/03X-1 on 770605:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings| ML20027A285 |
| Person / Time |
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| Site: |
Dresden  |
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| Issue date: |
06/05/1978 |
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| From: |
Wujciga J COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML17173A343 |
List: |
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| References |
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| LER-77-022-03X, LER-77-22-3X, NUDOCS 7811090130 |
| Download: ML20027A285 (2) |
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LER-1977-022, /03X-1 on 770605:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings |
| Event date: |
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| Report date: |
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| 2371977022R03 - NRC Website |
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8 60 61 DOCK E T N V'.*S E q 6d 69 EVENT CATE
- 4 75 RE* ORT DATE 80 EVENT DESCRIPTION AND PROBABLE CCNSECUENCES h
!ol:l l During routine startup operations, CRD L-5 was found to uncouple and overtravel when I
i o 13 l l withdrawn to pos. 48.
CRD L-5 was inserted and disamed.
Rx startup operations re-l 101. l lsumed after it was determined that L-5's pos. and core location did not adversely l
i o I s l l af fect core symmetry. Following start-up an overtravel check of L-5 proved matis-l
- ojel l factory, verifying that CRD L-5 was recoupled and operable.
This event occurred l
i>j lpreviously with this rod as ref. in R.O. #50-237/1977-15.
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, i ; o ; l An unlatched inner filter and abnormally long uncoupling rod resulted in the uncoupling t i ;i ; j of CRD L-5 during normal operating conditions.
Since the last overhaul of CRD L-5 in I
,7,g [Jan. 1975, a pull test on the inner filter has been incorporated in the overhaul &
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- ,,3j l assembly procedure. The revised procedure and improved OA coverage is believed l
- , y,,j l adequate to prevent future similar events.
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4 ATTACHMENT TO LICENSEE EVENT REPORT 77-022/03X-1 COM'!ONWEAL'ni EDISON COMPA'iY (CWE)
DRESDEN UNIT-2 (ILDRS-2)
DOCKET #050-237 During routine startup operations, control rod drive (CRD) L-5 became uncoupled and overtraveled when withdrawn to position 48.
This event occurred previously with this control rod on April 2, 1977 (Reportable Occurrence Number 50-237/1977-15).
CRD L-5 was inserted and electrically disarmed.
Reector startup operations were resumed since the position and core location of control rod L-5 did not adversely affect core
(
symmetry.
At a reactor power above 20%, L-5 was recoupled and with-drawn to position 48 and checked for overtravel.
The overtravel check verified CRD L-5 to be recoupled and operable.
This was the twelfth Control Rod Drive (CRD) uncoupling event at Dresden Unit 2 during the preceeding four years.
The inspection of CRD's which had previously experienced this event indicated that improper inner filter j
installation was probably responsible for the uncoupling. If the inner
{
filter becomes unlatched, full withdrawal of the control rod to position 48 could result in CRD uncoupling.
Symptoms of this event indicated that the same inner filter probler probably existed with CRD L-5.
I On November 30, 1977 CRD L-5 was disassembled and inspected per Control Rod Drive Inspection and Maintenance Procedure DMP 209. To assure a com-prehensive inspection a special operating procedure (SOP 216) was pre-pared and followed.
(
Upon inspection it was found that the inner filter was unlatched.
In addition the distance between the CRD flange and the end of the fully seated uncoupling rod was abnormally long (173.406 + 0.750").
The abnormal length coupled with an unlatched inner filter resulted in the uncoupling of the CRD.
As part of the reassembly procedure, C.E.Co. Quality Control Personnel performed the inner filter installation and a required 20-30 pound pull test.
In Feb.,1978 the Control Rod Drive Inspection and Maintenance Procedure DMP 209 was further changed to permit Maintenance Personnel to install the inner filter. This change occurred due to existing Management-Union Work Agreements. However, Quality Control Personnel will continue to conduct the 20-30 pound pull test.
The revised procedure coupled with improved Quality Control coverage of CRD overhaul and reassembly are believed to be adequate to prevent future similar events.
