LER-1981-012, Forwards LER 81-012/03L-0.Detailed Event Analysis Submitted |
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I D DA/RYLAND h
[k COOPERAT/VE
- 2615 EAST AV SOUTH LA CROSSE. WISCONSIN 54601 (608) 788-4000 November 23, 1981 In reply, please refer to LAC-7934 DOCKET NO. 50-409 Mr. James G.
Keppler, Director-U.
S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 D
LA CROSSE BOILING WATER REACTOR (LACBWR) b b Ilgjk I'[f
SUBJECT:
DAIRYLAND POWER COOPERATIVE f
PROVISIONAL OPERATING LICENSE NO. DPR-45 2
DEC9 I38Ih "
REPORTABLE OCCURRENCE NO. 81-12 r3; u,s, a c m, w, ;;
REFERENCE:
(1) LACBWR Technical Specifications, Section 6.9.1.9.b V)
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(2) LACBWR Technical Specifications, Section 4.2.21.1 (3) LACBWR Technical Specifications, Section 5.2.21.1.2
Dear Mr. Keppler:
In accordance with Reference 1, this is to inform you of an event which led to operation in a degraded mode permitted by a limiting condition for operation.
Reference 2 requires the Emergency Service Water Supply System (ESWSS) to be operable during Operational Conditions 1, 2 and 3 with at least three gasoline engine-driven pumps.
Reference 3 requires that each ESWSS pump be demonstrated operable at least once per 31 days by verifying that the fuel tank contains at least 5.0 U.
S. gallons of gasoline.
At 1100, on November 1, 1981, in Operating Condition 1, with the reactor at 85% Rated Thermal Power, the gasoline levels in the three ESWSS pumps and the spare pump were found to be less than 5 gallons during the monthly inspection.
The level of gasoline in each engine was:
Engine No. 1 5 3/4 in.
(3.7 gal.)
Engine No. 2 7 1/8 in.
(4.9 gal. )
Engine No. 3 6 1/2 in.
(4.25 gal. )
Engine No. 4 6 3/4 in.
(4.5 gal. )
-*fi 8112100295 811123 DECI 2 19 811 PDR ADOCK 05000409 4
_-e S
PDR P " ~-
e Mr. James G.
Keppler, Director' November 23, 1981 U.
S.
Nuclear Regulatory Commission LAC-7934 Gasoline was added to fill each tank at 1210 on November 1,
- 1981, returning the pumps to operable status.
The previous month's inspection had been performed October 1, 1981.
The level in the gasoline tanks was satisfactory on that date and during the September 1, 1981 inspection.
On October 6, 1981 the ESWSS Pumps Semi-Annual Test was performed on Pump Unit #2.
The tank.was refilled upon completion of the test. -The pumps were not utilized in any other manner during the month of October.- The quarterly fuel change of ESWSS Pumps had last-been performed on August 17, 1981.
No definite explanation could be determined for the lower-gasoline level in the ESWSS pump tanks.
An experiment conducted to determine the expansion and contraction of gasoline with change in' temperature demonstrated contraction was not sufficient explanation.
The Emergency Service Water Supply System was installed earlier this year to supply an additional cooling source to the reactor due to the potential for site liquefaction during a seismic event and subsequent loss of the Alternate Core Spray Pumps located in the Crib House.
Utilizing the maximum design fuel consumption rate of the pumps there was enough fuel in the tanks of November 1, 1981 to fulfill the water demand for an above core break.
If a below core break had occurred during a seismic event that resulted in site lique-faction, approximately the same number of gasoline refills (4 per pump, 3 pumps) would have been needed on November 1, as would be if there had been 5 gallons of gasoline in each tank.
Therefore, the safety significance of the low gasoline levels is minimal.
There was no LOCA or seismic event on November 1, 1981.
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 hWb y
Frank Linder, General Manager FL:LSG:eme Attachment r
D Mr. James G.
Keppler, Director November 23, 1981 U. S.
Nuclear Regulatory Commission LAC-7934 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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