039:on 831018,after Hays Gas Analyzer Removed from Svc to Perform Calibr,Waste Gas Sys Vent Header Not Sampled for 6.5 H.Cause & Corrective Action Will Be Described in Followup Rept
ML20078N4031983-10-0303 October 1983
RO 83-032:both Thermal & Seismic Stress on Instrument Tubes Reevaluated as Followup to Internal Matl Nonconformance Rept.Operability Stresses Below ASME III Criteria Revealed
ML20080P6041983-10-0303 October 1983
RO 83-032:on 830930,thermal & Seismic Stress Criteria on Instrument Tubes Not Met.Fatigue Characteristics Revealed Allowable Number of Cycles Exceeds Actual Number of Heatup & Cooldown Cycles Experienced
ML20080J2651983-09-21021 September 1983
RO 83-028:on 830920,manual Inside Containment Isolation Valve (IA-V20) in Instrument Air Penetration to Reactor Bldg Found Open.Caused by Stem Bushing in Valve Yoke Backed Out of yoke.IA-V20 Valve Bonnet Replaced
ML20078A6011983-09-19019 September 1983
Ro:On 830916,containment Isolation Valve Found Open While Containment Integrity Required.Cause of Incident & Corrective Actions to Prevent Recurrence to Be Described in 14-day Followup Rept
ML20080T0331983-09-19019 September 1983
RO 83-25:on 830916,containment Isolation Valve Found Open While Containment Integrity Required.No Threat to Health & Safety Since Second Boundary Remained Closed.Cause & Corrective Actions Expected in 14-day Followup Rept
ML20080T0361983-09-19019 September 1983
RO 83-26:on 830917-18,all Main Steam Safety Valves Tested. All But One Valve Lifted Above Allowed Lift Point Tolerance of +1% of Setpoint.Caused by Using Incorrect Main Steam Header
ML20085H6031983-08-29029 August 1983
Ro:On 830827,high Deuterium Alarm in Waste Gas Hold Up Sys Received.Caused by Leakage from Makeup Tank Gas Space Into Vent Header Due to Incorrect Valve Lineup
ML20069L3761983-04-18018 April 1983
RO 83-11:on 830326,decay Heat Pump 1A Shaft Bearings Failed,Rendering Pump Inoperable.Caused by Incorrect Design Change to Pump Bearing Lube Oil Sys.Lubrication Sys for Pumps 1A & 1B Returned to Original Configuration
ML20073R0881983-04-18018 April 1983
RO 83-11:on 830326,DHR 1A Shaft Bearings Failed,Making Pump Inoperable.Caused by Design Change to Pump Bearing Lube Oil Sys.Sys Returned to Original Configuration.Review of Existing Sys in Progress
ML20069L5481983-03-31031 March 1983
RO 83-008:on 830329,oxygen Concentration in Miscellaneous Waste Storage Tank Gas Space Exceeded Tech Specs.Nitrogen Used to Purge Oxygen from Sys & Oxygen Concentration Reduced within Limits
ML20072Q5861983-03-22022 March 1983
Telecopy RO 83-005:on 830321,high Oxygen Content Found in Waste Gas Sys.Caused by Recent Maint Activities.Addl Hydrogen/Oxygen Monitor Scheduled for Installation Prior to Restart
ML20070W0821983-02-11011 February 1983
Telecopy of RO 83-003:on 830210,initial Disassembly & Insp of PORV RC-RV2 Revealed Pilot Valve Piston & Spring Corroded in Full Open Position.Failure Analysis Initiated to Determine Cause & Corrective Actions
ML20065B5651983-02-11011 February 1983
Telecopy RO 83-003:on 830210,during Insp of PORV RC-RV2, Corrosion Identified in Inconel & Austenitic Steel Parts. Pilot Valve Piston & Spring Also Found Corroded.Cause Under Analysis
ML20064N9211982-09-0303 September 1982
RO 82-012:on 820902,Tech Spec Re Limiting Condition for Operation Was Not Met for Station Effluent Line Monitor Setpoints RML-7.Caused by Setpoints Not Being Set Per Offsite Dose Calculation manual.RML-7 Setpoints Reset
ML20054G5881982-06-0404 June 1982
RO 82-20:on 820603,determined That Recent Overflow of Auxiliary Bldg Sump Occurred Due to Influx of Rainwater from Borated Water Storage Tank Recirculation Pump Encl Sump. Caused by Deficient Administrative & Design Controls
ML20053C9711982-05-11011 May 1982
RO 82-007:on 820509,oxygen Concentration Exceeded Tech Specs Limit of 2% After Reactor Coolant Bleed Tank Was Returned to Svc After Maint.Nitrogen Purge Initiated on Tank to Reduce Oxygen.Erroneously Numbered
ML20079F8491982-05-11011 May 1982
RO 82-008:on 820408 & 0509,oxygen Concentration Exceeded Tech Spec Limit After C Reactor Coolant Bleed Tank Returned to Svc Following Maint.Tech Spec Will Be Revised to Take Maint Effects Into Account
ML20050D5331982-04-0202 April 1982
RO 82-011/01L-0:on 820303,re Potential Bypass Path of Several Ventilation Sys Filtration Units.Followup Rept Will Be Submitted by 820406
ML20050A5431982-03-18018 March 1982
Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank
