Abnormal Occurrence 50-289/75-07:on 750317,problems Found W/Connector & Wiring on Engineered Safeguard Motor Control Center Units.Caused by Poor Workmanship During Mfg &/Or Installation.Connections Tightened & Wire ReplacedML19262A247 |
Person / Time |
---|
Site: |
Three Mile Island |
---|
Issue date: |
04/02/1975 |
---|
From: |
Arnold R METROPOLITAN EDISON CO. |
---|
To: |
|
---|
References |
---|
GQL-0893, GQL-893, NUDOCS 7910260583 |
Download: ML19262A247 (7) |
|
|
---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19210A1511976-02-12012 February 1976 Abnormal Occurrence 76-7/1P:on 760212,empty Snubber Fluid Reservoir Found at Location DHH-198.Leakage Due to Damaged Seal.Snubber Removed & Replaced ML19322A4301976-02-0505 February 1976 Abnormal Occurrence 76-6/1P on 760204:radiation Leak Detection Sys Out of Svc for 22-h.No Reactor Bldg Atmospheric Samples Taken.Caused by Cover Plate to Monitor Left Open Following Insp.Procedures Reviewed W/Personnel ML19210A1581975-12-26026 December 1975 Abnormal Occurrence 50-289/75-43:on 751218,one of Six Pressure Switches Tripped at Less Conservative Limits than Tech Specs During Channels Surveillance Test.Caused by Calibr Drift in Associated Pressure Switch PS-290 ML19210A1451975-12-19019 December 1975 Abnormal Occurrence 50-289/75-42:on 751210,outside Containment Isolation Valve for Steam Generator Sample Line CA-V5B Failed to Close.Caused by Valve Manual Operator Inadvertently Left Open by Reactor Personnel ML19210A1731975-11-25025 November 1975 Abnormal Occurrence 50-289/75-40:on 751112,stuck Contacts on Diesel Generator 1A Voltage Relays Threatened Function of Engineered Safety Feature.Caused by Pitting of Relay Contact.Relays Checked at Each Startup Pending Design Mods ML19261F1481975-11-24024 November 1975 Abnormal Occurrence 50-289/75-41:on 751114,personnel Failed to Strictly Follow Drain & Blanketing Procedure.Vented Center Control Rod Drive Mechanism Allowed Radioactive Gas Into Reactor Bldg.Personnel Counseled on Proper Procedures ML19210A1831975-11-21021 November 1975 Abnormal Occurrence 50-289/75-39:on 751112,control Rod 4 in Group 7 Dropped Into Core,Resulting in Asymmetrical Rod Signal & Automatic Power Reduction.Caused by Failure of Stator Winding.Stator Winding Replaced & Tested ML19210A1891975-10-31031 October 1975 Abnormal Occurrence 50-289/75-38:on 751021,control Rod Verification Program Not in Compliance W/Tech Specs.Caused by Procedure Misinterpretation.Revised Surveillance Program Will Clearly State Requirement of Individual Rod Movement ML19210A1911975-10-31031 October 1975 Abnormal Occurrence 50-289/75-37:on 751021,blocked Strainer on Outlet to Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Improper Design Allowing for One Strainer W/No Bypass Caused Blockage ML19210A2021975-10-29029 October 1975 Abnormal Occurrence 50-289/75-36:on 751019,auxiliary Operator Failed to Obtain Radiation Work Permit & Carry Monitoring Device.Caused by Improper Administrative Procedures ML19210A1971975-10-21021 October 1975 Abnormal Occurrence 75-37:on 751021,blocked Strainer on Outlet of Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Plant Returned to Svc in 15 Minutes ML19210A2151975-10-20020 October 1975 Abnormal Occurrence 50-289/75-35:on 751010,improper Mix of Boric Acid Crystals Caused Blockage in Mix Tank.Crystals Settling to Bottom of Tank Clogged Line to Reclaimed Boric Acid Storage Tank.Mixture Mod Should Correct Failures ML19210A2211975-10-10010 October 1975 Abnormal Occurrence 75-37:on 751010,during Transfer of Boric Acid from Storage Tank to Reclaim Tank,Blockage Noticed in Outlet Line.Caused by Boric Acid Crystals Settling to Drain Due to Improper Mixture ML19210A2241975-10-0808 October 1975 Abnormal Occurrence 50-289/75-34:on 750928,inoperative Hydraulic Shock Suppressor Threatened Function of Engineered Safety Feature.Low Fluid Level in Snubber Caused Failure. All Other Snubbers Checked Satisfactorily ML19322A4371975-09-30030 September 1975 Abnormal Occurrence 75-34 Re Disconnected Hydraulic Snubber within Reactor Bldg Secondary Shield.Investigation of Circumstances Incomplete.Snubber Replaced During Ongoing Seal Replacement Program ML19210A2461975-09-26026 September 1975 Abnormal Occurrence 50-289/75-31:on 750917,core Flood Tank Water Level Below Tech Specs Requirements.Caused by Incorrect Reading