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l' NRC Form 3ee U.S. NUCLEAR KEIULATM;V COMMtBS80N N'
APPROVED oms 8eo attM104 LICENSEE EVENT REPORT (LER)
F ACILITY NAME til DOCKET NUMeER (2)
PAGE G Three Mile Island Unit 2 o [ slo go lol3l 2 0 s lorl 0l3 1
Inoperability of Emergency Diesel Generator DF-X-1B Dt.c to a Failed Governor and a Defective Soleroid EVGerT DATE ill LER seUM6ER tel 84EPORT DATE (7)
OTHER FACILITIES INVOLVED 18)
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NAME TELEP* SONE NUMBER ARE A CODE 9,4 8,
,8,2,4 4 7 l,7 Christopher J. Dell, TMI-2 Licensing Technical Analyst i
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At 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on December 13, 1985, the annual preventive maintenance for Eniergency Diesel Generator DF-X-1B commenced. On December 20, 1985, while performing the required demonstration of engine operability, it was determined that there was no remote speed control. Troubleshooting eventually identified the governor as being defective. A replacement governor was obtained and installed. Retesting indicated that the remote speed control problem was corrected, but there was no shutdown capability. Further troubleshooting l
discovered a defective solenoid in the replacement governor. A new solenoid was obtained and installed. Engine operability was successfully demonstrated and the engine was returned to service at 1709 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.502745e-4 months <br /> on December 21, 1985 Thus, Emergency Diesel Generator DF-X-1B was out-of-service for more than seven (7) days, exceeding the timeclock of the Action Statement of Technical Specification 3.8.1.1.
The event is reportable pursuant to 10 CFR l
50.73(1)(2)(1)(B). The root cause of this event is not known at this time.
The governor and solenoid will be returned to the manufacturer for analysis.
A supplemental report will be submitted to report the results of the analysis.
e 8601230127 B60116 [V'
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/i asac Pera sesA U.S. NUCLEAR REGULATORY COMMISO40N LICENSEE EVENT REPORT (LE~) TEXT CONTINUATION AreaOveO OMS =O stio-oio.
Expints S/31/05 pactLITY esaast du DOCKET NUMBER G8 ggg geUMBER (S)
PAGEtal VIA" es a we a Three Mile Is1and Unit 2 o !s lo lo lo l3 l 2l 0 8 l6 0 l 0l 1 0l 0 0l2 or 0 l3 fin,, i -.,
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PLANT OPERATING CONDITIONS BEFORE THE EVENT
The TMI-2 facility was in a long-term cold shutdown state; the defueling evolution is in progress. The reactor decay heat was being removed via loss to ambient. Throughout this event there was no effect on the Reactor Coolant System or the core.
II.
ST4TUS OF STRUCTURES, COWONENTS, OR SYSTEMS THAT WERE INOPERABLE AT THE START OF THE EVENT AND THAT CONTRIBUTED TO THE EVENT At the time of the event, Emergency Diesel Generator DF-X-1B (IEEE Code - EK) was out-of-service due to the performance of the annual preventive maintenance.
III.
EVENT DESCRIPTION
At 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on December 13, 1985, the annual preventive maintenance of TMI-2 Emergency Diesel Generator, DF-X-18, commenced in accordance with TMI-2 Preventive Maintenance Procedure 4220-PMR-3860.01, 'niesel Generator Inspection." On December 20, 1985, while perfarming the required demonstration of engine operability at the completion of the preventive maintenance, it was determined that there was no remote speed control, i.e., the speed of the diesel generator could not be regulated by the Control Room. Troubleshooting eventually identified the governor (IEEE Code-65) as being defective. A replacement governor was obtained and installed. Retesting indicated that the remote speed control problem was corrected, but there was no shutdown capability. Further troubleshooting discovered a defective solenoid (IEEE Code-SOL) in the replacement governor. A new solenoid was obtained and installed. Engine operability was successfully demonstrated and the engine was returned to service at 1709 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.502745e-4 months <br /> on December 21, 1985.
Due to the timing of the governor and solenoid failure, i.e., at the completion of,the annual preventive maintenance, Emergency Diesel Generator YI-X-1B could not be restored to service within the seven (7) day timeframe permissible under the Action Statement of Technical Specification 3.8.1.1.
The Action Statement was exceed by twenty (20) hours and nineteen (19) minutes. Therefore, this event is reportable parsuant to 10 CFR 50.73(a)(2)(1)(B).
s IV.
