ML19350A275
| ML19350A275 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/27/1981 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML19350A274 | List: |
| References | |
| NUDOCS 8103130382 | |
| Download: ML19350A275 (10) | |
Text
LA CROSSE BOILING tiATER nEACTOR ANNUAL REPORT 1980 Provisional Operating License No. DPR-45 1
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SPECIAL WORK PERMITS (SUP ' S ) > 1.2 MAN-REM SUP NO.
MAN-REMS80-006 Dispose of Old Peripheral Shroud by Drumming-----
8.392 80-035 Cutting and Welding of Crash Pad-----------------
1.636 80-037 Sample Hi-Rad Drums in Waste Treatment Building Pit----------------------------------------------
4.113 80-043 Repair of lA FCP Scal----------------------------
1.875 80-061 Prepare for Hi-Rad Drum Shipment-----------------
3.760 80-069 Drill Holes in FESW Drain Line and Test for Le a k a g e - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2.210
)80-072 Repair Anchors in FCP Cubicles-------------------
3.885 l
80-092 Repair Leaks in FESW Liner-----------------------
3.353 80-115 Repair lA FCP Scal-------------------------------
1.940 80-117 Remove, Repair, Replace Upper CRD----------------
2.140 80-122 Install New Racks in FESW------------------------ 11.472 80-140 Repair No. 28 Upper CRD--------------------------
2.051 80-142 Repair lA FCP Scal-------------------------------
2.077 80-153 Repait Of Lower CRD------------------------------
1.830 80-155 Remove and Reinstall UCRD's Nos. 5 and 21--------
7.225 80-170 Change FESW F ilter on High AP--------------------
1.826 80-171 Install Remaining New Fuel Racks-----------------
2.886 80-185 Test-Cut Old Fuel Racks for Packaging------------
1.270 80-196 Re move A ll Lowe r C RD ' s--------------------
1.255 80-198 Replace Bolts in FCP Cubicle Baseplate Restraints 14.625 80-199 Remove Lower Cavity Baseplate and Concrete Blocks to Install CRD Shielding-------------------------
2.104 80-201 Remove Reactor Head and Prepare for Refueling----
2.381 80-212 Repair Decay Heat Pump Seal----------------------
1.250 80-215 Re f u e l i n g - - -- - - - - - -- - - - - - - -- -- -- - - -- - - - - - - - - - - - - -
6.859 80-219 Remove Lagging in Reactor Building for ISI-------
3.830 80-222 ISI in Reactor Building and Tunnel by SWRI-------
3.615
'0-223 Re move UCRD, Re in s ta ll S ame-----------------------
5.815 d
00-224 PM UCRD------------------------------------------
1.371 80-239 Replace All Lower CRD's----------------------
2.2E4 80-240 Add Boroflex Shielding to Lower Cavity and 4
Replace Shie:d Blocks----------------------------
9.229 80-242 Repair lA FCP Scal-------------------------------
2.220 80-224 Transfer Core Spray Bundle to Reac'or and Bolt in Place-----------------------------------------
6.880
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DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS 1980 Facility Changes requiring prior NRC approval:
2 FC-78 Installation of New High Density Storage Racks for Spent Fuel Replaced existi.ng racks with high density storage racks to expand capacity of fuel element storage well.
The safety analysis review shows *.cre is reasonable assurance that the health and safety of the public will not be endangered.
(Amendment No. 18 to Provisional Operating License No. DPR-45) i Facility Changes not requiring prior NRC approval:
FC-77 Removal of Thermocouples from the Fuel Element Dry Sipping Rig Removed two thermocouples f rom sipping canister and plugged holes since not needed and will simplify use and maintenance of sipping rig.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-79 Heating Boiler Relief Valve Discharge Piping Modification Rerouted heating boiler rel.af valve discharge piping i
l external to heating boiler room.
The saf ety evaluation concluded this change did not l
constitute an unreviewed safety question.
FC-62-80 Installation of Test Chamber for Shutdown Condenser Pipe Nipple Installed test chamber around pipe nipple or shutdown condenser shell to perform leakage test.
j The saf ety evaluation concluded this change did not constitute an unreviewed safety question.
