ML20203K004
| ML20203K004 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/31/1997 |
| From: | Berg W DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LAC-13628, NUDOCS 9803040402 | |
| Download: ML20203K004 (7) | |
Text
p AMYLAND hb$[ COOPERATIVE. 3200 EAST AVEPOSO e* LACROSSE. WISCONSIN 6460? 0817 BOX 817 (608) 780-4000 FAX NO f600) 7871420
$$,Iiu rf.[, February 23,1998 in reply, please refer to LAC 13628 DOCKET NO 50-409 Document Control Desk U. S. Nuclea Regulatory Commission Washington, DC 20555 ,
SUBJECT:
Dairylaad Power Cooperative La Crosse Boiling Water Reactor (LACBWR)
Possession Only License No. DPR-45 Annual Report for 1997 - Hrpm (Changes. Tests and Exnerimcats
REFERENCES:
(1) LACBWR Technical Specification, Section 6.5.1.1 (2) 10 CFR 50.59(b)
In accoidance with Reference !, we are submitting the Annual Report covering the radiological exposure summary.
Also included are brief descriptions of t'acility changes, including summaries of their safety evaluations, as required by Reference 2. There were no tests or experiments conducted during 1997.
If there are any questions concerning this report, please contcet us.
Sincerely, DAIRYLAND POWER COOPERATIVE WM William L. Berg, Gene Manager 7 j WLB;MNJ:dh - II Enclosures 4,p'.,l,l/j u
cc/ enc: Paul W. Harris, NRC Freject Manager David Nelson, Decommissioning Branch, NRC Regi on til 9003040402 971231 PDR ADOCK 05000409 1
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Annual Report - 1997 4
, Prepared by n
Michael N. Johnsen Technical Support Engineer i
POSSESSION ONLY LICENSE NO. DPR-45 t
- Dairyland Power Cooperative 3200 East Avenue South la Crosse, WI 54602-0817 i
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DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS j997 FACILITY CHANGES The following Facility Changes, which did not require prior NRC approval, were physically completed in 1997. 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 unreviev ed safety questions for these fac!Ilty changes.
25 95 07 HF_ MOVE CATCH BASIN AT FUEL TRUCK UNLOADING STATION This was a necessary change to remove an unacceptable and potential site for fuel oil contamination entering the ground water. This change has no effect on any plant related structures, systems or components associated with SAFSTOR.
42 95 08 REMOVE EQUIPMENT FROM CONTROL ROOM PANEL "G-1" AND BENCHBOARD "E" The entire nucleal instrumentation system was removed. The equipment no longer had any function; removal reduced clutter and streamlined the control room to improve SAFSTOR monitoring. The change has no effect on any plant related structures, systems or components associated with SAFSTOR. '
45 91 16 INST ALL P 10 MANIFOLD SYSTEM FOR THE TURBINE BUILDlliq The P 10 gas supply for Personnel Monitoring and Counting Rooni instrumentation was supplied to each lnstrument by a bottle located at each instrument. This change moved the supply to a centrallocation and piped the gas to the instruments. This change has no effect on safety as it relates to a plant in SAFSTOR.
459619 REMOVE H!GH RADIATION AREA ENTRY ALARMS The high radiation entry alarm systems for the Turbine Main Floor, Stop Valve Area, #3 Feed Water Heater Area and the C:pe Tunnel were no longer needed because, with the plant shut down and in SAFSTOR, ti:ese areas are no longer high radiation areas. This Facility Change completed removal of an obsolete system and has no effect on structures, systems or components associated with SAFSTOR.
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- ' QESR8JDTION OF CHANGES &STS. AND EXPERIMENTE - (cont'd) l 45 97 20 REM _OVE HIGH RANGE CONTAINMENT BUILDING AREA RADIATION MONITORS Post Accident Radiation Moru e. Instrumentation was designed to provide Indication of radiation lew during a Loss of Coolant Accident (LOCA). LACBWR's POL prevents reactor operations and, therefore, this type of accident from occurring. SAFSTOR nccident analysis for a Fuel Element Storago Well pipe break establishes 679 ft as the lowest level to which the pool would drain during the worst case credible pipe break accident. At this level, a'l the spent fuel would remain covered. There are two Area Radiation Monitors (ARM)In the fuel pool area that provide adequate Indication (0.1 to 10,000 mrem /hr) of radiation levels during a credible postulated accident. Therefore, the High Range Monitoring is no longer necessary.
47 96 06 UPGRADF PLANT INSTRUMENTATION This change replaMd the existing transmitters, power supplies and Control Room indsation for the Liquid Waste system, Component ?
Cooling system, Fuel Element Storage Well system, Dumineralized Water system, Weli Water system, Overhead Water Storage system, High Pressure Service Water system, Circulating Water system and Low Pressure Service Water system. This new equipment does not change the basic function of equipment being replaced. It also provides increased reliability and a reduction in maintenance problem associated with aged equipment.
54 97 20 DISCONNECT GAS STORAGE VAULT SUMP PUlePS AND CONTROLS The Wasto Gas Storage Vault sump pumps both failed and were disconnected to remove an electrical safety hazard. In the SAFSTOR mode the Waste Gas Sturage Vault is now an accessible area and, ahhough converilent, automatic pumps are not needed to meet the infrequent pumping demand associated with this sump. A portable pump is used to empty this sump on an as necessary basir. H1levelindication will continue to be maintained in a functional condition.