ROOT CAUSE OF THE EVENT Therootcauseoftheg'Sernorfailureandthesubsequent defective solenoid has not been determined. A supplemental report will be submitted wher this information becomes available.
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CORRECTIVE ACTIONS
Short Term - The failed governor and subsequent defective solenoid were replaced. Engine operability was successfully demonstrated and the diesel was returned to service at 1709 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.502745e-4 months <br /> on December 21, 1985.
Long Term - Both the governor and the solenoid will be returned to the manufacturer for analysis. GPU Nuclear will interact with the manufacturer on this event to determine if additional corrective actions are necessary.
VI.
COWONENT FAILURE DATA Part Type Part Designator Manufacturer Governor D-8240-089 Woodward Solenoid 5407-049 Woodward VII.
AUTOMATIC OR MANUALLY INITIATED SAFETY SYSTEM RESPONSES N/A VIII.
ASSESSMENT OF THE SAFETY CONSEQUENCES AND IWLICATIONS OF THE EVENT During the period the Emergency Diesel Generator, De-X-18, was inoperable, Emergency Diesel Generator, DF-X-1A, was in service.
The operability of DF-X-1A was demonstrated by performing the surveillance requirements of Recovery Operations Plan Section 4.8.1.1.1 and 4.8.1.1.2.a.4 in accordance with the Technical Specification Testing Frequency Matrix of Table 3.8-1.
During the period DF-X-1B was inoperable, offsite AC power was available and DF-X-1A could have performed the same function as DF-X-18.
No events requiring use of the Emergency Diesel Generators occurred during this period; therefore, this event had no effect on the health and safety of the public.
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Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 4410- 86-L-0016 Document ID 0386A January 16, 1986 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Licensee Event Report 86-01 Attached is Licensee Event Report 86-01 concerning the inoperability of Emergency Diesel Generator DF-X-1B on December 20, 1985.
This event is considered reportable pursuant to Title 10 of the Code of Federal Regulations, Section 50.73(a)(2)(1)(B).
Sincerely,
/
',k.
kuw F. R. Standerfer Vice President / Director, TMI-2 FRS/CJD/eml Attachments cc: Regional Administrator - Office of I & E, Dr. T. E. Murley Director - TMI-2 Cleanup Project Directorate, Dr. W. D. Travers M
t 1 l
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 1
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| 05000320/LER-1986-001-01, :on 851220,Tech Spec 3.8.1.1 Found Exceeded Due to Emergency Diesel Generator DF-X-1B Out of Svc for More than 7 Days.Caused by Remote Speed Control Problem Due to Leaking Governor & Loose Fittings on Solenoid |
- on 851220,Tech Spec 3.8.1.1 Found Exceeded Due to Emergency Diesel Generator DF-X-1B Out of Svc for More than 7 Days.Caused by Remote Speed Control Problem Due to Leaking Governor & Loose Fittings on Solenoid
| 10 CFR 50.73(a)(2)(1) | | 05000320/LER-1986-001, :on 851220,no Remote Speed Control Existed on Emergency Diesel Generator DF-X-1B.Caused by Defective Solenoid in Replacement Governor.Governor & Solenoid Returned to Mfg for Analysis |
- on 851220,no Remote Speed Control Existed on Emergency Diesel Generator DF-X-1B.Caused by Defective Solenoid in Replacement Governor.Governor & Solenoid Returned to Mfg for Analysis
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-001-01, :on 860103,snubber RC-18 Found Inoperable Due to Detached Parts.Caused by Personnel Error.Snubber Restored to Operable Status & Engineering Evaluation Performed Per Tech Spec 4.17.1.g.2 |
- on 860103,snubber RC-18 Found Inoperable Due to Detached Parts.Caused by Personnel Error.Snubber Restored to Operable Status & Engineering Evaluation Performed Per Tech Spec 4.17.1.g.2
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-002, :on 860104,anticipatory Reactor Trip from Turbine Trip Occurred During Power Escalation.Caused by High Moisture Separator Level.Failed Controller Replaced & Power Escalation Recommenced |
- on 860104,anticipatory Reactor Trip from Turbine Trip Occurred During Power Escalation.Caused by High Moisture Separator Level.Failed Controller Replaced & Power Escalation Recommenced
