LER-1977-015, Forwards LER 77-015/03X-1 |
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| 2371977015R00 - NRC Website |
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CommonweA Edison Dresden NuclearWwer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #78-1447 James G. Keppler, Regional Din:~ctor
- Directorate of Regulatory Operations - Region III.*
U.S. Nuclear Regulatory Commission 79-9 __ Roosevelt Road Glen Ellyn, IL : 60137.
Reportable Occurrence "Update" Rep~rt 77.,-.015/03X-l, Docket i/050-237 i.s hereby submitted ~o your office to update the cause description and final corr~ctive actions taken to. prevent recurrence.. Th:Ls event was reported* to your office under Dresden Nuclear Power. Stat;ion Techni.cal Specification 6.6.B.2.(b), ~onditions leading to operat~on ~n a.*
degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting c.ondition for operatiOn.
- ens on Superintendent Presden Nuci~ar Power*Station.
BBS/deo*
Enclosure cc:. Director. of Insp~ction' *& Enforcement
- Director* of Management Informad.on &
File/NRC Program Control
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P~OUS REPORT DATE 4/29/77 CONTROL BLOCK:
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!During routine startup operations, CRD*L-5 uncoupled and overtraveled when withdrawn
@ill. I to pos. 48.
L-5 immediately inserted and disarmed; Startup operations resumed after [QITI_jdeterminai::ion that L-S's pos. and core location did not adversely affect core symmetry~
[ill] jFollowing_startup overtravel check of L-5 proved satisfactory, verifying it was re-l
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CRD uncouplings have occurred previously.
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!Unlatched inner filter and abnormally long uncoupling rod resulted in unc0upling of QJJJ I CRD L-5 during startup; Since earlier overhaul" of CRD L-5 on-Jan. 1975. *a i:mll.:test*
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i ATTACHMENT TO LICENSEE EVENT REPORT 77-0l5/03X-l
- COMHONWEALTH EDISON COMPANY (CWE)
DRESDEN UNIT-2 (ILDRS-2)
DOCKET ii 050.:...237 During routine start.:...up operations, control rod drive (CRD) t-5 was found to uncouple and overtravel when withdrawn to position 48.
L-5 was immediately inserted. and electrically disarmed.
Reactor start...:.up operations were resumed after.it had been determined that *the position and core location of the-L-5 control rod did not adversely affect core symmetry; At a reactor power level of approximately 30%, L-5 was withdrawn t~ position 48 and checked for overtravel.
The overtravel :
check proved s~tisfactory,' verifying that CRD. L-5 was recoup led and operaole.
Control rod drive/blade uncoupling incidents had occurred several times *in the past.
Symptom and performance evaluations indicated that: a loosened CRD inner.
filter could have caused the blade and drive to. uncouple at the fully withdrawn position.
Loosening of the filter could have resulted from a comoination of improper.installation and latching spring fatique.
It was aiso determined that a. loosened filter could not exert. sufficient
- pres*sure.to uncouple: the olade except when* the drive was fully withdrawn to position 48; upon insertion, the f>lade and drive automatically..
recoup led, Because the potential for uncoupling the blade existed. only*
- wfi.en tiie drive -t.ras. fully withdrawn, the.saf~ty irp.plications of this event were minimal.
As a precautionary measure, an operating order was. issue.cl to ~nsure that.*
- a coupling check was* performed. whenever drive L-5.was withdrawn to
- On Novemf>er 30, 1977.CRD L-5 was disassemoled and inspected: p~~ Control Rod Drive Inspection and Maintenance Procedure DMP 209,
comprehensive inspection a special operating procedure (SOP 216) was
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Upon inspection it was found that the inner filter was unlatched. *:"tri"' *-*.'
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addition the* distance between the CRD flange and the end of the fully.
- seated uncoupling rod was af>normally long (173.406 + 0.750").* The abnormai length coupled with an unlatched inne.r filter resulted.in the uncoupling of the CRD.
CRD L-5 had oeen overha.uled in January; 1975.
Since May, 1975 a 20 to 30 pound pull test on the inner filter has been incorporated in the overhaul
- and reassembly procedure, Control Rod Drives overhauled and reassembled*
- under this revised procedure have not experienced uncoupling.
The revised procedure coupled with improved Quality Control coverage of CRD overhaul and reassembly are believed to be adequate to prevent. future* similar ev*ents.
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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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