68 96 08 REMOVE WELL WATER FLOW TOTAll2ERS This change was made to reduce the obstruction to flow in the Well Water system presented by the flow meters. The flow totalizers were unused and the removal of the internals enhanced system operation.
74 97-43 RjiMOVE AND STORE METERING AND POTENTIAL TRANSFORMERS FOR MAIN GENERATOR 1his equipment is not used and unneeded. This removal completed electricalisolation of the Main generator, reducing isolation and tagging time for performing maintenance. This change has no effect on any plant related structures, systems or components associated with SAFSTOR.
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DESCRIPTIO'N OF CHA NGES. TESTS. AND EXPERIMENTS - (cont'd) 74 97 44 CONTPOL ROOM ELECTRICAL LOAD VERIFICATION This facility change de energized unneeded electrical circuits. This was accomplished by verifying and de energizing loads contained on Control Room fuse blocks and Foxboro instrument distribution panels.
Equipment necessary for SAFSTOR was verified to be unaffected by de energizing circuits and components contained in the scope of work, 78 93 14 REMOVE TELEDYNE EMERGENCY LIGHTS FROM VARIOUS LOCATIOLS These stand alone battery operated emergency lights were installed as part of safe shutdown requirements. They had reached the end of their usefullife. In SAFSTOR they have no purpose; they were removed as they failed.
78 95 15 PERSONNEL AIRLOCK DC LluHTING CHANGEOVER The feed for the DC light in the personnel airlock was moved from the Telodyne unit located on the containment building mezzanine to the Reactor plant 125V DC bus, the original and now more reliable power-source. This maintained the backup DC lighting in the airlock and allowed for completion of Facility Change 78 93 14.
87-96 20 QJ)TDOOR SECURITY LIGHTING A three lamp fixtute was added to the south wall of the Waste Treatment Building to illumir, ate the north portion of the Containment Building- This
.was added to provide sufficient lighting to allow the crane lights to be turned off during bug hatches.
97 95 02 REMOVE GLAND STEAM PIPING The Gland Steam and Flash Tank Rollef discharge piping to the main condenser was removed. The Gland Steam Generator had been removed, and this piping was removed as a follow up to that, This removal has no effect on structures, systems or components associated with SAFSTOR.
TESTS There were no tests conducted during 1997.
EXPERIMENLt There were no experiments conducted during 1997, 3
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s 1997 ,
APPENDIX A STANDARD FORMAT FOR REPORTfdG NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCrlON Number ofPersonnel(>100 miem) TotalMan-Rem Station Utility Contract Station Utility Contract Employees Employees Workers and Employees Employees Workers and Work & Job Function Others Odrers REACTOR OPERATIONS / SURVEILLANCE 0 0 0 0.245 0.000 0.000 Maintenance Personnel 0 0 0 0.441 0.000 0.000 Operating Personnel Health Physics Personnel 0 0 0 0.132 l 0.000 0.000 0 0 0 0.174 O.000 0.000 Supervisory Personnei 0 0 0 0.000 0.011 0.000 Engineering Personnel ROUTINE MAINTENANCE 0 0 0 0.134 0.000 0.000 Maintenance Personnel 0 0 0 0.001 0.000 0.000 Operating Personnel Health Physics Personnel 0 0 0 0.005 0.000 0.000 0 0 0 0.000 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Ergineering Personnel ,
INSERVICE INSPECFION 0 0 0 0.000 0 000 0.000 )
Maintenance Personnel Operating F rsonnel 0 0 0 0.000 0.000 0.000 J 0 0 0 0.000 0.000 0.000 IIcalth Physics Personnel 0 0 0 0.000 0.000 0.000 Supervisery Personne!
0 0 0 0.000 0.000 0.000 Engineering Personnel SPECIAL MAINTENANCE 3 0 0 0.4 % 0.000 0.000 Maintenance Personnel 0 0 0 0.039 0.000 0.000 l Operating Personnel O O O 0.020 0.000 0.000 IIcalth Physics PersonncI 0 0 0 0/305 0.000 0.000 Supervisnry Personnel 0 0 0 0.000 0.009 0.000 Engineering Personr.el I
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J APPENDIX A- (cont'd) 1997 Nur.ber ofPersonnel(>100 mrem) TotalMan-Rem Station Utility Contract Station Utdity Contract Work & Job Function Employees Employees Workers and Employ:es Edam Workers and Others Others WASTE PP.OCESSING Maintenance Personnel 0 0 0 0.195 0.000 . 0.000 Operatmg Personnel 0 0 0 0.019 0.000 0.000 IIcalth Physics Personnel 0 0 0 0.043 0.000 0.000 Supervisory Personnel 0 0 0 0.010 0.000 0.000 Ergineering Personnel 0 0 0 0.000 0.000 0.000 DEFUELING Maintenance Personnel 0 0 0 0.000 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 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engincenng Personnel 0 0 C 0.000 0.000 0.000 TOTAL Maintenance Personnel 5 0 0 1.070 0.000 0.000 Operating Personnel 0 0 0 0.500 0.0n0 0.000 IIcalth Physics Personnel 0 0 0 0.200 0.000 0.000 Supervisory Personnel 0 0 0 0.190 0.000 0.000 Engincenng Personnel 0 0 0 0.000 0.020 0.000 GRAND TOTAL 5 0 0 L960 0 020 0.000 ,
MAXIMUM INDIVIDUAL DOSE DURING CALENDAR YEAR 1997 - INSTRUMENT TECHNICIAN .190 REM
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