/03L-0:on 771023,water Leaked to C Holdup Tank & Ground During Normal U-1 Radwaste Operation.Caused by Scratched Valve V3 & V45 Seats & Worn Manhead Gasket.Valve Seats Lapped,Manhead Gasket Replaced & Hatch Tightened| ML19338E407 |
| Person / Time |
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| Site: |
Dresden  |
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| Issue date: |
11/23/1977 |
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| From: |
Mohr T COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML19338E406 |
List: |
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| References |
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| LER-77-041-03L, LER-77-41-3L, NUDOCS 8009290531 |
| Download: ML19338E407 (3) |
|
LER-1977-041, /03L-0:on 771023,water Leaked to C Holdup Tank & Ground During Normal U-1 Radwaste Operation.Caused by Scratched Valve V3 & V45 Seats & Worn Manhead Gasket.Valve Seats Lapped,Manhead Gasket Replaced & Hatch Tightened |
| Event date: |
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| Report date: |
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| 0101977041R03 - NRC Website |
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U.S. NUCLEAR REGULAT5GY COMMISSION (7 M )
iP c.lCENSEE EVENT REPORT-w "CONTi?OL BLOCK:
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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74
'S REPORT DATE So EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h iei2l l During normal operations of U-l Radwaste, U-l neutralizer was being pumped to B SSG l
,3,3; j waste collector. Valves V3 and V45 leaked 7000 gal of H20 to empty C heldup
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- l l tank.
Worn gasket on a manhead allowed approx 12 gal of H20 contain-l t O lsi l ing 2.5 E-4 Ci to leak to ground. Some leakage was collected and returned to U-l l
10teIl neutralizer. No leakage reached uncontrolled areas. Leakage into controlled areas l
1017 l l vas cleaned. The event posed no threat to public safety.
Minor spills occurred]
ioisl l previously 50-010/70-1 and 50-010/77-1.
I SYSTEM
CAUSE
CdfSE COMP.
VALVE code CODE SUBCODE COMPONENT CODE SUBCODE SUSCODE l0l9l l Ml Alh Wh (_Bjh I V l A l L l V l E l X lh l Cl@ l Dl @
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9 10 11 12 13 18 19 20 SE QUENTI AL OCCURRENCE REPORT REVISION LE R 'RO EVENT YE AR REPORT NO.
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33 i4 3h 36 32 40 41 42 43 44 47 CAUSECESCRIPTION AND CORRECTIVE ACTIONS h IllOl t h?ve seats in valves V3 and V45 were scratched, causing leakage to C holdup tank l
r i (1 l l above the lower manhead. The valves seats were lapped.
The manhead gasket was re-l
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44 4s 46 so AMOUNTgF ACTIVITY @ l RELEASED OF RELE ASE LOC ATION OF RELE ASE 1f 16 1 [1_l h [_P,j @ l 2.5 x 10-Curies l
Ground adiacent to "C" holdun tank l
8 9 10 11 44 45 80 PERSOMEL EXPOSURES NUMBE R TYPE
DESCRIPTION
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ATTAfmMENT TO LICENSEE EVENT REPORT 77-041/03L-0 COMMONWEALTH EDISON COMPANY (CWE)
DRr.SDEN UNIT 1 (ILDRS-1)
DOCKET # 050-010 Unit 1 neutralizer was being pumped to B-SSG waste collector at 0035 on 10/23/77. At the same time B-SSG waste collector was being pumped to Unit 2/3 radwaste B-neutralizer. At 0250 the operator discovered water The leaking from the lower manhead of C-holdup tank onto the ground.
release area was posted and covered.
Samples were taken for isotopic Valve V-3 and V-45 had leaked because of scratched valve seats, analysis.
allowing approximately 7000 gallons of water to enter C - holdup tank.
The level was raised This was determined from the increase in tank level.
to six inches above the lower manhead. A worn gasket on th" manhead per-mitted water to leak to the ground. A bucket vss placed unour the leak and leakage rate was determined to be approximat.ely 1/8 gallon per minute.
Using the distance of the bottom of the manhead to the final fluid level and assuming the tank was filled at a " constant rate, it was determined that the tank had been leaking.for approximately 96 minutes.
Therefore, the water which was released amounted to approximately 12 gallons.
The activity of the water was found to be 5.5 pCi/L.
the total release amounted to 2.5 x 10-4 Ci.
The water in C - holdup
. Thus, tank was pumped to Unit 2/3 radwaste B-neutralizer. The water collected by bucket was returned to Unit 1 neutralizer. The release was contained in a controlled area and no water was released to the river.
The valve seats were repaired and the manhead gasket was replaced.
Safety significance of this event was minimal because of the small amount of the release.
Previous occurrences were reported under R.O. #50-010/1976-1 and 50-010/1S77-1.
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l' NRC DISTRIZUTION pen PART 50 DOCKET MATERIAL INCIDENT REPORT i
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FROM:
oATE OP coCUMENT Comonwealth Edison Company 11/23/77 Mr. James G. Keppler Morris, Illinois e4TE RECEivEm B. B. Step'tenson 12/09/77 i
INPUT PoRM NUMBER CP CCPIES RECEIVEo
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Licensee Event Report (R0 50-010/77-041/-031,
- 0) on 10/23/77 concerning valve seats in valves V3 & V45 being scratched, causing leakage to C holdup tank above the lower i
manhead.....
i i
l PLANT NAME: Dresden Unit No.1 l
RJL 12/09/77 (1-P)
(1-P)+(1-P)
NOTE: IF PERSONNEL EXPOSURE IS INVOLVED l
SEND DIRECTLY TO IGiEGER/J. COLLINS
/ WWh FOR ACTION /INFORMATION s
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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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