ML20135C390

Annual Rept for 1996 - Rept of Changes,Tests & Experiments

ML20135C390
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/31/1996
From:	Berg W, Johnsen M DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LAC-13580, NUDOCS 9703040011
Download: ML20135C390 (13)

Text

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I D DA/RYLAND l

1. COOPERAT/VE

• 3200 E/.ST AVE. SO.

• P.O. BOX 817

• LA CROSSE. WISCONSIN 546 I

(608) 788-4000 FAX NO. (608) 787-1420 ,

WILLIAM L. BERG February 14,1997 I Gsneral Manager l

In reply, please l refer to LAC-13580 '

DOCKET NO. 50-409 i

Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR)

Possession-Only License No. DPR-45 ADnual Report for 1996 - Reoort of Changes. Tests and Experiments

REFERENCES:

(1) LACBWR Technical Specification, Section 6.8.1.1 (2) 10 CFR 50.59(b)

In accordance with Reference 1, we are submitting the Annual Report covering the radiological exposure summary.

- Also included are brief descriptions of facility changes, including summaries of their safety l' evaluations, as required by Reference 2. There were no experiments or tests conducted during 1996.

If there are any questions concerning this report, please contact us.

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Sincerely, DAIRYLAND POWER COOPERATIVE 9703040011 961231 ADOCK 05000409 b

PDR R PDR "

William L. Berg, General Manager - p

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9 DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS 1996 FACILITY CHANGES The following Facility Changes, which did not require prior NRC approval, were physically completed in 1996. A summary of the safety evaluations performed in accordance with 10 CFR 50.59 type criteria is included. It was determined that there were no unreviewed safety questions for these facility changes.

18-96-05 INSTALL BULKHEADS IN CRIBHOUSE INTAKE Two steel bulkheads were installed, between existing H-piles, to facilitate isolation of the screenhouse bays and forebay from the river during zebra mussel control treatments. One bulkhead has an opening of sufficient size to accommodate plant river water needs and can be closed with the installation of a sliding steel panel. This modification is an integral part of the maintenance strategy for controlling the zebra mussel infestation, and to assure a reliable river water supply.

44-95-03 REMOVE ALL EQUIPMENT MOUNTED ON CONTROL PANEL "F" Removed were the instruments and controls for in-Core Flux monitoring system located in the Control Room. The equipment, located in the containment building, had been previously removed. This Facility Change completed removal of an obsolete system and has no effect on structure, systems or components associated with SAFSTOR.

45-94-17 PLANT EFFLUENT AIR MONITORING EQUIPMENT Replaced existing Stack, Containment Building Ventilation Exhaust and Lab Hood monitoring equipment with a more modern system and components, with enhanced data collection. Alarm and isolation functions were retained.

46-95-06 DISCONNECT UNNECESSARY ALARMS FROM CONTROL ROOM PANELS "A" & "B" Alarms associated with permanently shutdown equipment were removed from service to reduce the number of meaningless alarms. Alarms applicable to the SAFSTOR status of the plant remain in service and are now more easily identified.

DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS - (cont'd) 48-93 09 REMOVE AGS TRANSMITTERS AND PANEL FROM TUNNEL ADD.1 The Automatic Gain Control System (AGS) adjusted the output gain of ,

the Nuclear Instrument Power Ranges to correct the non-linearity l associated with out-of-core power instrumentation based on thermal power. The entire Automatic Gain System was removed under addenda i to this facility change, including all components located in the Control  !

Room. Its removal has no effect on structures, systems or components .

associated with SAFSTOR. I 50-04 18 REMOVE REACTOR WATER LEVEL SIGHT GLASS ADD.1 4 The Reactor Water Levelindicating Sight Glass and level transmitter piping were removed. This removal has no effect on structures, systems, or components associated with SAFSTOR.

53-93-08 REMOVE EMERGENCY CORE SPRAY SYSTEM I The High Pressure Core Spray system equipment located outside the l biological shield was removed, including the Emergency Spray Pumps, instrumentation, piping and valves. Its removal has no effect on structures, systems, or components associated with SAFSTOR. The low pressure supply is retained to provide Reactor Vessel refill capability.

59-93-01 REMOVE SHIELD COOLING SYSTEM The need for the cooling provided by this system ceased with the l permanent shutdown of the reactor. All system components outside the '

biological shield were removed. There is no effect on structures, l systems or components associated with SAFSTOR.