on Lower Reading Channel CF2-LT3.Channel Will Now Be Monitored & Personnel Informed on Procedures ML19210A2411975-09-26026 September 1975 Abnormal Occurrence 50-289/75-33:on 750917,de-ice Makeup Valve NR-V-4A Failed in Open Position.Failure Caused by High Resistance Contact in Closing Control Circuit Not Fully Energizing.All Control Contacts to Be Checked & Cleaned ML19210A2391975-09-26026 September 1975 Abnormal Occurrence 50-289/75-32:on 750918,incorrect Open Position of Air Supply Valves PP-V-47 & 179 Could Have Prevented Proper Functioning of Door Seals in Event of Emergency Safeguards Actuation.Jj Colitz 750919 Ltr Encl ML19210A2451975-09-19019 September 1975 Abnormal Occurrence 75-33 Re Failure of de-ice Makeup Valve NR-V-4A to Close Using Control Room Remote Pushbutton.Caused by High Resistance Contact in Closing Control Circuit. Contact Cleaned,Tested & Returned to Svc ML19322A4361975-09-18018 September 1975 Abnormal Occurrence 75-31 Re Low Borated Water Level in Core Flood Tank B.Caused by Improper Level Channel Transmitter LT3 Readout.Transmitter Adjusted ML19210A1791975-09-0505 September 1975 Abnormal Occurrence 50-289/75-29:on 750827,reactor Bldg Purge Supply Valve AH-V-1D Failed to Close Prior to Engineered Safeguards Test.Caused by Corroded Robotarm Actuator.Robotarm Actuator Lubricated ML19210A2251975-09-0505 September 1975 Abnormal Occurrence 50-289/75-30:on 750827,valve CF-V-2B of Core Flood Tank B Sample Line Isolation Failed to Close Upon Receipt of Engineered Safeguards Actuation Signal.Caused by Valve Binding Against Valve Stem ML19210A1811975-09-0202 September 1975 Abnormal Occurrence 50-289/75-28:on 750823,MS-V-13A Valve Turbine Drive Emergency Feed Pump Failed to Remain Open. Caused by Control Circuit Pressure Switch Failure,Due Possibly to High Ambient Temp ML19210A1871975-08-29029 August 1975 Abnormal Occurrence 50-289/25-27:on 750821,crack & Leak Found in Auxiliary Makeup Pump a Suction Vent.Caused by Fatigue Due to Vibration.Cracks Repaired & Hydrostatically Tested.Failed Pipe Section Replaced ML19322A4351975-08-28028 August 1975 Abnormal Occurrence 75-30:on 750827,core Flood Tank B Sample Line Isolation Valve CF-V2B Failed to Close Following Engineered Safeguards Signal.Valve Manually Closed Using Handwheel ML19210A1861975-08-27027 August 1975 Abnormal Occurrence 75-29:on 750827,reactor Bldg Supply Valve AH-V-1D Failed to Fully Close.Investigation Into Cause Underway ML19210A1841975-08-23023 August 1975 Abnormal Occurrence 75-28:on 750820,during Test of Turbine Drive Emergency Feed Pump,Associated Valve Failed to Remain Open.Caused by Failed Pressure Switch ML19210A1901975-08-21021 August 1975 Abnormal Occurrence 75-27 on 750821:leaks Found in Socket Weld Joint at Makeup Pump a & Suction Line Connection W/Pump Suction Header.Cause of Problem Under Investigation ML19210A1941975-08-0101 August 1975 Abnormal Occurrence 50-289/75-26:on 750724,high Reactor Coolant Pressure Trip Set Points Less Conservative than Tech Specs.Caused by Calibr Drift.Specs Will Be Changed to Account for Instrument Error ML19210A1951975-07-31031 July 1975 Abnormal Occurrence 50-289/75-25:on 750721,failure of Diesel Generator a Frequency Relay to Actuate,Threatening Nonperformance of Diesel Generator.Cause Presently Unknown ML19210A2001975-07-25025 July 1975 Abnormal Occurrence 50-289/75-23:on 750716,auxiliary Relay to Generator 1B Failed to Energize on Demand.Caused by Mfg Defect.Failed Relay Replaced & Remaining Relays Inspected ML19210A2071975-07-25025 July 1975 Abnormal Occurrence 50-289/75-24:on 750716,during Removal of River Water Pump NR-P1B from Svc,Discharge Valve Failed to Close.Caused by Open Phase on Winding Due to Severe Heat Resulting in Single Phasing of Other Windings ML19210A1991975-07-22022 July 1975 Abnormal Occurrence 75-25:on 750722,three Frequency Relays to Steam Generator a Found in Dropped Out State.Relays Replaced & Returned to Svc.Cause of Failure Yet to Be Determined ML19210A2171975-07-21021 July 1975 Abnormal Occurrence 50-289/75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump Suction Vent Line MU-PIA Leading to Valve MU-V156A.Caused by Improper Spacing Between Moving Anchor & First Pipe Restraint ML19210A2051975-07-18018 July 1975 Abnormal Occurrence 75-23:on 750716,one of Three Auxiliary Relays of Diesel Generator 1B Breaker G11-02 