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FC-06-80 Fire Proofin~ Maintenance Shop Beans Covered maintenance shop beams with mixture of plaster and monakate for fireproofing.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-55-80 Installation of an Isolation Valve in the Vacuum Pump Loop Seal Drain Line Installed valve in motor driven vacuum pump muf fler drain line to climinate possible contamination spread via Turbine Building floor drain system.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-06-80 Replace Fire Hoses in Turbine Building Replaced unlined linen fire hoses with 75',
lh" diameter, 100% polyester, single jacheted lined fire hoses, factory tested at not less than 300 psig.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-06-80 Installation of Time Meter for Fire Zone Alarm Bypass Installed time alarm circuit for each fire zone bypass switch as per NRC request.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-55-80 Installation of Water Traps in Of fgas Flowmeter Inlet and Outlet Lines Installed water traps in offgas flowmeter inlet and outlet lines to eliminate moisture buildup and source of scale.
The saf ety evaluation concluded - this change did not constitute a.n unreviewed safety question.
FC-74-80 Change Feed Tap for the Reserve Auxiliary Transformer Changed tap for reserve auxiliary transformer from the 724 50V setting to 70725V tap as per NRC request.
The saf ety evaluation concluded this change did not constitute an unreviewed safety question, i
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FC-52-30 Installation of Drain Valve in the Seal Inject Makeup Line Inside of the Containment Building Installed drain valve in seal inject makeup line to enable line to be drained for Type C air leakage test.
Safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-35-80 Modification of the Shroud can Handling Tool Chamferred shroud can handling tool to prevent it from catching on new fuel storage well rack.
Safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-50-80 Forced Circulation Pumps Coupling Oil Pump Vent Line Modif ica tion Rerouted coupling pumps' vent lines to eliminato loop seal.
Safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-50-80 Installation of Forced Circulation Pump Trip on High Reactor Pressure and Low Water Level (ATUS)
Installed automatic trip of FCP's on 2-of-3 logic on high reactor pressure or low water level.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-45-80 High Radiation Monitor Installation Inside Containment l
Installed high radiation monitor inside containment as per TMI requirements.
The saf ety evaluation concluded this change did not
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constitute an unreviewed safety question..
FC-64/38-80 Installation of Reset Control Buttons in the Main Steam Isolation Bypass Valve and Scr'een Wash Circuitry Installed reset buttons in ianin steam isolation bypass valve and screen wash circuitry to prevent automatic reset.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-79 Anchor Bolt Replacement and Base Plate Modifications Removed and replaced pipe support base plates and concrete anchor bolts at several locations.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-31-80 Refueling Plan for Cycle 7 of the La Crosse Boiling Water Reactor Installed fresh fuel and shroud cane and rearranged fuel and shroud cans in the reactor cnre.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
FC-58-80 Installation of Remote Manual Actuated Valve for Addition of Water to the Fuel Element Storage Well Installed remote manual actuated valve for addition of water to fuel element storage well from Control Room.
Safety evaluation concluded this change did not constitute an unreviewed saf ety question.
FC-06-80 Modification of 1B Diesel Generator Room Modified 1B diesel CO2 system to provide remote manual actuation f or the main and reserve banks.
The saf ety evaluation concluded this change did not constitute an unreviewed safety question.
FC-06-80-1, - Installation of Sprinkler Systems for LA Diesel Generator Room, Electrical Penetration Room, and the Main and Auxiliary Transf ormers Installed sprinkler systems at main and auxiliary transformers, lA diesel generator room, and electrical penetration room.
The saf ety evaluation concluded this change did not constitute an unroviewed safety question.
FC-21-80-l _- Installation of Fire Resistant Neutron Shielding in Lower Reactor Cavity Replaced neutron shielding around lower rod drives with firc-resistant neutron shielding in lower reactor cavity.
The saf ety evaluation concluded this change did not constitute an unreviewed safety question.
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PC-06-80 Installation of Fire Curbs Around +ba Turbine Oil Reservoir, lA Diesel Room, and 1B Diesel Room j
Installed metal curb across lA diesel roon doorway and extended curbs around IB diesel oil day tank and turbine oil tank.
The safety evaluation concluded this change did not constitute an unreviewed safety question.
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TESTS There were no tests performed during 1980 which required prior NRC approval.
The following tests not discussed in the SAR were performed during 1980.
STP-40 Determination of Shutdown Margin as Required by IE Bulletin No. 79-29 Performed shutdown margin test and showed there was an s2t ak/k shutdown margin, whidi is a significantly greater shutdown margin than required by Technical Specifications.
The cafety evaluation concluded this tcol did not constitute an unreviewed safety question.
OP-58 " Blackness" Test to Verify the Presence of the Neutron Poison Material in Irradiated Fuel Storage Racr.s Performed test which showed the presence of poison material in the new storage racks.
The safety evaluation concluded this test did not constitute an unreviewed safety question.
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t EXPERIMEMTS No experiments were conducted during 198 0.
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SAFETY VALVE FAILURES i
l There were no safety valve failures during 1980.
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