| | | 05000320/LER-1986-002-01, :on 860103,discovered Containment Isolation Valve DW-V-139 Open.Cause Not Identified.Valve Locked Closed.As Precautionary Measure,Double Valve Isolation Outside Containment Will Be Maintained |
- on 860103,discovered Containment Isolation Valve DW-V-139 Open.Cause Not Identified.Valve Locked Closed.As Precautionary Measure,Double Valve Isolation Outside Containment Will Be Maintained
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-003, :on 860114,undervoltage Relay for CRD Trip Breaker Failed,Causing Inoperability of Shunt Trip Feature. Caused by Incorrect Positioning of Relay Jumper.Jumper Insp Added to Procedures |
- on 860114,undervoltage Relay for CRD Trip Breaker Failed,Causing Inoperability of Shunt Trip Feature. Caused by Incorrect Positioning of Relay Jumper.Jumper Insp Added to Procedures
| | | 05000320/LER-1986-003-01, :on 851117,fuel Handling Bldg Exhaust Monitors HPR-221A & HPR-221B Not Tested within Required Interval,Per Tech Spec 3.3.3.1.Caused by Personnel Error.Monitors Successfully Tested |
- on 851117,fuel Handling Bldg Exhaust Monitors HPR-221A & HPR-221B Not Tested within Required Interval,Per Tech Spec 3.3.3.1.Caused by Personnel Error.Monitors Successfully Tested
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-004-01, :on 860227,w/condenser Offgas Monitor RM-A-5L Out of Svc & Continuous Watch of RM-A-13 Not Established, Small Leak in once-through Steam Generator Unidentified. Caused by Personnel Error |
- on 860227,w/condenser Offgas Monitor RM-A-5L Out of Svc & Continuous Watch of RM-A-13 Not Established, Small Leak in once-through Steam Generator Unidentified. Caused by Personnel Error
| | | 05000320/LER-1986-004, :on 860224,number of Transfers of Expended Filter Media to Holding Drum Exceeded Limit in Ser.Caused by Failure to Incorporate SER Transfer Limits Into Procedure. Procedure Revised |
- on 860224,number of Transfers of Expended Filter Media to Holding Drum Exceeded Limit in Ser.Caused by Failure to Incorporate SER Transfer Limits Into Procedure. Procedure Revised
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000289/LER-1986-006, :on 860315,turbine/reactor Tripped.Caused by Low Oil Pressure.Procedure Changes Initiated to Ensure Standby Lube Oil Cooler Filled & Pressurized Prior to Attempting to Swap Coolers |
- on 860315,turbine/reactor Tripped.Caused by Low Oil Pressure.Procedure Changes Initiated to Ensure Standby Lube Oil Cooler Filled & Pressurized Prior to Attempting to Swap Coolers
| | | 05000320/LER-1986-006, :on 860715,contaminated Camera Tripod Discovered in Dumpster in Unrestricted Area.Caused by Failure of Unknown Personnel to Implement Controls When Transferring Matl.Tripod Decontaminated |
- on 860715,contaminated Camera Tripod Discovered in Dumpster in Unrestricted Area.Caused by Failure of Unknown Personnel to Implement Controls When Transferring Matl.Tripod Decontaminated
| | | 05000320/LER-1986-006-02, :on 860715,discovered Contaminated Camera Tripod in Scrap Metal Dumpster in Unrestricted Area.Caused by Personnel Error.Tripod & Dumpster Decontaminated & Dumpster Resurveyed on 860716 |
- on 860715,discovered Contaminated Camera Tripod in Scrap Metal Dumpster in Unrestricted Area.Caused by Personnel Error.Tripod & Dumpster Decontaminated & Dumpster Resurveyed on 860716
| | | 05000320/LER-1986-007-02, :on 860727,grab Sample Not Taken & Analyzed within Tech Spec Limit of 24 H.Caused by Declaring Epicor II Ventilation Sys Monitor Inoperable on 860724.Another Grab Sample Obtained |
- on 860727,grab Sample Not Taken & Analyzed within Tech Spec Limit of 24 H.Caused by Declaring Epicor II Ventilation Sys Monitor Inoperable on 860724.Another Grab Sample Obtained
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-007, :on 860326,design Criteria on 2 H Backup Air Supply Sys Not Met.Caused by Error in Original Sys Design. Manual Isolation Valves on Side of Two Check Valves Will Be Kept Closed |
- on 860326,design Criteria on 2 H Backup Air Supply Sys Not Met.Caused by Error in Original Sys Design. Manual Isolation Valves on Side of Two Check Valves Will Be Kept Closed