60-93-01 REMOVE BORON INJECTION SYSTEM The need for the ability to inject a boron solution into the reactor vessel 1 for reactivity control no longer exists. The system was removed in  !

conjunction with the High Pressure Core Spray System removal, and its removal has no effect on structures, systems or components associated with SAFSTOR.

62-91-13 PRIMARY SYSTEM RELIEF VALVES Over-pressure protection of the Primary system is no longer needed or required. The primary system relief valve assemblies have been removed. This removal has no effect on design or function of any structures, systems or components associated with SAFSTOR.

70-95-05 REPLACE 1 A AIR COMPRESSOR. INSTALL NEW FILTER AND DRYER The 1 A Station Air Compressor was replaced with one sized to the air demand of the shutdown plant. New air filters and control air dryer were installed as part of this upgrade.

l DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS - (cont'd) 73-94-22 MODIFY ALARM C-8-2 "RX VENT EXHAUST FLOW (LO)"

The Ventilation Exhaust Fan is rarely placed in operation, causing this alarm to be locked in continuously. The alarm was modified to annunciate when the fan is running, making it more meaningful to the operator and removing a nuisance alarm. The alarm window now reads "RX VENT EXHAUST FAN RUNNING."

74-95-41 REDESIGN RATING OF FUSES IN 1B 480 V ESSENTIAL BUS I POTENTIAL TRANSFORMER CIRCUlT The 1B 480-Volt Essential bus potential transformer high-side fuses were increased from 3 amps to 5 amps to improve protection from nuisance voltage spikes to improve reliability of the bus. i 92-96-03 A.C. TURBINE BEARING OIL PUMP MOTOR ABANDONMENT IN PQQE The A.C. Turbine Bearing Oil Pump Motor winding is shorted to grounu.

The turbine oil system is no longer used; power leads were lifted to make certain that this equipment would not be inadvertently energized. This j has no effect on any plant related structures, systems, or components i associated with SAFSTOR. I The following Facility Changes, which did not require prior NRC approval, were physically completed before 1996 but, due to local variations in the i interpretation of the term " physically completed," have not been included in previous ,

annua! reports. " Physically completed"is now defined and this milestone .3 now tracked in a Facility Change database. Comparison of the database and Annual j Reports to the NRC identified the following to be reported: l 1995 37-95-22 REMOVE DEW CELL RECORDER The field devices that provided inputs to this recorder had been removed under a previous facility change, leaving this recorder unused and unnecessary, its removal has no effect on structures, systems, or components associated with SAFSTOR.

47-94-04 CONSOLIDATION OF TEMPERATURE MONITORING POINTS The remaining operational recorder points on several of the older control room temperature recorders were moved to the newer and more reliable VideoGraphics recorder.

l DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS - (cont'd) i l

1994 50-93-17 REMOVAL OF REACTOR WATER LEVEL STANDPIPE 4 THERMOCOUPLES AND RECORDER The reactor water level standpipe thermocouples and recorder were no l longer used and their removal has no effect on structures, systems, or components associated with SAFSTOR.

1993 l

21-93-06 TURBlNE SHIELD WALLS j The removable biological shield wall sections around the steam turbine  !

were taken out and disposed of. This has no effect on any plant-related structures, systems, or components associated with SAFSTOR.

52-92-21 SEAL INJECTION MAKEUP HEATER The need for heating makeup water to the sealinjection system ceased with the permanent shutdown of the reactor; this unneeded heater was l removed. There is no effect on structures, systems, or components  !

associated with SAFSTOR.

67-93-08 DEMINERALIZED VIRGIN WATER TANK LO LEVEL ALARM The Technical Specification requirement for the minimum amount of stored water was reduced from that required during plant operation. The alarm setpoint was lowered to reflect current plant conditions, eliminate a nuisance alarm, and make the alarm more meaningful to the operators.

1992 32-92-10 CASK CRASH BEAMS These beams were designed to protect the Lower Control Rod Drives in a postulated cask-drop accident. They were removed to provide access for the removal of Lower Control Rod Drives, and the removal has no effect on structures, systems, or components associated with SAFSTOR.

37-91-16 TYPE "A" INTEGRATED LEAK RATE TEST SYSTEM Type "A" testing of the Containment Building is not required and the unused containment building test panels were removed. This has no effect on design or function of any structures, systems, or components associated with SAFSTOR.