Failed. Remaining Relays Tested Satisfactorily.Cause of Failure Under Investigation ML19210A2121975-07-18018 July 1975 Abnormal Occurrence 75-24:on 750716,river Water Pump Discharge Valve Failed Due to Low Valve Motor Winding Resistance & Winding Motor Overheating ML19210A2221975-07-11011 July 1975 Abnormal Occurrence 75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump a Suction Line Vent.Caused by Pump Vibration ML19210A2311975-07-0303 July 1975 Abnormal Occurrence 50-289/75-21:on 750625,coolant Temp Trip Bistable Channel C Failed to Trip During Test of Reactor Protection Sys.Caused by Defective Printed Circuit Board Solder Joint in Signal Converter ML19210A2371975-06-27027 June 1975 Abnormal Occurrence 50-289/75-19:on 750618,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Caused by Channel C Trip Setpoint Out of Calibr Due to Instrument Drift ML19210A2301975-06-27027 June 1975 Abnormal Occurrence 75-03:on 750626,noble Gas Released to Auxiliary Bldg.Probable Cause:Evaporator Malfunction While Filling Makeup Tank or Coolant Bleed Tank.No Tech Specs Exceeded ML19210A1621975-06-27027 June 1975 Abnormal Occurrence 50-289/75-18:on 750615,QA Documentation from Vendor Found Inadequate for Repaired Decay Heat River Water Pump Motor Shaft.Caused by Lack of Administrative Controls ML19210A2351975-06-25025 June 1975 Abnormal Occurrence 75-21:on 750625,reactor Protection Sys Channel C Failed During Surveillance Test.Caused by Coolant Temp Trip Bistable Failure to Trip Due to Component Failure in Signal Converter ML19210A1721975-06-25025 June 1975 Abnormal Occurrence 50-289/75-17:on 750615,reactor Bldg Purge Isolation Valve Failed Local Leak Rate Test.Caused by Improper Valve Adjustment Procedures & Matl Defects Not Allowing Long Term Retention of Adjustment ML19308A5371975-06-23023 June 1975 Abnormal Occurrence 75-20:on 750622,while Returning to Full Power Operation After Forced Power Reduction,Reactor Power Increased Above Power Level Cutoff Before Xenon Reactivity Approached Stability.Procedures Under Review ML19210A2431975-06-19019 June 1975 Abnormal Occurrence 75-19:on 750618,less Conservative Variable Low Reactor Coolant Sys Pressure Trip Setpoint for One Channel of Reactor Protection Sys Violated Tech Specs. Caused by Instrument Drift for Channel C Setpoint Calibr ML19210A1661975-06-17017 June 1975 Abnormal Occurrence 75-18:on 750615,repaired Motor Shaft to Decay Heat River Water Pump Not Returned W/Proper QA Documentation.Caused by Lack of Administrative Control ML19210A1751975-06-17017 June 1975 Abnormal Occurrence 75-17:on 750615,during Test of Reactor Bldg Purge Isolation Valve Local Leak Rate Test,Two Exhaust Valves Would Not Pressurize to Required Test Pressure.Caused by Valve AH-V1A Failing to Fully Close ML19210A1771975-06-16016 June 1975 Abnormal Occurrence 50-289/75-16:on 750605,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Specific Cause Not Established. Setpoints Will Be Checked to Assure Proper Calibr ML19291B5291975-06-13013 June 1975 Abnormal Occurrence 50-289/75-15:on 750605,pressure Transmitter Trip Setpoint of Reactor Protection Sys Channel B Tested Out of Calibr.Caused by Trip Setpoint Calibr Drift ML19210A1801975-06-0606 June 1975 Abnormal Occurrence 75-16:improper Trip Setpoints on Variable Low Reactor Coolant Sys Pressure Sys Violated Tech Specs 1976-02-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-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 ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With 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 ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca 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 ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) 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 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 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 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 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 ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl 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 ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan 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 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 ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
[Table view] |
Text
.
