LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted |
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D DA/RYLAND h
[k COOPERAT/VE
- PO BOX 817 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN 54601 (608) 788-4000 November 20,-1981.
In reply, please refer to LAC-7932 DOCKET NO. 50-409 f
[V d !N n7 q f h,T/
h Mr. James G.
Keppler, Regional Director U.
S. Nuclear Regulatory Commission w
i Directorate of Regulatory Operations
/E7 Sk JU Lj)
Q' Region III J_'
DEC9 1981 5 ~
l 799 Roosevelt Road.
,y Glen Ellyn, Illinois 60137 T
""foT j$^*8 ;h/
G N/
SUBJECT:
DAIRYLAND POWER COOPERATIVE
\\Q (LACBW{3t) g. [
LA CROSSE BOILING WATER REACTOR DPR-4 PROVISIONAL OPERATING LICENSE NO.
l REPORTABLE OCCURRENCE NO. 81-11
REFERENCES:
(1)
LACBWR Technical Specifications, Section 6.9.1.9.b t
(2)
LACBWR Technical Specifications, Section 4.2.2.18 (3)
LACBWR Technical Specifications, Section 4.2.18.1 i
Dear-Mr. Keppler:
In accordance with Reference 1, this is to notify you of a plant condition which led to operation in a degraded mode permitted by a limiting condition for operation.
At 1400 on October 31, 1981 with the reactor in Operating Condition 1 at 85% Rated Thermal Power, the LACBWR Mechanical Engineer, who was the Duty Shift Technical Advisor, observed that the radiator hose on the IB HPSW (High Pressure Service Water) Diesel Engine was slightly cracked during a random tour of the plant.
In his opinion, the magnitude of the crack was such that the hose would have ruptured after a couple hours of diesel operation.
The IB HPSW Pump Control Switch in the Control Room was placed in i
the "OFF" position for approximately 10 minutes while the radiator hose was. replaced.
The diesel was then test run for three minutes to check for hose leakage and water level in the radiator.
After i
a satisfactory inspection, the control switch was returned to the
" AUTO" mode.
j
_1_
gMf8l DEN 2 198l' 8112100307 811120 PDR ADOCK 05000409 7 31.
S PDR
~
MMY
Mr. James G.
Keppler, Regional Director November 20, 1981 U.
S. Nuclear Regulatory Commission LAC-7932 On November 3, 1981, the hoses on both the 1A and 1B HPSW Diesels were inspected and one hose which showed signs of aging was replaced on the 1A HPSW Diesel.
A specific visual inspection of the condition of all hoses has been incorporated into the monthly Preventive Maintenance Program.
A Licensee Event Report (Reference: Appendix A, Regulatory Guide 1.16, Revision 4) is enclosed.
Should you have any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE
.IA Frank Linder, General Manager c
FL:LSG:eme Attachment cc:
Director, Office of Inspection and Enforcement (30)
U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 Director, Office of Management Information (3) and Program Control U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 NRC Resident Inspector _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
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| 05000409/LER-1981-001, Forwards LER 81-001/02L-0 | Forwards LER 81-001/02L-0 | | | 05000409/LER-1981-001-02, /02L-0:on 810201,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Disconnected.Caused by Disconnect Switch Opened Due to Operator Error.Two Operators to Operate Switching Order | /02L-0:on 810201,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Disconnected.Caused by Disconnect Switch Opened Due to Operator Error.Two Operators to Operate Switching Order | | | 05000409/LER-1981-001-03, /03L-0:on 810116,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Disconnected.Caused by Maint on Main Transformer Airbreak Switch 25NA1 Due to Ice in Swivel Joint.Ice Melted | /03L-0:on 810116,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Disconnected.Caused