ML20041E225
| ML20041E225 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/22/1982 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20041E219 | List: |
| References | |
| NUDOCS 8203100263 | |
| Download: ML20041E225 (8) | |
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LA CROSSE BOILING WATER REACTOR ANNUAL REPORT 1981 Provisional Operating License No. DPR-45 Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601 l
l 8203100263 82022205000409 PDR ADOCK PDR R
l l
DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS 1981 FACILITY CHANGES There were no facility changes performed during 1981 for which prior NRC approval was obtained.
The following facility changes which did not require prior NRC approval, were physically completed in 1981:
FC-06-80-1 Installation of fire sprinklers for Main and Auxiliary Power Transformers, lA Diesel Generator Room and Electrical Penetration Room.
The Safety Analysis Review shows that this installation will reduce the probability of fire damage to the 1A Diesel Generator, Main and Auxiliary Power Transform" s and the Electrical Penetration Room.
FC-06-80-5 Modification to allc. remote manual actuation of the 1B Diesel Generator Room cog System.
The Safety Analysis Review shows that this modification will increase the reliability of 1B Diesel Generator Room CO2 System.
i FC-06-81-9 Oil Storage Room floor overflow drain '.ine installation.
1 The Safety Analysis Review shows that this installation will not affect the margin of safety, but will allow for the removal of excessive oil from the Oil Storage Room in case of a leak and plugging of normal drain.
FC-06-81-12 Installation of 3-HR rated fire door on the l
Records Storage Room.
The Safety Analysis Review shows that this modification is not safety related, but does enhance safe storage of records.
i FC-06-81-13 Installation of Control Panel for the Main and Auxiliary Power Transformer Deluge Fire System.
The Safety Analysis Review shows that this modification does not affect the margin of safety as discussed in the design basis for fire suppression systems.
DESCRIPTIONS OF CHANGES, TESTS, AND EXPERIMENTS - 1981 FC-31-80-1 Refueling sequence for Cycle 7 of the La Crosse Boiling Water Reactor.
The Safety Analysis Review shows that this Facility Change only involves re-arranging the fuel and fuel shrouds in the LACBWR core and replacing certain high ex-posure fuel with fresh fuel and exchanging remaining stainless steel shroud cans with Zirconium shroud cans.
(See LAC-TR-087, Refueling Plan for Cycle 7 of LACBWR).
FC-37-80-3 Installation of protective cover over Con-tainment Isolation Valves reset buttons.
The Safety Analysis Review shows that this installation will deter inadvertent reset actions by the Control Room operators.
FC-38-81-2 Modification to allow for individually leak testing the Alternate Core Spray Check Valves.
The Safety Analysis Review shows that this installation is within the analysis envelope for small size pipe breaks.
FC-45-80-1 Installation of Containment Building High Range Radiation Monitor.
The Safety Analysis Review shows that this installation will provide additional guidance regarding fuel condition following a Design Basis Accident.
FC-45-80-3 Installation of High Range Monitor for stack activity.
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The Safety Analysis Review shows that this installation will extend the monitoring range l
for the stack gaseous and particulate activity I
following an accident.
FC-48-81-1 Move Ground Wind Speed and Direction Recorder from Annex Building to Control Room.
The Safety Analysis Review shows that this j
modification is not safety related and the environmental monitoring system is not i
I addressed in the FSAR.
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4 DESCRIPTIONS OF CHANGES, TESTS, AND EXPERIMENTS - 1981 FC-48-81-2 Installation of new 10-Meter Meteorological Tower and run conduit from Tower to Annex.
The Safety Analysis Review shows that this modification will not interface with any safety related system.
Also, the meteorol-ogical system is not addressed in the FSAR.
FC-52-80-5 Installation of isolation valve in Seal In-ject Surge Tank equalizing line and changing micron size of filter.
The Safety Analysis Review shows that this installation will not change the operation of the Seal Inject System, and Technical Specifications do not address this portion of the Seal Inject System.
FC-54-81-3 Installation of Sand Point Well for Ground Water Sampling.
The Safety Analysis Review shows that this sampling is not safety related and is not addressed in the FSAR.
FC-55-80-4 Install new isolation valve in the Contain-ment Off-Gas Vent Header.
The Safety Analysis Review shows that this installation will not change the function of the valve, only the location in the line.
FC-55-81-5 Modify 4" Reactor Off-Gas Vent Header Isol-ation Valve Control Circuit for Automatic Closure on High Containment Radiation.
The Safety Analysis Review shows that this modification will improve the valves closure response in the event of a LOCA.
FC-58-81-3 Modify FESW Level Alarm.
The Safety Analysis Review shows that this modification establishes the appropriate setpoint consistent with the Revised Technical Specifications required by Fuel Storage Rack modification. _
DESCRIPTIONS OF CHANGES, TESTS, AND EXPERIMENTS - 1981 FC-63-80-1 Modify Condensate Domineralizer System Drain Line.
The Safety Analysis Review shows that this modification only provides an alternate drain path to allow bypassing plugged normal drain line.
FC-54-80-2 Replacement of liquid flow totalizer with micro motion mass flow meter.
The Safety Analysis Review shows that this replacement is an upgrade and should provide better control of radioactive liquid waste releases.
FC-73-80-2 Actuator Seal and Solenoid Valve replacement for Containment Ventilation Damper.