NRCi TRIBUTION FOR PART SO DOCKE .1 ATE RI AL (TEMPORARY FORM)
CONTROL NO: 878 FILE: INCIDEPT PEPC'T FI'2 FROM: Metropolitan Edison Co. DATE OF DOC DATE REC'D LTR TWX RPT OTHER P.O. Box 542 Reading,Pa. U R.C. Arnold 4 9 7r A s_7s AG TO: ORIG CC OTHER SENT AEC PDR NRC 1 signed SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
EX 1 50-289 DESCRIPTION: ENCLOSU R ES:
Ltr. trans the following... Abnorm Occurr. fi 75-07, on 3-17-75, cancernini Connector and Wiring on Engineered Safe-guard Motor Control Center _ Units. . .
. . . . .s
~
PLANT NAME: Three Mile Island til FOR ACTION /INFORMATION vrp t :_,s BUTLER (L) SCHWENCE R (L) ZIEMANN (L) REG AN (E)
W/ Copies W/ Copics W/ Copies W/ Copies CLARK 'L) STOLZ (L) DICKER (E) /LE AR (L) w f r.n piet W/ Copies W/ Conies / W8 Con.es dan o (L) V A9SA! ! O f t i KNIGHTON (El SPELS W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOD (E)
W/ Copics .W/ Copies W/ Copies W/ Copies INTERNAL DISTRISUTION A/T IND
@G FU : 3 anGFDR TECH REVIEW
,,,, SC H R O E D E R
.DENTON LIC ASST R. DIGGS (L) _B R AITi.. AN f ~ PRIMES SALTZMAN 03C ROOM P 50GA MACCARY GAMMILL H. GE ARIN (L)
GOSSICK/ST AF F KNIGHT KASTN E R E. GOULSOURNE (L) MELTZ BALLARD P. KREUTZER (E) f CASE PAWLICKI SHAO SP ANG LE R J. LEE (L) PLANS GIAMBUSSO MCDONALD BOYD **p ST E L LO M. MAIGRET (L)
MOORE (L) ** , HOUSTON ENVIRO S. PEED (E) CHAPMAN
- ,,,,N OV AK MULLER M. SERVICE (L) DUBE (Ltrl DEYOUNG (L) E. COUP E SKOVHOLT (L) f ROSS DICKER S. SHEPPARD (L)
KN:GHTON M. SLATER (E) PETERSON GOLLER (L) (Ltr) f IPPOLITO TEDESCO YOUNGBLOOD H. SMITH (L) HARTFIELD (2)
P. CO LLINS KLECKER DENISE LONG REGAN j S. TEETS (L)
LAIN AS PROJECT LDR/ G. F LLI AMS (E) EISENHUT REG OPR V. WILSON (L) . . WIGGINTON
/ FILE & REGION (2) . BENAROYA pT.R. WI LSON (;:) VOLLMER HAR LESS R. INGRAM (L) F. WILLIJ23 STEELE w:m:n -
/ . o 'l
"'^'
<1 - LOC AL PDTk3dtddd 1 - PDR S AN/L A S!Y j1 - TIC (ASERN ATHY) (1)(2dO) - N ATIONAL LASS 1 - BROOKH AVEN N AT LAB 1 - W. PENNINGTON. Rm E 201 GT f 1 - NSIC (BUCHAN AN) 1 - G. ULRlKSON. O r ' L 1 - ASLB 1 - CONSU LT ANTS 1 - AGMED (RUTH G ;SS'." A:;)
1 - Nev. ton Anderson NEWM ARKiBLUME/AGB ABI AN R m B.12 7 GT 5- ACRS S::: TO 1.10 f. s:
1 - J. D. RUNKLES. Rm E :01
- SE::D C:? Y TE: D!a* TlTO.;TS GT 1484 233 y g , g 2 g 03g 3 g _r
fI#n '
- ~nmu METROP LITAN EDISON COMPANY -
POST OFFICE BOX 542 RE ADING, PENNSYLV ANI A 19603 TELEPHONE 215 - 929-3601 April 2, 1975 GQL 0593 Director Directorate of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sir:
Operating License DPR-50 Docket #50-289 The following abnormal occurrence is submitted in accordance with the Technical Specifications for Three Mile Island Nuclear S tation, Unit 1, and is being submitted at this time in accordance with the March 26, 1975, conversation between your office's Mr. D. Jaffe and our Mr.
D . N . Gra ce .