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| 05000237/LER-1977-001-01, /01T-0 on 770117,notification Received from GE That MAPLHGR Absolute Limits No Longer Considered Sufficiently Conservative.Caused by Error in MAPLHGR Calculations.Tech Spec Rev Request Initiated | /01T-0 on 770117,notification Received from GE That MAPLHGR Absolute Limits No Longer Considered Sufficiently Conservative.Caused by Error in MAPLHGR Calculations.Tech Spec Rev Request Initiated | | | 05000237/LER-1977-001, Regarding Notification from GE That the Maximum Average Planar Linear Heat Generation Rate Absolute Limits May No Longer Be Considered Sufficiently Conservative | Regarding Notification from GE That the Maximum Average Planar Linear Heat Generation Rate Absolute Limits May No Longer Be Considered Sufficiently Conservative | | | 05000249/LER-1977-001, For Dresden Unit 3 Regarding During Normal Operation, Differential Pressure Indicating Switch 3-1349A Failed in the Opening Position | For Dresden Unit 3 Regarding During Normal Operation, Differential Pressure Indicating Switch 3-1349A Failed in the Opening Position | | | 05000237/LER-1977-002, Regarding Discovery of APRM Flow-Bias Indication Exceeding 100% on Both Channels a and B | Regarding Discovery of APRM Flow-Bias Indication Exceeding 100% on Both Channels a and B | | | 05000249/LER-1977-003, For Dresden Unit 3 During Normal Operation, APRM 6 Indication Appeared to Be Registering Power Level Fluctuations of 6 - 10% | For Dresden Unit 3 During Normal Operation, APRM 6 Indication Appeared to Be Registering Power Level Fluctuations of 6 - 10% | | | 05000237/LER-1977-003, For Dresden Unit 2 Regarding Discovery of an APRM Averaging Card Relay Contact Failure | For Dresden Unit 2 Regarding Discovery of an APRM Averaging Card Relay Contact Failure | | | 05000237/LER-1977-004, Regarding Notification from GE That the Maximum Average Planar Linear Heat Regeneration Rate Limits for Dresden 2 and 3 Have Undergone Further Revision, Including Several Reductions | Regarding Notification from GE That the Maximum Average Planar Linear Heat Regeneration Rate Limits for Dresden 2 and 3 Have Undergone Further Revision, Including Several Reductions | | | 05000237/LER-1977-006, For Dresden Unit 2 Regarding Discovery That Three Surveillance Intervals Had Been Inadvertently Exceeded During a Routine Monthly Surveillance Audit | For Dresden Unit 2 Regarding Discovery That Three Surveillance Intervals Had Been Inadvertently Exceeded During a Routine Monthly Surveillance Audit | | | 05000237/LER-1977-007, For Dresden Unit 2 Regarding Discovery of IRM 16 to Trip at 122% of Scale and IRM 16s Rod Block Setpoint at 111% Due to Instrument Setpoint Drift | For Dresden Unit 2 Regarding Discovery of IRM 16 to Trip at 122% of Scale and IRM 16s Rod Block Setpoint at 111% Due to Instrument Setpoint Drift | | | 05000237/LER-1977-008, For Dresden Unit 2 Regarding Discovery of Main Steam Line Low Pressure Isolation Switch 2-261-30C to Trip at 853 PSI, Which Is Below the Technical Specification Requirement of 855 PSI or Greater | For Dresden Unit 2 Regarding Discovery of Main Steam Line Low Pressure Isolation Switch 2-261-30C to Trip at 853 PSI, Which Is Below the Technical Specification Requirement of 855 PSI or Greater | | | 05000237/LER-1977-009, For Dresden Unit 2 Regarding an Attempt to Replace a Burned-Out Indicating Light Bulb for the Feed Breaker to MCC 28-2 Which Tripped the Feed and Indirectly Removed the Normal Supply to RPS Bus B and the Instrument Bus | For Dresden Unit 2 Regarding an Attempt to Replace a Burned-Out Indicating Light Bulb for the Feed Breaker