by Maint on Main Transformer Airbreak Switch 25NA1 Due to Ice in Swivel Joint.Ice Melted | | | 05000409/LER-1981-002, Forwards LER 81-002/02L-0.Detailed Event Analysis Submitted | Forwards LER 81-002/02L-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-002-02, /02L-0:on 810201,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Was Disconnected.Caused by Operator Opening Incorrect Disconnect Switch.Switch Reclosed.Operators Retrained | /02L-0:on 810201,independent Circuit Between Offsite Transmission Network & Onsite Power Distribution Sys Was Disconnected.Caused by Operator Opening Incorrect Disconnect Switch.Switch Reclosed.Operators Retrained | | | 05000409/LER-1981-003-03, /03L-0:on 810202,gross Alpha Activity of Primary Coolant Sample Exceeded Tech Spec.Caused by Degraded Fuel Cladding During Previous Fuel Cycles.Primary Purification Sys Operation Reduced Concentration to Allowable Level | /03L-0:on 810202,gross Alpha Activity of Primary Coolant Sample Exceeded Tech Spec.Caused by Degraded Fuel Cladding During Previous Fuel Cycles.Primary Purification Sys Operation Reduced Concentration to Allowable Level | | | 05000409/LER-1981-003, Forwards LER 81-003/03L-0.Detailed Event Analysis Encl | Forwards LER 81-003/03L-0.Detailed Event Analysis Encl | | | 05000409/LER-1981-004, Forwards LER 81-004/03L-0.Detailed Event Analysis Also Submitted | Forwards LER 81-004/03L-0.Detailed Event Analysis Also Submitted | | | 05000409/LER-1981-004-03, /03L-0:on 810309,during Condition 3,480-volt Diesel Bldg Essential Switchgear Bus 1B Was Energized from 1B Emergency Diesel Generator for Approx 25 Minutes W/Control Power Key in on Position | /03L-0:on 810309,during Condition 3,480-volt Diesel Bldg Essential Switchgear Bus 1B Was Energized from 1B Emergency Diesel Generator for Approx 25 Minutes W/Control Power Key in on Position | | | 05000409/LER-1981-006-01, /01T-0:on 810518,during Installation of Attachment on Containment Pressure Sensing Line,High Containment Bldg Pressure Starting Signal to HPCS Pump 1B,auxiliary Cooling Sys Pump & AC Valve Was Isolated.Procedures Not Followe | /01T-0:on 810518,during Installation of Attachment on Containment Pressure Sensing Line,High Containment Bldg Pressure Starting Signal to HPCS Pump 1B,auxiliary Cooling Sys Pump & AC Valve Was Isolated.Procedures Not Followed | | | 05000409/LER-1981-006, Forwards LER 81-006/01T-0.Detailed Event Analysis Encl | Forwards LER 81-006/01T-0.Detailed Event Analysis Encl | | | 05000409/LER-1981-007-01, /01T-0:on 810601,during Initial Integrated Sys Test W/Plant Shut Down,Emergency Svc Water Supply Sys Did Not Produce 900 Gpm at 90 Psig,As required.Three-way Distributor Fabricated.Sys Retested Satisfactorily | /01T-0:on 810601,during Initial Integrated Sys Test W/Plant Shut Down,Emergency Svc Water Supply Sys Did Not Produce 900 Gpm at 90 Psig,As required.Three-way Distributor Fabricated.Sys Retested Satisfactorily | | | 05000409/LER-1981-007, Forwards LER 81-007/01T-0 | Forwards LER 81-007/01T-0 | | | 05000409/LER-1981-008-01, /01T-0:on 810729,main Steam Bypass Valve Did Not Open During Momentary Pressure Spikes Approx 20 Psi Above Nominal Reactor Pressure.Caused by Decrease in Pressure Prior to Valve Opening Due to Short Duration & Spikes | /01T-0:on 810729,main Steam Bypass Valve Did Not Open During Momentary Pressure Spikes Approx 20 Psi Above Nominal Reactor Pressure.Caused by Decrease in Pressure Prior to Valve Opening Due to Short Duration & Spikes | | | 05000409/LER-1981-008, Forwards LER 81-008/01T-0.Detailed Event Analysis Submitted | Forwards LER 81-008/01T-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-009-03, /03L-0:on 