| | | 05000320/LER-1986-008-02, :on 860828,nonperformance of May 1986 Monthly Surveillance Test for Fire Suppression Water Sys Valve Lineup Verification Noted.Caused by Personnel Error. Personnel Counseled |
- on 860828,nonperformance of May 1986 Monthly Surveillance Test for Fire Suppression Water Sys Valve Lineup Verification Noted.Caused by Personnel Error. Personnel Counseled
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-009, :on 860422,incorrect Cable to Emergency Cooling Fans Identified During Environ Qualification Reverification Walkdown.Caused by Personnel Error.Cable Replaced W/ Environmentally Qualified Cables |
- on 860422,incorrect Cable to Emergency Cooling Fans Identified During Environ Qualification Reverification Walkdown.Caused by Personnel Error.Cable Replaced W/ Environmentally Qualified Cables
| | | 05000320/LER-1986-009-02, :on 860904,control Room Bypass Filter AH-F-5 Deluge Sys Isolated by Tagging Out Valve FS-V-507 W/O Hourly Fire Watch.Caused by Personnel Error.Personnel Counseled & Procedure Revised |
- on 860904,control Room Bypass Filter AH-F-5 Deluge Sys Isolated by Tagging Out Valve FS-V-507 W/O Hourly Fire Watch.Caused by Personnel Error.Personnel Counseled & Procedure Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000289/LER-1986-010, :on 860423,reactor Tripped on High RCS Pressure Resulting from Inadequate Main Feedwater Flow.Caused by Personnel Error.Procedural Changes Initiated |
- on 860423,reactor Tripped on High RCS Pressure Resulting from Inadequate Main Feedwater Flow.Caused by Personnel Error.Procedural Changes Initiated
| | | 05000320/LER-1986-010-02, :on 860930,radiological Controls Technician Discovered AMS-3 at Reactor Bldg Equipment Hatch Exhibiting Failure Light.Caused by Personnel Error.Faulty Detector Replaced & One Hatch Door Closed |
- on 860930,radiological Controls Technician Discovered AMS-3 at Reactor Bldg Equipment Hatch Exhibiting Failure Light.Caused by Personnel Error.Faulty Detector Replaced & One Hatch Door Closed
| 10 CFR 50.73(a)(2)(1) | | 05000320/LER-1986-011-02, :on 861207,during Replacement of Charcoal filters,16 Deluge Sys Fire Detectors for Fuel Handling Bldg Exhaust Filter AH-F-14A/B Inoperable.Caused by Personnel Error.Hourly Fire Watch Established |
- on 861207,during Replacement of Charcoal filters,16 Deluge Sys Fire Detectors for Fuel Handling Bldg Exhaust Filter AH-F-14A/B Inoperable.Caused by Personnel Error.Hourly Fire Watch Established
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-011, :on 860601,breaker 1C-02 (Feeder Breaker to Turbine Plant Bus 1C) Tripped.Caused by Failure to Reset Plunger on Phase a Overload Device,Discovered on 860602. Westinghouse Breaker DB-25 Replaced |
- on 860601,breaker 1C-02 (Feeder Breaker to Turbine Plant Bus 1C) Tripped.Caused by Failure to Reset Plunger on Phase a Overload Device,Discovered on 860602. Westinghouse Breaker DB-25 Replaced
| | | 05000320/LER-1986-012-02, :on 861214,sprinkler Nozzle (IEEE Code Nzl) for Control Room Bypass Charcoal Filter AH-F-5 Logged Inoperable.Caused by Personnel Error.Nozzle Cleaned,Retested & Returned to Svc |
- on 861214,sprinkler Nozzle (IEEE Code Nzl) for Control Room Bypass Charcoal Filter AH-F-5 Logged Inoperable.Caused by Personnel Error.Nozzle Cleaned,Retested & Returned to Svc
| 10 CFR 50.73(a)(2)(1) | | 05000289/LER-1986-012-01, :on 860904,exhaust Duct Grill in Switchgear Room 1D Found Blanked Off,Blocking Air Flow from Room.Caused by Personnel Error.Fire Watches Established |
- on 860904,exhaust Duct Grill in Switchgear Room 1D Found Blanked Off,Blocking Air Flow from Room.Caused by Personnel Error.Fire Watches Established
| | | 05000289/LER-1986-013-01, :on 861107,reactor Bldg Integrated Leak Rate Test Declared Failure as-found.Caused by Purge Exhaust & Penetration Pressurization Valve Leakage.Check & Butterfly Valves Repaired & Procedure Revised |
- on 861107,reactor Bldg Integrated Leak Rate Test Declared Failure as-found.Caused by Purge Exhaust & Penetration Pressurization Valve Leakage.Check & Butterfly Valves Repaired & Procedure Revised
| | | 05000289/LER-1986-013, :on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable |
- on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable
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