ML20126L5161981-05-11011 May 1981
RO 81-13/1P:on 810508,incore Thermocouple L-11 Failed. Thirty-two Thermocouples Remain Operable
ML20126J8521981-04-21021 April 1981
RO 81-10/1P:on 810420,discovered Failure to Meet Requirements of Shift & Daily Checks Surveillance Procedures for post-accident Instrumentation & Radiation Monitoring Instrumentation.Addl Info Will Be Provided
ML20049A3761980-12-15015 December 1980
RO 80-56/1P:on 801212,determined That Core Flood Tank a Had Failed.Cause Not Stated.Details Will Be Included in Followup Rept
ML20062K0701980-11-17017 November 1980
RO 80-53/1P:on 801108,incore Thermocouples N-3 & N-9 Determined to Be Failed
ML20062K0691980-11-17017 November 1980
RO 80-52/1P:on 801113 Following Leak Test of Personnel Airlock 2,inner Door Leak Rate Test Failed to Meet Required Tech Spec Limit.Door Could Not Be Returned to Svc within 24-h Required Limit
ML20062K0531980-10-28028 October 1980
RO 80-48/1P:on 801027,four Relief Valves W/Unauthorized ASME UV Code Symbol Stamp Discovered.Followup Action Being Initiated
ML20062J4281980-10-20020 October 1980
RO 80-410:determined That Replacement Coils Being Installed in Response to IE Bulletin 79-01A Have a Range Lower than Station Battery Voltage Range.Coils Could Potentially Fail If Maintained at Voltages Above Normal Operating Range
ML20126B4771980-02-11011 February 1980
RO 80-03/1P:makeup Pump Discharge Check Valves MU-V-734A/C Found W/Damages Locking Devices on Valve Seat Holddown Bolts.Cause Unstated.Matls Analysis on Failed safety-related Crane Tilting Disc Check Valves Being Conducted
ML20062E6271978-12-0505 December 1978
RO 78-31/4P:river Water Temp Change Exceeded Tech Spec Limits.Caused by Low Inlet Temp & High Ambient Temp & Relative Humidity,Resulting in Inability of Mechanical Draft Cooling Towers to Cool Discharge Water Properly
ML20085A5011975-06-27027 June 1975
Ro:On 750613,power Relief Valve Actuated at 2,257 Psig & Failed to Close,Resulting in Rupture of Quench Tank Rupture Disc & Violation of Fuel Compression Curve & Cooldown Rates. Caused by Incorrectly Positioned Pilot Valve Lever
ML20244A8031975-04-0909 April 1975
Nonroutine 30-Day Rept 75-04:deficiency Found in Scope of Analysis Utilized in Deriving Power Vs Rod Withdrawal Limits Per Tech Spec Figures-3.5-2a,2b & 2c.Mgt Review Underway
1986-07-03
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1001999-10-14014 October 1999
Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage
ML20217K4701999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for TMI-1.With
ML20216F9231999-09-22022 September 1999
Safety Evaluation Supporting Amend 216 to License DPR-50
05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With
ML20211Q3551999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With
ML20211H5111999-08-31031 August 1999
Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis
ML20211E8731999-08-24024 August 1999
Safety Evaluation Supporting Amend 215 to License DPR-50
ML20211B1931999-08-19019 August 1999
Safety Evaluation Supporting Amend 214 to License DPR-50
ML20210R4791999-08-13013 August 1999
Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2
ML20210U4791999-07-31031 July 1999
Monthly Operating Rept for July 1999 for TMI-1.With
05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
ML20210K7651999-07-0909 July 1999
Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca
ML20209G0011999-07-0909 July 1999
Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1
ML20209H8251999-07-0101 July 1999
Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station
ML20209H1421999-06-30030 June 1999
Monthly Operating Rept for June 1999 for TMI-1.With
ML20212H9101999-06-21021 June 1999
Safety Evaluation Supporting Amend 212 to License DPR-50
05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With
ML20195H0751999-06-0808 June 1999
Drill 9904, 1999 Biennial Exercise for Three Mile Island
ML20209G0351999-05-31031 May 1999
TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo)
ML20195H9261999-05-31031 May 1999
Monthly Operating Rept for May 1999 for TMI-1.With
ML20207B6621999-05-27027 May 1999
SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05
05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
ML20206R0571999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With
ML20206D4201999-04-20020 April 1999
Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2
ML20205Q6111999-04-15015 April 1999