37-92-17 CONTAINMENT BUILDING PENETRATION SHIELD With the permanent shutdown of the reactor, there no longer exists the possibility of an Alternate Core Spray System line break, making the penetration area spray shields unnecessary. They have been removed to afford safer access to the electrical penetrations.

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- DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS - (cont'd)

F l 44-91-02 INCORE FLUX MONITORING SYSTEM Traversing Incore Neutron detectors had previously been removed. This facility change removed the mechanical drives and has no effect on structures, systems, or components associated with SAFSTOR.

i 63-86-03 CONDFNSATE DEMIN. SYSTEM

Unused and unneeded condensate domineralizer resin regeneration

equipment, including acid and caustic pumps and tanks, was removed.

l Its removal has no effect on structures, systems, or components associated with SAFSTOR.

67-91-06 REMOVE 8000-GALLON ACID STORAGE TANK The bulk sulfuric acid storage tank which had been the supply for the Make-up Domineralizer and Condensate Demineralizer systems was removed. Its removal has no effect on structures, systems, or components associated with SAFSTOR.

91-93-04 INSTALL MONITORING BOX FOR ZEBRA MUSSELS IN CRIBHOUSE As part of Environmental Department's program for zebra mussel control, a sampling box to monitor population and growth was installed in the Crib House. River water is supplied by a small side stream off the Low Pressure Service system.

93-92-01 CONTROL AIR Oil REMOVAL FILTER An unused filter assembly was removed to permit freer movement in the area next to the control air dryers, and its removal has no effect on structures, systems, or components required for SAFSTOR.

1988 93-92-02 WASTE WATER RETENTION TANK DISCHARGE AUTO VALVE TRAP This facility change installed a moisture trap in the air supply line to the pneumatically operated automatic isolation valve on the retention tank i pump discharge to protect the valve from potential moisture accumulation at this remote point in the air system.

1987 70-86 03 SUPPLY 1 A AIR COMPRESSOR SOLENOID POWER FROM 1 A SIDE OF ELECTRICAL ' _ .NT The control solenoids for both station air compressors had a common power supply on the 1B side of the electrical plant. To increase reliability, the power for the 1 A Air compressor solenoids was taken from the 1 A side of tha electrical plant.

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i DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS - (cont'd)

'T 1986 30-86-02 CUT AND PLUG UNUSED REACTOR LEVEL PROBES During " Initial Tests at increasing Power" the reactor gauge glass, control room level indications and the two-phase interface level were inter-calibrated with the in-vessel probes. One Reactor Vessel Water level probe was retained as a backup means of obtaining a primary sample.

The remaining were cut and capped to eliminate potential sources of primary coolant leakage.

, 78-86-11 1B EMERGENCY DIESEL GENERATOR OUTPUT BREAKER 452-EGB i installation of contact 13/14 in the auto-close portion of the breaker-close circuit to improve manual operation of the breaker when the engine is running. This change will allow resetting the anti-pump circuit without securing the Diesel Generator.

1985 i 92-83-02 TURBINE LUBE OlL A locked closed bypass valve was installed around the turbine relay oil i filters, to facilitate resetting relay oil during cold start-up, to protect the i filter from high differential caused by the initial in-rush flow.  !

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l TESTS There were no tests conducted during 1996.

I EXPERIMENTS i

There were no experiments conducted during 1996, i

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1996 ~

APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION Number ofPersonnel(>100 mrem) TotalMan-Rem Station - . .. Utility Contract .- Station Utihty  ? Contract Work & Job Function . Employees (Employees Workers and Employees . Employees Workers and

- Others Others REACIDR OPERATIOiM/c'JRVEILLANG Maintenance Personnel 1 0 0 0.382 0.000 0.033 Operating Personnel 0 0 0 0.441 0.000 0.000 Health Physics Personnel 0 0 0 0.211 0.000 0.000 Supervisory Personnel 2 0 0 0.313 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 ROLTTINE MAINTENANG Maintenance Personnel 1 0 0 0.263 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 IIcalth Physics Personnel 0 0 0 0.000 0.000 0.000 Supenisory Personnel 0 0 0 0.001 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 INS 15RVIG INSPECTION Maintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supenisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANG Maintenance Personnel 2 0 0 0.408 0.000 0.097 Operating Personnel 2 0 0 0.347 0.000 0.000 IIcalth Physics Personnel 0 0 0 0.002 0.000 0.000 Supervisory Personnel 0 0 0 0.035 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.010

APPENDIX A- (cont'd) .