to MCC 28-2 Which Tripped the Feed and Indirectly Removed the Normal Supply to RPS Bus B and the Instrument Bus | | | 05000237/LER-1977-010, Updated LER 77-010-00 for Dresden Unit 3 Regarding Routine Calibration Checks, Undervoltage Relays for Buses 34-1 and 38 Were Found to Be Apparently Inoperative | Updated LER 77-010-00 for Dresden Unit 3 Regarding Routine Calibration Checks, Undervoltage Relays for Buses 34-1 and 38 Were Found to Be Apparently Inoperative | | | 05000249/LER-1977-011, Regarding Reactor Building Vacuum Breaker A03-1601-20A Not Opening as Required During a Routine Surveillance | Regarding Reactor Building Vacuum Breaker A03-1601-20A Not Opening as Required During a Routine Surveillance | | | 05000237/LER-1977-011, For Dresden, Units 2 and 3 During Initial Start Attempt, Unit-2/3 Diesel Apparently Turned Over for Approximately 4 Seconds Before Shutting Down | For Dresden, Units 2 and 3 During Initial Start Attempt, Unit-2/3 Diesel Apparently Turned Over for Approximately 4 Seconds Before Shutting Down | | | 05000249/LER-1977-012, Regarding a Reactor Water Sampling Interval Violation on April 29, 1977 | Regarding a Reactor Water Sampling Interval Violation on April 29, 1977 | | | 05000249/LER-1977-012-01, Regarding a Failure of the Responsible Radman to Collect the Required 4 Hour Reactor Water Sample During the Start-Up | Regarding a Failure of the Responsible Radman to Collect the Required 4 Hour Reactor Water Sample During the Start-Up | | | 05000237/LER-1977-013, For Dresden Unit 2 Regarding Discovery of a Leak of Reactor Coolant Inside the Primary Containment | For Dresden Unit 2 Regarding Discovery of a Leak of Reactor Coolant Inside the Primary Containment | | | 05000237/LER-1977-014-03, /03X-1 on 770402:during Normal Startup Oper,Crd H-8 Was Found to Uncouple & Overtravel When Withdrawn to Pos 48.Caused by an Unlatched Inner Filter & Abnormally Long Uncoupling Rod | /03X-1 on 770402:during Normal Startup Oper,Crd H-8 Was Found to Uncouple & Overtravel When Withdrawn to Pos 48.Caused by an Unlatched Inner Filter & Abnormally Long Uncoupling Rod | | | 05000249/LER-1977-014, Regarding an Occurrence of the Differential Pressure (D/P) Across the Off Gas High Efficiency Particulate After Filters (HEPA) Increasing to Approximately 13-Inches of Water | Regarding an Occurrence of the Differential Pressure (D/P) Across the Off Gas High Efficiency Particulate After Filters (HEPA) Increasing to Approximately 13-Inches of Water | | | 05000237/LER-1977-014, Forwards LER 77-014/03X-1 | Forwards LER 77-014/03X-1 | | | 05000249/LER-1977-015, Regarding a Pressure Switch 3-1349B Setting Greater than the Tech Specification Limit of Less than or Equal to 32 W.C.D.P | Regarding a Pressure Switch 3-1349B Setting Greater than the Tech Specification Limit of Less than or Equal to 32 W.C.D.P | | | 05000237/LER-1977-015, Forwards LER 77-015/03X-1 | Forwards LER 77-015/03X-1 | | | 05000237/LER-1977-016, For Dresden Unit 2 Regarding an Incident Concerning the Torque Switch on the Limitorque Operator for Recirculation Pump Suction Valve MO-2-202-4B Opened and Prevented the Valve from Closing While Isolating the B Recirc | For Dresden Unit 2 Regarding an Incident Concerning the Torque Switch on the Limitorque Operator for Recirculation Pump Suction Valve MO-2-202-4B Opened and Prevented the Valve from Closing While Isolating the B Recirc | | | 05000249/LER-1977-016, For Dresden Unit 3 Regarding an Occurrence Where the APRM Flow Bias Off-Normal Alarm Annunciated During Normal Operation | For Dresden Unit 3 Regarding an Occurrence Where the APRM Flow Bias Off-Normal Alarm Annunciated