810917,upscale Trip Setpoint on Nuclear Instrument Channel 7 Found in Excess of Tech Spec Limit. Cause Not Determined.Setpoint Reset | /03L-0:on 810917,upscale Trip Setpoint on Nuclear Instrument Channel 7 Found in Excess of Tech Spec Limit. Cause Not Determined.Setpoint Reset | | | 05000409/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-010, Forwards LER 81-010/01T-0.Detailed Event Analysis Submitted | Forwards LER 81-010/01T-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-010-01, /01T-0:on 810923,during Normal Operation Mechanical Interlock Preventing Simultaneous Opening of Both Doors of Containment Bldg Personnel Airlock Failed.Caused by Worn or Misadjusted Actuating Mechanism.Drawings Encl | /01T-0:on 810923,during Normal Operation Mechanical Interlock Preventing Simultaneous Opening of Both Doors of Containment Bldg Personnel Airlock Failed.Caused by Worn or Misadjusted Actuating Mechanism.Drawings Encl | | | 05000409/LER-1981-011-03, /03L-0:on 811031,observed That Radiation Hose on High Pressure Svc Water Diesel Engine 1B Was Slightly Cracked.Cause Not Stated.Hose Replaced & Diesel 1B Tested Satisfactorily | /03L-0:on 811031,observed That Radiation Hose on High Pressure Svc Water Diesel Engine 1B Was Slightly Cracked.Cause Not Stated.Hose Replaced & Diesel 1B Tested Satisfactorily | | | 05000409/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-012-03, /03L-0:on 811101,gasoline Levels in Three Emergency Svc Water Supply Sys Gasoline Engine Driven Pumps & Spare Pump Found to Be Less than 5 Gallons During Monthly Insp.Cause Unknown.Gasoline Added to Fill Tanks | /03L-0:on 811101,gasoline Levels in Three Emergency Svc Water Supply Sys Gasoline Engine Driven Pumps & Spare Pump Found to Be Less than 5 Gallons During Monthly Insp.Cause Unknown.Gasoline Added to Fill Tanks | | | 05000409/LER-1981-012, Forwards LER 81-012/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-012/03L-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-013-03, Following scram,1B 2,400-volt Bus Reserve Feed Breaker Did Not Close Automatically.Cause Undetermined.Reserve Feed Breaker Control Switch Flagged to Trip Position | Following scram,1B 2,400-volt Bus Reserve Feed Breaker Did Not Close Automatically.Cause Undetermined.Reserve Feed Breaker Control Switch Flagged to Trip Position | | | 05000409/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Submitted | Forwards LER 81-013/03L-0.Detailed Event Analysis Submitted | | | 05000409/LER-1981-014-03, /03L-0:on 811223,following Scram,Offsite Transmission Network Did Not Automatically Supply Onsite Power Distribution Sys.Cause Undetermined.Transformer Breaker Closed | /03L-0:on 811223,following Scram,Offsite Transmission Network Did Not Automatically Supply Onsite Power Distribution Sys.Cause Undetermined.Transformer Breaker Closed | | | 05000409/LER-1981-014, Forwards LER 81-014/03L-0 & Updated LER 81-013/03X-1. Detailed Event Analysis Encl | Forwards LER 81-014/03L-0 & Updated LER 81-013/03X-1. Detailed Event Analysis Encl | | | 05000409/LER-1981-015, Forwards LER 81-015/01T-0.Detailed Event Analysis Encl | Forwards LER 81-015/01T-0.Detailed Event Analysis Encl | | | 05000409/LER-1981-015-01, /01T-0:on 811224,following Reactor Scram,Temp of 1B Forced Circulation Loop Piping Decreased Below Tech Specs Limit.Caused by Inoperation of Pump Due to Seal Problems & Lack of Monitoring.Personnel Reinstructed | /01T-0:on 811224,following Reactor Scram,Temp of 1B Forced Circulation Loop Piping Decreased Below Tech Specs Limit.Caused by Inoperation of Pump Due to Seal Problems & Lack of Monitoring.Personnel Reinstructed | |
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