1996 Number ofPersonnel(>100 mrem) TotalMan-Rem Station Utility Contract Station . Utility Contract .

Work & Job Function Employees Employees Workers and ' Employees Employees Workers and Others Others WASTE PROCESSING hiaintenance Personnel 4 0 0 0.870 0.000 0.000 Operating Personnel 0 0 0 0.098 0.000 0.000 Health Physics Personnel 0 0 0 0.117 0.000 0.000 Supenisory Personnel 0 0 0 0.022 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 DEFUELINQ hiaintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supenisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 TOTAL hiaintenance Personnel 8 0 1 1.990 0.000 0.130 Operating Personnel 4 0 0 0.890 0.000 0.000 Health Physics Personnel 2 0 0 0.330 0.000 0.000 Supenisory Personnel 2 0 0 0.390 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.010 GRAND TOTAL 16 0 1 3.600 0.000 0.140 MAXIh1Uh1 INDIVIDUAL DOSE DURING CALENDAR YEAR 1996 - ELECTRICIAN .410 REh!

. - . - -.- - ... -.--. --- - . - - . = . - . - - . = - . .

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During preparation of the 1996 Annual Report, the 1995 Annual Report was reviewed and it was discovered that the values shown in Appendix A, " Standard j Format for Reporting Number of Personnel and Man-Rem by Work and Job l

Function," for 1995 were actually the 1994 values. This is being corrected by the  !

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inclusion of a new revised Appendix A for 1995.  !

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-i 1995 - Revised ~

APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION -

Number ofPersonnel(>100 mrem) TotalMan-Rem Station Utility . Contract Station - tUtility Contract Work & Job Function Employees . Employees Workers and : Employees . ~ Emp;u,A 6 Workers and ,

3 RE ACTOR OPERATIONS /SURVEILLANG Maintenance Personnel 0 0 0 0.561 0.000 0.133 ,

Operating Personnel 4 0 0 0.684 0.000 0.000 7 Health Physics Personnel 2 0 0 0.384 0.000 0.000 Supenisory Personnel 0 0 0 0.201 0.000 0.000 Engineering Personnel 0 0 0 0.044 0.002 0.030 T

ROLTTINE MAINTENANG Maintenance Personnel 0 0 0 0.073 0.000 0.000 Operating Personnel 0 0 0 0.010 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supenisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 INSERVI INSPECTION f Maintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 ,

Supenisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANG 0 0.372 0.000 0.015 Maintenance Personnel 1 0 Operating Personnel 0 0 0 0.093 0.000 0.000 Health Physics Personnel 0 0 0 0.061 0.000 0.000 Supenisory Personnel 0 0 0 0.058 0.000 0.000 Engineering Personnel 0 0 0 0.036 0.000 0.000 .

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APPENDIX A- (cont'd) -

1995 Revised Number ofPersonnel(>100 mrem) TotalMan. Rem Station Utility Contract Station _

Utility - Contract Work & Job Function Employees Employees Workers and Employees . Employees : 1 Workers and Others Others WASTE PROCESSING hiaintenance Personnel 1 0 0 0.314 0.000 0.000 Operating Personnel 0 0 0 0.023 0.000 0.000 Health Physics Personnel 0 0 0 0.005 0.000 0.000  ;

Supervisory Personnel 0 0 0 0.011 0.000 0.000

• Engineering Personnel 0 0 0 0.000 0.000 0.000 DEFUELING hiaintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 TOTAL hiaintenance Personnel 4 0 1 1.320 0.000 0.190 Operating Personnel 5 0 0 0.810 0.000 0.000 Health Physics Personnel 2 0 0 0.450 0.000 0.000 Supervisory Personnel 1 0 0 0.270 0.000 0.000 Engineering Personnel 0 0 0 0.080 0.000 0.030 GRAND TOTAL 12 0 1 2.820 0.000 0.220 h1AX1h1Uh1 INDIVIDUAL DOSE DURING CALENDAR YEAR 1995 - h1AINTENANCE hiECHANIC .280 REh!