The Safety Analysis Review shows that replacement of seals, gaskets and solenoid valves with environmentally qualified items does not affect the operation of the dampers.
FC-74-80-4 Change taps for Reserve Auxiliary Power Transformer.
The Safety Analysis Review shows that this change evaluation indicated a safe condition should exist if the change is made.
FC-74-81-5 Installation of larger vent fan in the Admin-istration Building Electrical Equipment Room.
The Safety Analysis Review shows that this modification will not affect safety and the equipment is not safety-related.
FC-74-81-6 Add 7 Conductor M-I Cable and junction box
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on Mezzanine Level in Containment.
The Safety Analysis Review shows that this modification will not affect the design of electrical penetrations and'will be leak tested after installation.
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FC-74-81-8 Installation of seismic restraints on the 1A (480V) Essential Switchgear.
The Safety Analysis Review shows that this installation will not interfere with bus operation. t
DESCRIPTIONS OF CHANGES, TESTS, AND EXPERIMENTS - 1981 FC-78-81-3 Installation of anchor bolts on the 1A Emergency Diesel Generator.
The Safety Analysis Review shows that this modification will not affect the operation of the Diesel Generator.
FC-83-80-1 Installation of an Emergency Service Water Supply System.
The Safety Analysis Review shows that this installation will not affect the margin of safety in that the functional capability of the present system will remain as before.
In addition, an unauthorized modification was made in adding a pressure switch on a Containment Building Sensing Line.
For the method of installation utilized, advanced NRC approval was necessary.
Through administrative oversight, the need for the NRC approval was not considered.
The switch was removed with NRC approval.
TESTS There were no tests performed during 1981 which required prior NRC approval.
The following tests not discussed in the SAR was performed during 1981:
FC-31-80-1, Proc. 6 Procedures for Certain Tests Required during the First Startup and Power Escalation after the 1980 Refueling Outage.
The Safety Evaluation concluded that this test did not constitute an un-reviewed safety question and was similar to those conducted following previous refuelings.
FC-83-80-1 Integrated Test of Emergency Service Water Supply System (Refer to FC-83-80-1 above).
EXPERIMENTS No experiments were conducted during 1981.
SAFETY VALVE FAILURES There were no safety valve failures during 1981..-
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I APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN REM BY WORK AND JOB FUNCTION Numbee of Personnel (> 100 mrem)
Total Man-Rem j
Contract Workers Contract Worhets Woek & Job Function Station Employees Utility Employees and Others Station Employees Utility Employees and Others Reactor Operations A Surveillance Maintenance Personnel 9
3.174 Operating Personnel 20 35.208 Ilealth Physics Personnel 7
0 8.943 0.088 Supervisory Personnel 11 0
8.534 0.213 Engineenng Personnel 5
0 0
2.044 0.029 0.175 Itoutine Maintenance Maintenance Personnel 18 1
23.603 0.256 Operating Personnel 6
2.076 ilcalth Physics Personnel 6
1.604 i
Supervisory Personnel 8
0 4.304 0.002 Engineenns tersonnel 1
0 0.643 0.060 l
laservice Inspection Maintenance Personnel 6
1.174 Operating Persannel 0
0.172 I
IIcalth Physics Personnel 0
0.024 cn '
Supervisory Personnel 1
0.232 Engineering Personnel 0
0.0 Special Maintenance g
Maintenance Personnel 14 2
0 7.472 0.310, 0.002 l
Operating Personnel 7
1.866
?
llealth Physics Personnel 5
1.894 Supervisory Personnel 5
2.006 Engineering Personnel 3
0 1.922 0.134 Waste Processing Maintenance Personnel 2
2 0.478 1.448 Operating Personnel 4
0.821 llcalth Physics Personnel 3
0.905 Supervisory Personnel 1
0.650 Engineering Perscenel 0
0.050 Refuelin5 i
Maintenance Personnel 5
1.501 Operating Personnel 0
0.555 llealth Physics Personnel 3
0.537 4
Supervisory Personnel 1
1 0.277 0.135 Engineering Personnel 1
0 0.217 0.018 TOTAL Maintenance Personnel 18 2
3 37.402 0.310 1.706 Operating Personnel 20 0
0 40.648 0.0 IIcalth Physics Personnel 8
0 0
13.907 0.088 Supervisory Personnel 18 0
1 16.003 0.350 l
Fncineerine Personnel 7
O O
4,876 0.024 0.187 i
Grand total 71 2
4 112.R86 0.339 2.531 i
k
SPECIAL WORK PERMITS (SWP'S)
HAVING GREATER THAN 1.2 MAN-REM EXPOSURE SWP NO.
023 9.853 Remove and Replace 1B Forced Circulation Pump (FCP) Motor Bearing 81-052 1.1875 Install Piping in Containment Building for Post-Accident Sampling System 81-062 1.171 Drill Holes as Necessary to Rehang Pipe Hangers81-074 1.300 Change Filters in FESW 81-088 4.394 Take Measurements or 1A FCP and Repair 1A FCP 81-090 2.270 Receive Fuel from Morris, IL and Store 81-112 5.45 Transfer Resin 81-135 1.218 Drop Nos. 7, 8, and 22 Lower Control Rod Drive Mechanism
(' CRDM), Repair as Necessary, L
and Raise 81-204 1.973 Repair Oil Leak on 1A FCP, Tighten Packing on Valve (Loop Discharge)81-207 2.015 Repair 1A FCP Seal