/03L-0:on 771017,Channel 1 (RIC-281) Found to Trip at 132%.Caused by Instrument Drift.Trip Setpoint Readjusted to 115%.High Neutron Flux Monitor Testing Will Continue Monthly Per Dis 700-4,verifying Operability| ML19338E410 |
| Person / Time |
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| Site: |
Dresden  |
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| Issue date: |
11/03/1977 |
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| From: |
Lindberg C COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML19338E409 |
List: |
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| References |
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| LER-77-040-03L, LER-77-40-3L, NUDOCS 8009290533 |
| Download: ML19338E410 (3) |
|
LER-1977-040, /03L-0:on 771017,Channel 1 (RIC-281) Found to Trip at 132%.Caused by Instrument Drift.Trip Setpoint Readjusted to 115%.High Neutron Flux Monitor Testing Will Continue Monthly Per Dis 700-4,verifying Operability |
| Event date: |
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| Report date: |
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| 0101977040R03 - NRC Website |
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REPOHT DATE 60 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o j p l During monthly surveillance DIS 700-4 Channel #1 (RIC-281) found to trip at 132%.
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- o,3 i ; Tech Spec table 3.1.1.c requires high neutron flux trip of </-123% of scale.
Safety l i o,4 ; g significance minimal because remaining two channels (#3,#5) of "A" trip channel were l IOlsl I perable within required tech spec range (T.S.3.1).
"B" trip channel unaffected.
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!3 l0l] Cause due to instrument drift. Trip setpoint readjusted to 115%.
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ATTACHMENT TO LICENSEE EVENT REPORT 77-040/03L-0 COMMONWEALTH EDISON COMPANY (CWE)
DRESDEN UNIT 1 (ILDRS-1)
DOCKET # 050-0010 While performing high neutrop flux monthly surveillance DIS 700-4 Channel
- 1 (RIC 281) was found to trip at 132%. Three high neutron flux instrument channels are provided for each trip system.
High Neutron Flux Instrument Channels #1, #3, #5 operate contacts in the "A" trip channel and Instrument Channe?.s #2, #4, #6 operate contacts in the "B" trip channel. Tech Spec 3.1 maintains that a minimum of two channels per trip channel must be oper-able. The inability of Channel #1 to trip at the designated limit did not pose any safety implications because the remaining two channels (Ch #3, 5) of the "A" trip channel remained operable. The "B" trip channel was unaf-fected. The micromicroammeter is manufactured by General Electric Catclogue No. 534E745G4.
Tech Spec Table 3.1.1.C require a High Neutron Flux Trip of < 123% of scale. The Dresden setpgint is 114 to 116% increasing.
This is a repetitive occurrence as reported under 50-010/1977-3,12,13 and 31; 50-010/1976-8 and 18.
The trip setpoint was readjusted to 115%. The rause was attributed to instrument drift. The trip setpoints will continue to be tested per monthly surveillance DIS 700-4 to verify operability below the 123% Tech Spec Iimit.
In addition, previous drif t problems will be analyzed and a new setpoint determined to eliminate recurrence.
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NRC Foru 195
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.~ NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL ANCIDENT REPORT FROM Co::Inonwealth Edison DATE OF DOCUMENT James G. Keppler 11/03/77 Morris, Illinois 60450 B. B. Stephenson CATE RECEIVCD l
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Licensee Event Report (R0 50-010/77 40/03L.0) on 10/17/77 concerning the inability of J
Channel #1 to trip at the designated limit,....
while performing high neutron flux monthly surveillance DIS 700 4.....
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PLANT NAME: Dresden Unit No.1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND RJL-11/17/,77 DIRECTLY TO KREGER/J. COLLINS FOR ACTION /INFORMATION l 3 RANCH CHIEF:
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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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