(1) Report Number: A0 50-289/75-07 (2a) Report Date: April 2, 1975 (2b) Occurrence Date: March 17, 1975 (3) Facility : Three Mile Island Nuclear Station Unit 1 (4) Identification of Occurrence:
Title:
Connector and Wiring Problems on Engineered Safeguard Motor Control Center Units Type : An abnormal occurrence as defined by the Technical Specif-ications , paragraph 1.8d, in that the connector and wiring problems on Engineered Safeguards motor control center units could possibly threaten to cause portions of Engineered Safety systems to be incapable of performing intended functions .
(3) Conditions Prior to Occurrence:
Power: Core: 99%
Elec.: 867 E' (Gross) 1484 234
RC Flow: 139 x 106 lb/hr RC Pressure: 2150 psig RC Temp.: 580 F PRZR Level: 240 in.
PRZR Temp . : 6500F (6) Description of Occurrence:
On February 26, 1975, a situation regarding the reliability of Engineered Safeguards electrical circuits was reported as Nonroutine 30-Day Repo rt 75-01, and it was during investigations conducted in correction of this finding that additional problems were found and determined to constitute this abnormal occurrence. The initial March 17, 1975, telephone report of this occurrence noted that investigations had revealed 6 of 20 engineered safeguards motor control center units to have some type of wiring and/or connector problems. In addition to these problems, this report also addresses the results of additional inspections conducted through March 22, 1975. Specific descriptions of affected units, and respective associated components, results of inspections, and corrective actions , are given in the attached table.
(7) Designation of Apparent Cause of Occurrence:
The apparent cause of the occurrence is pcor workmanship daring the process of manuf acture and/or installation. This is primarily manifested in three areas : use of wire smaller than required in the manufacturer's specifications, poorly crimped lugs, and loosely-bolted electrical connections.
(8) Analysis of Occurrence:
lt is believed that the connector and wiring problems in the Engineered Safeguards motor control center units discovered in the inspections conducted through March 22, 1975, did not represent a threat to the health and safety of the public in that there was no evidence of overheating nor any indication of imminent f ailure related to these problems. Further, even in the event such a failure had occurred, sufficient redundancy existed to provide the necessary reactor core cooling, reactor building cooling, and isolation functions.
With regard to further operations prior to completion of an inspection program that is still in progress, it has been determined that this cccurrence does not threaten the health and safety of the public because of the redundancy that exists in safety systems, and the fact that two or more unit failures--for components in the same or related safety systems--would have to occur for the capability of safety systecs to be less than that assamed in the accident analyses ;
and the chances of this happening are considered to be highly unlikely.
1484 235
(9) ,
Corrective Action:
Immediate corrective actions have been taken as described in the attached table. It thould be noted that in some of the cases described therein, materials 1eed to be procurred prior to being able to remedy known deficiencies.
The Plant Operations Review Committee (PORC) met after the occurrence and recommended that when possible, deficiencies be continued to be corrected immediately upon discovery by tightening connections or replacing wire. PORC also recommended that
- a. the inspection of all safety related units (except those requiring plant shutdown) be completed by April 18, 1975, and
- b. the inspectien of all units in Engineered Safeguards Control Centers be completed and, if possible (i.e. barring material procurement problems) corrected by June 30, 1975.
The Station Superintendent concurred with PORC's findings, has taken steps to ensure PORC's recommendations are implemented, and in addition has directed that the use, type, calibration, and control of crimping tools be reviewed and, as may be found to be appropriate, administrative procedures be revised to include the results of this review.
(10) Failure Data:
- a. Previous Failures: See Nonroutine 30-Day Report 75 -01
- b. Equipment Identification:
ITE Imperial Corp.
480 V Motor Control Center Series 9600 Sincerely, R. C . 4hmold ~
Vice Pr'esident-Generation RCA: RSB :ccs cc: Office of Inspection and Enforcement, Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 File: 20.1.2 '7.7.3.5.1 1484 236
.:: .: i .. nn n n Or :
L..n-ll1,.,.
n.
. > , n. : i.. . .l la.
1, !.>. n. n. ! !l n.: I,, nO n t o> n6-i.,
- n. t .
<. i.
~ r. . .