During Normal Operation | | | 05000237/LER-1977-017, For Dresden Unit 2 Regarding Discovery of the Ball Isolation Valve on E Traversing Incore Probe (TIP) System Guide Tube to Open from the Control Room | For Dresden Unit 2 Regarding Discovery of the Ball Isolation Valve on E Traversing Incore Probe (TIP) System Guide Tube to Open from the Control Room | | | 05000249/LER-1977-017, Regarding the Discovery of APRM 4 to Generate an Inop When 60% of the LPRM Inputs Were Bypassed | Regarding the Discovery of APRM 4 to Generate an Inop When 60% of the LPRM Inputs Were Bypassed | | | 05000249/LER-1977-018, Regarding the Discovery of the Analysis Completion Date for the April 77 Dresden 3 Reactor Water Exceeded the Allowable Limit by 17 Hours | Regarding the Discovery of the Analysis Completion Date for the April 77 Dresden 3 Reactor Water Exceeded the Allowable Limit by 17 Hours | | | 05000237/LER-1977-018, For Dresden Unit 2 Regarding Fluctuation of a Off-Gas Monitor as a Result of Instrument Drift and Low Input | For Dresden Unit 2 Regarding Fluctuation of a Off-Gas Monitor as a Result of Instrument Drift and Low Input | | | 05000249/LER-1977-019, Regarding CRD H-9 Being Determined to Exhibit a 90% Insertion Scram Time in Excess of 7.0 Seconds | Regarding CRD H-9 Being Determined to Exhibit a 90% Insertion Scram Time in Excess of 7.0 Seconds | | | 05000237/LER-1977-019, Updated LER 77-019-00 for Dresden Unit 3 Regarding on 06/06/1977, During Routine Half Core Control Rod Drive (CRD) Scram Testing at 46% Power, CRD H-9 (Core Location 30-35) Was Responding Irregularly | Updated LER 77-019-00 for Dresden Unit 3 Regarding on 06/06/1977, During Routine Half Core Control Rod Drive (CRD) Scram Testing at 46% Power, CRD H-9 (Core Location 30-35) Was Responding Irregularly | | | 05000237/LER-1977-020, Regarding a Pin-Hole Leak in a Weld Crack on the 3A Moisture Separator Drain Tank Drain Line | Regarding a Pin-Hole Leak in a Weld Crack on the 3A Moisture Separator Drain Tank Drain Line | | | 05000237/LER-1977-021, /03X-1 for Dresden 3 Regarding a Pin Hole Leak Found in Minimum Flow Line from 3A Reactor Feedwater Pump (Line 3-3205C-6) | /03X-1 for Dresden 3 Regarding a Pin Hole Leak Found in Minimum Flow Line from 3A Reactor Feedwater Pump (Line 3-3205C-6) | | | 05000249/LER-1977-021, Regarding the Discovery of a Pin Hole Leak in the Minimum Flow Line from the 3A Reactor Feedwater Pump During a Reactor Shutdown | Regarding the Discovery of a Pin Hole Leak in the Minimum Flow Line from the 3A Reactor Feedwater Pump During a Reactor Shutdown | | | 05000249/LER-1977-022, Regarding Water Observed at the 6 Pipe Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted | Regarding Water Observed at the 6 Pipe Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted | | | 05000237/LER-1977-022, Regarding an In-Leakage Occurrence, Where Water Was Observed at the 6 Pip Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted | Regarding an In-Leakage Occurrence, Where Water Was Observed at the 6 Pip Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted | | | 05000237/LER-1977-022-03, /03X-1 on 770605:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings | /03X-1 on 770605:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings | | | 05000237/LER-1977-023, For Dresden Unit 2 Regarding Discovery of the 12% APRM Upscale Rod Block Trip Setting to Be at 12.5% for APRM Channel One Due to Setpoint Drift | For Dresden Unit 2 Regarding Discovery of the 12% APRM Upscale Rod Block Trip Setting to Be at 12.5% for APRM Channel One Due to Setpoint Drift | | | 05000237/LER-1977-024, For Regarding the Inoperability