Safety Evaluation Supporting Amend 210 to License DPR-50
ML20205Q5981999-04-13013 April 1999
Safety Evaluation Supporting Amend 209 to License DPR-50
ML20206P2841999-04-12012 April 1999
SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90
ML20209G0071999-03-31031 March 1999
Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion)
ML20205K6851999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With
05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With
ML20210C0161999-03-0101 March 1999
Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246
ML20207M8461999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for TMI-1.With
05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
ML20196K3561999-01-22022 January 1999
Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits
05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20196G4661998-12-31031 December 1998
British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl
ML20207A9291998-12-31031 December 1998
1998 Annual Rept for TMI-1 & TMI-2
ML20196F6861998-12-0202 December 1998
Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection
ML20198B8641998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for TMI-1.With
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20195C6921998-11-12012 November 1998
Safety Evaluation Supporting Amend 52 to License DPR-73
ML20196B7191998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for TMI-1.With
ML20203G1211998-10-30030 October 1998
Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt
05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
ML20155E7511998-10-15015 October 1998
Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing
05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for TMI Unit 1.With
05000289/LER-1998-011, :on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge1998-09-23023 September 1998
- on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge
05000289/LER-1998-009-01, :on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised1998-09-18018 September 1998
- on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised
1999-09-30
[Table view] |
Text
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GPU Nuclear Y O ?,Y Q
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'*7 944 762:
Wnte s Onect Diat Nruer 717-H. E-S002 r bruary 11, 1951 3200-y3-059 e
' r. Monald C. F.ayner., Recional.id::inistrator Office of Ins;'arrien and
.;f o rce rent
- Mien.
N*:21 ear t..c
- nter"..'-. i =
- c -
b.il Fu rk Aver.uc Ung of Prusuia, PA 19 'es Lthj ec t :
Licensee Event F.epo r t W.53-003 Octr Mr. !!avnes :
i.e :
.yw rating Licencoe DPR-50 Da n.e t 50 *'P9 This telecerv is to.enfirn L: e c.nversatien between Mr.
F. Youne, Rc;;1on 1 NRC
.nv '!r M.
. Nelson, Suocrviser '. nit i Eeview Prograt., ril-1. at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> en Fecrt.ary 1, 1933.
2he event dem.:ti' rec below van declared reportable at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />.
At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> en 2.O.'C'.
ini M -1 disasse. bit and inspection of the Power Operated Erlicf valve O'C-P.Y 2 ).:as cc 7 e: vel.
This inspection was beinP nerformed to con-
-ir ths; the corresion reptr:ed ic the FRC by LER ':c.82-011 onan earlier nodel of this valve was n0 recurring in "!T-l's Extended cold shutdown environment.
Th.15 i t: spec tie:: has ider:tified.ha. cerrosten has occurred in the incencl and cartentd tic r,asi aarts in the.rresently :nstalled valve.
Furtherr. ore, althounh the main vc.1vc tisc was found ir, thu cold pnsitinn, the pilet valve piston and sorint were fcund ccrroded in the full coen nosition.
Tne corroded condition of this valve is considered to require renedial action er corrective measures te prevent potential r..alfunction of
'Lis valve, and ix
.onsidered in he reportable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance.with
~e::hnical Spec i f i er.t ien 6. 9. 2.i. 9.
Ihis was determined to be repertable nt 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> or February 11, 198 3 by T"T-1 Pl n r.t Review r;roup.
Faliure analysis of the ccrreded parts is beint. intiated to dercrmine the cause and atprepriate corrective actions necessnry tc assure future valve onerabilitv.
Tree details of this occurrence and the ccrrective actions to prevent its recurrence vili 'ce provided within l' day?t.
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