L,. L. ~. n. .
g O c' t-
Cl l 'l < > lej I th ' ' t'l l '1 (t) d t *j
(
ct tej OJ to d tij l d til in (1) e t t'j UJ d (']
ts)
( F t rl U) ct l'j U2 gt l'j U) C w
H '
D) ON .O
- Pq3 i An d 0I bsp u4 \ n (1 -1 TV p. ; }'
,^ 1 to 4 u t.'<* >
c > (n u :r: Jij . l v1
t .'
to cn La :t:
O :n t*
O p o
'l
\
8 -
f l ro e 'O :q .k 4 to O O e -J tti to O N 03 *ti O- 4O l-% d lif 't= O t7) f 7
't1 ; n,'D 1dt *o 9 i 1 til
%j j p *) t ' t3 N* I ll 0 H1**j ' HI P
ta ju <D i ;p ga rD > *1 y) >$ U) p **j O O to O > 0 p 1 p I ts [1 p 1 m e-) ,. 11 I d la t1 O P 1 gb t;*
M .O #D ct 8 4 l'8[1 f 4 ed (D 4-4 o to . O P ' J <.* ^ (D. U) O 4 : d O O lf O. 'TJ V1 s d" (D C t> ' O '9
- 4I (D ea *g to > - (D > PI I IL I (D 1 *f O I * 'rj O 6^ t 'l o l I @ pb ED {0 TV l8 IV pe 't1 P 1 k*
(b W 't l II" ' 'i
^
d !T! l, 'Y: tJJ '
(Ji 4> > O s1 'd 1 LIf (G \11 !
J' fo O N HO (n (D <* (D d > '.
P ro I o
,D '
rd I E D
3 's L1 yd o n 40 p l g
p g [". i t tf p
J Q 1O Ch f1
. m .'%
' t?.!
O :n
')
l '3 Ut i P IIM , H > fo p
4 ! M (D M '
't O (D *1 F'.
',l GO [1 (D l (D NO fL &^
'tf M.
Q d i H ct [] o J,
~s M *1
. o, r
o i i
O O
.s .'
u 1
- 4 <
Y sl 5l*S W t*
i 5; ro mN o g p. O . { ._ t.tf f.* O d t.If (D O' M af D M P tt! ' tf W 'd.
rD 64 *p $ *1 H 0: & la O s 6 8< l 'tf Mt 'b.I I rpU c f '^ <F r . O P- O 't t) O O U (D ta F* O P c0 lij O
o M y ta fa i) .
I f 'Dty d
( 1TO T1#D I A
l y en (D gD gD fo 4 U (D p *f lt iD H <D of 68 i ct (D
p '(t!
1 d ct 1* (L 4- (D
- f *f d M (D (D v3 68 ct to C:
5: If O 8 N 'd ,
- D (p o' 98 p m sh r* I If M D* v* (h to d t*
In fD U p (. J to ct p P. rn '
- d. O o pm @ M l N (D G G d M Ha (D P O d il o [1 m i6 .tg $ I 'I ' ' ' bO O pm@ l
'I rD $h p
o& e e l. D<hD m e eD - ,n.u . (3'D
., . l.
gd
,,, t Do, 11, y
oo (D
M,.
i o
o'*
o Cb m e v.
U,
.rf p II d
'9 e is: h: ofi dp II o
- o. ., e t nn,:1 o I 't 5: g$
- l' i .g g ey M et M o In: O p, (D <D f g e., gg ge I I' ( ), e t t) t (0 tm 18 O O 1J P O tj l . e ., , in (D l iD
' 98
'i g )i . . l. I . )., m o l, o o rfee i tv mo to v. -: d o' o '.
p et eee in I I D ({ l '
- 8D D e j i PO ct 11 tD (a ta d 11 ti) o f 't t ja ' t s h ' g' I.oy
. e ;'rft ' 1 l, ; ,t eD g .: M in 't f (D t) O in 11 o o t s' L1 ft ' t. j (Ps ta e n- (n e og in
- f 11 , o 11 r f (D *1 it: et eg D i)
I vb O ,D *r f - O* p. (D ,,
18 U 11 sto p. i ut 11 O (9 OJ t' D ra 'i ()
eg 'r1 eb o Ol
< F :s e t t .'
p i 10 i ih hl4D 3 gg O
cf O
te p 't f af t0 s:
I (D e o
Md p 49 C 11 t cf "
ct et to to ae I
sn o +th tI:PO O <D ,
- l. M I jn o 't to d ta pb 'e lo e o' ')
t '+ s : 3 .!
EG t t' Ipd tf If q [ p- d 18 [f Ie e in O v* t i- -J p. M et t ta ff o g (f et
', l f l
l 'O ED 'd l 'i Ptb O d if rD & , ,, to 't sh y i +, ; (D 13 O *f tf d (D to a o o in D rD c) l[ o' (D '. af ,o, g.
ct ct O t
O p O tD y in o ti to Ie o if Io* .fi lp5' p.s-og I o t
g gg .,
og o et ta (D r s* gh s'i iD , e o ., , : in ! (D u t-1 1o, d o
<D lh 'i m : . ,,,
'D 't in I 8,. '> wi.