of the Unit 2/3 Diesel Generator for 25 Minutes on June 30, 1977 | For Regarding the Inoperability of the Unit 2/3 Diesel Generator for 25 Minutes on June 30, 1977 | | | 05000249/LER-1977-025, LERs 77-025-00, 77-026-00, 77-027-00 for Dresden Unit 3 Regarding Electromagnetic Relief Valves 3-203-3C and 3D, the Failure of 3D Electromatic Relief Valve, and the Failure of Electromatics 203-3D and 3E | LERs 77-025-00, 77-026-00, 77-027-00 for Dresden Unit 3 Regarding Electromagnetic Relief Valves 3-203-3C and 3D, the Failure of 3D Electromatic Relief Valve, and the Failure of Electromatics 203-3D and 3E | | | 05000237/LER-1977-026, Regarding the Discovery of Pressure Switch PS-263-51A to Activate at 614 PSI | Regarding the Discovery of Pressure Switch PS-263-51A to Activate at 614 PSI | | | 05000237/LER-1977-027, Regarding Failure of 46 Control Rod Drives to Fully Insert and Latch at Position 00 Following a Reactor Scram on July 9, 1977 | Regarding Failure of 46 Control Rod Drives to Fully Insert and Latch at Position 00 Following a Reactor Scram on July 9, 1977 | | | 05000237/LER-1977-028, Regarding Discovery of the Water Tight Buckhead Door Which Provides Flood Protection to the Ccsw Vault to Be Open | Regarding Discovery of the Water Tight Buckhead Door Which Provides Flood Protection to the Ccsw Vault to Be Open | | | 05000237/LER-1977-029-03, /03X-1 on 770802:during 1/2 Core Scram Test,Crds F-5 & H-7 Uncoupled When W/Drawn to Position 48.Caused by Unlatched Inner Filter & Abnormally Long Coupling Rod a Pull Test Has Been Incorporated Into Overhaul Procedure | /03X-1 on 770802:during 1/2 Core Scram Test,Crds F-5 & H-7 Uncoupled When W/Drawn to Position 48.Caused by Unlatched Inner Filter & Abnormally Long Coupling Rod a Pull Test Has Been Incorporated Into Overhaul Procedure | | | 05000237/LER-1977-029, Regarding the Control Rod Drives F-5 and H-7 Uncoupling and Overtravelling When Withdrawn to Position 48 Following Testing | Regarding the Control Rod Drives F-5 and H-7 Uncoupling and Overtravelling When Withdrawn to Position 48 Following Testing | | | 05000237/LER-1977-031, Regarding the Unit 2/3 Make-Up Demineralizer Acid and Caustic Day Tanks Overflowed While Being Filled Simultaneously Due to Operator Error | Regarding the Unit 2/3 Make-Up Demineralizer Acid and Caustic Day Tanks Overflowed While Being Filled Simultaneously Due to Operator Error | | | 05000249/LER-1977-032, Regarding a Surveillance Interval Discrepancy for the LPCI and Core Spray Pump and Valve Operability | Regarding a Surveillance Interval Discrepancy for the LPCI and Core Spray Pump and Valve Operability | | | 05000237/LER-1977-032, Regarding Failure of Motor Operated Suction Valve MO-2-1501-5A to a LPCI to Reopen Remotely from the Control Room | Regarding Failure of Motor Operated Suction Valve MO-2-1501-5A to a LPCI to Reopen Remotely from the Control Room | | | 05000249/LER-1977-033, Regarding an Occurrence Where APRM 4 Would Not Generate an Inop Until 13 LPRMs Were Bypassed | Regarding an Occurrence Where APRM 4 Would Not Generate an Inop Until 13 LPRMs Were Bypassed | | | 05000249/LER-1977-034, Regarding an Interruption in the Feedwater Flow Signal to the Circulation System | Regarding an Interruption in the Feedwater Flow Signal to the Circulation System | | | 05000237/LER-1977-034, /03L-0 for Dresden 2 Regarding Main Steam Line Isolation Switch 2-261-16D Initiation of a Group I Isolation Signal on Channel B | /03L-0 for Dresden 2 Regarding Main Steam Line Isolation Switch 2-261-16D Initiation of a Group I Isolation Signal on Channel B | |
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