. m (D
I' (D
11 h+ '
1 iD < v 5'
l"s, O e
'D I "'
d:
r/
'D 'O O u O 'D i ,v, O m .. . d. - ,
O th o. D
( ,
, en 't n. 's a
,D 62- % (D I . I :D 0 O (L l i (D (D g m Os 13 - ll-I g .a 1 't ; I i v'
' ,p , . I. .
C > to C O' t1 94 N I'1 N Pt1M *
!rf '
- 3' O 63 t-] e in '11 t-3 O g .. g (D l *.
' , h t-1 la l J 'e g ;$ oI8 l '< o1>$4 & cp '
ri O i% 6% l O ls'b iM s. (D P O y *f (n O o en (F G M c t tp M M o (73 I p I d 't '< f 73 o
p 'r f l *e to (D . . i ff o og 3 (D P* O G l
13 yf n' ;
(73
't =
() '
d dif to ; , O d ,) i s <e cD d ce j g p d i 1 is.
in, iDd i+
.. IS' y(D el a unrrm
- e. p M %: o i :, nd:
l.
g a e't e- .n (D a
o (D (D u e Ou-(D s: (lij
- ',J' n$b i d du (D r1 Of
! ,1 o
i la IJ ei iD p.
I8 l8 (D ,
' sw .
(D O
p (D ti no o (D p (D cD
[b
.D
$b 0 (D i ti gL e (D
fL d b E' ta su FL -
11 ' t P '
i:t +
rO o b* Ot* d td tf b 1,; fn I *1
- O G II (D l1 d O' O U* {I MO O' If cf a ddtf o i n m O (t> m O (D :r O rO n O.
i3 (D u O sD O (D - M d d mO (D o o :D e p l l- O P
,, qm u o
!F o' d p n. d d d u e c+
o u.
e m .;
i i .a O i e iV, - -.
a .
<.j o m e d'tl M l w t a rD
- n [" pa h. ' O 1;m ' L. , . . .
m m e e [*s e nm s e *d <*
r u 1 S> O
- . rf ,g.
a < . 0ap np d e in r.-
gfi pe s.
c.
! p r et od d r c+ o (D e G ,D ru d e l P e- O g1 o gl (D (D m d
.p. . o sb I. C. .i p
i '
p$
p p1 p
et p'
u D
'pe .c
N I. ..
l
. - _ _ . . . ' _ - __..--.1.._----. - - - - - - - - .
O 1
ia ia LN ' ;[I x '
x< '
x x x N M Ni '
X M L*H
-J !
dO 3
, l f b
- i i a m. I l f
,. ,. I.
t
,n: ...:
A~ v 1 .0r
% ~ g.'a" _..et_.__.".. r~r _ ~1 - .. C .^.~"D7.. . . .' ' i .,
. . _ CO". PO'3E".'."
. r. .T.S"s L _c Cr.
I
- t. t
- r.,
. - r3 u. .n. y5 un - Inern. - W_4 . _4 n e- .e. ..__
_ e__, ,...._.2 . e. . e_w.' e a d "_4 . L' .e-4., ,,, , -Cooler Discharge w,c,.._ .r ,o,se
. ._ _n
- ypass ,e e, ve, 7 _
, a=.= ' ~.^ . =. .' U. 4. . s _3 I a. l_ a_ =_^ vas ',
U. ES VV i Heat Trace -
W4_re s 4_ze :n sne-S _
I
" nit 10 AL- Panel LA b etve a. .e'<_- p_e_ w .a=>=_ _ ._ _ . . W_4 _ a. replaced vi h #10 AWG ,
i wa s #' 9 * -
e , _e _ "_ " ' A_ sa e .4. ., 0 .y., I sta e lead . ,
- - r. 3 1
- i 1C ES VV WDG-V-2 R.C. ,
Lus; not inse-ted preper: y en ene! Inse-ted lug correctly. I Unit 7C
- Drain Ta.% phase at treaker. Screv ! Cishtened screv l's i
turn i Vent Valve loose load side cf treaker t
.._. 1
! Will reple.ce with 1A ES VV ! L80 V Recept '
Scre s en Icad side cf b-ao>a-
" nit 10 AR Ah, A5, A6 ,
do not assn-e gced connection suitable ccnnectors
-t~
-: r_e yy
- !. Dv.._yh3 %m, e.,. . o~. t ..e_ w _:._ v__ e
- o. e-._ e '. a'. '. o I
to o e_a.- v _-- te ra_placed
'i.~. .". v4_ "_ _'s aved'abla.,
.:.. _d ',, 1C v.a. a.' P"mnp ur '.
. . 'D . e c.' .a. - ' s 's. ~.~ s > - . '. . W4 ~.
Reactor Valve ,
Ch and X3 net n.renerly in- -
- Wires reinse-ted and 8
c e e.e d _4m,, s ,m. e*.- +. o v.._s. 4 a_7 . I 'w 4_ ,u e me.c.a N .
,i t&n
- e pho_.e , n. e._ . _ _ .
'C"_ "_'_- C _' ^ .e a. ;
. s *o *_.*-'.'. a - n'_'.'.'.'.a__' .'%.'.'.
m e
s " 7 a',, ' - ". a a- _a__-^~._"_
_ . i, a____.__ -. . . . _ . _ - - . -
- r_ VV S_W H2 Borated We.e .e
. r..>.__= _-_ _s=-- '^ = .e _4 _b. c' _ , Laad_e_ v___ be -a.e'a e# . - -
.._: _., , c. "ater Sterage -on.e-a- e= --- o . _m_ . . - .-n.. _ ,
,.u..- .. =_- :_s
. .e.e:__+___a_
Tank Heater 4 - sula'. i _- ve _e a.' . _' , a e d
.'n.t -V- 3 'i Pakeup ' Or.a. e ' ".__ d_ .....'o-.., '
"s, ^. e "~' -- vas ' ..s a. '., a_ d l X
T_S VV
--_i+
- . 2D Punn. Evn. . as s .d- e e c .:.. a. s a e ._ + ..._ ._4_
e.,. , ..-o.-,_.,
,, . =.n 2 . .a-,
Valve . ,,
, .+ 1e-w . .. .4.
_... r_.e VV U.e a+ m.-au-
. 2 a. .."'..,'_,'a e--e' _ ' __= . . .w'. a .- "n i_ _' 1' _~ ,'a e v_.e 4
T.it lOCL Panel 2A & '!A few strands treken naterial is available
-..e, c.a-v
- == _-
n.._
- r r_ , n" .n.. . r. u.. :_.e_, .... .,2
. ...u. =_ _ e -. _. .2, +
- l. r.o .,. u_ang,an. n..:
- w r ~~~. =-~ n . n . .-- - .
r_- m. .m : ~ r. .e a. c,, e.;: s=_;i e.
~.v- m. . .h_ ,M.. z. ~_, _~_.u--
~
Vent Fa.
- _ } . - - --- - - - - -
_ _:. r.e, yy n.:
na-E-1B n ea . c- ' .. 's %v . _'"..~..=.#.
.>..'.'e"',
"_ _, b a. .. ' . _ey ~ m' a_ d e_
-a
-A - 6 p*C. U.e. ,+ . . r. E . 4e. e . v... . a. . . ...
-, rwe v.y a c n.._r__ _1 v n p.e A. ^ ^. ^. .- ..'-'w
. .a b. . _# . . *, a. . . a. #_ '.'* __ # ' a. U".# . _ "O %.
- e.;" a 'v a #
,1* 2e s'.,....... 2....
._2 _. __n 31. dg . *s*ee.+. . r. aw.. 4
_ . r_e r3_r._1A n2ese,_
e
"."et i . M.. _. '..=s=_.=.'.
. . ".".'__'a "-_. ' , ,
. "_^%.. '..e~_~'.,a.'
. . . ..: r.,
~~
C.e a ra+ C ,. n.; ,. .
4e
.. oe- . L. 2..
. .~
s .> . -
- r. .m._. .v-C-. e e.,w.n -
" ,
- O -... . . . _ e, w o e . - o .+. . A
_- . . -,_... c . . . : . .u.. . _e
_.: . r. a,7-1_An
. .w.. ?e,a.
e V. e. e. v _...y .. -9 4.
. . . . . :". .. o
.co ,.. m aw e s .,. 4e
.. .w e...... 2_....
Cenerator AUX.
- 7. , L. 4. F . ..,w
.g . .+.
l 0
I t
C .20Tn'E ;.0 CC" i
. ~a /g-. T.'.
. C wn'a9 . 0F. .". a" P.r m^" ".. r~. '
. T". . . T. r" ~. ^. " u"T. T_0.". . e. r. _ . ._
10 ES VV ITR-S-13 !!uclear > Must be inspected while unit '
To be inspected i Uni 13AE Service River i is shut devn i 3
Punp Discharge :
Sh2ner !
i i 6 13 ES Unit EG-PlE Diesel l Must be inspected while unit To be inspected 303 Generator Air ' is shut do-I Cc gressor ! ,
t I
f I
t t
I t
i
,, "- _ ~ * ['
- w. m -.+- c-. p,,
i 1484 239 l k
D
_ _-- _ _ . _ _ _ _ .