ML20211B633
| ML20211B633 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/31/1986 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM LAC-12065, NUDOCS 8702190470 | |
| Download: ML20211B633 (12) | |
Text
LA CROSSE BOILING WATER REAC'IOR ANNUAL REPORT 1986 PROVISIONAL OPERATING LICENSE NO. DPR-45 Dairyland Power Cooperative 2615 East Avenue South 8702190470 861231 La Crosse, WI 54602-0817 PDR ADOCK 05000409 R PDR pc2-6.7.1 I ,(
.e DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS 1986 FACILITY CHANGES There was one Facility Change performed during 1985 for which prior NRC approval was obtained prior to plant operation.
74-85-26 Replace the 1KVA inverter (1C) with a larger SKVA unit.
The safety review shows this installation will increase the capacity of the non-interruptible busses and will add an elternate source of power to the IC inverter. A Technical Specification change was required since the inverter capacity was listed in Technical Specifications.
The following Facility Changes, which did not require prior NRC approval, were physically completed in 1986, with the exception of M 45-85-10. FC 45-85-10 was physically completed in October 1985, but was inadvertently omitted from the 1985 report.
45-85-10 Remove Tracerlab air particulate monitor from mezzanine level of turbine building.
The safety review shows this modification is not safety related and this system is no longer in use.
- 19-86-11 Install an electric one ton hoist on the turbine building main floor beam at the northeast stairwell.
The safety review shows this installation is not safety related.
20-84-1 Rensove the portable steam generator from #3 feedwater heater area and remove the indicating lights from control room panel C.
l The safety review shows this modification is not safety related and the equipment has not been used for several years.
i 25-85-1 construct a building to store dry low level barreled radioactive waste material.
The safety review shows this installation is not safety related and will serve to protect the barrels.
30-86-3 Install thermocouple Jack panel in junction box RP-28T and new thermocouple from vessel head to Jack.
The safety review shows this facility change will not affect system operation, only the location of the connections change.
pc2-6.7.1 1 l
31-86-3 Enlarge the core spray bundle upper assembly support plate locating pin holes.
The safety review shows this modification will not alter the ability of the bundle to perform its function and there is no change in the margin of safety.
84-4 Replace control rod drive steel N2 gas charging lines with high pressure hose and snap couplers.
The safety review shows this replacement does not affect function of control rod drives. The gas charging header is normally depressurized except for raising accumulator pressures.
32-86-9 Install 1/4" stainless steel tubing from high pressure nitrogen system to grade floor for lower control rod drive test bench.
The safety review shows this installation is not safety related.
38-84-5 Add a turbocharger to the high pressure service water (HPSW) diesel engine 1A.
The safety review shows the operating conditions of the diesel with an added turbocharger are within the design capabilities of the HPSW system. Addition of the turbocharger will increase reliability and performance of the system.
46-86-4 Rearrange benchboard controls for forced circulation pumps and valves and shutdown condenser controls.
The safety review shows the equipment operation will remain the same, only the arrangement on the benchboard will change.
48-85-7 Add a line power interrupter to the power source to the Annex meteorological rack.
The safety review shows this installation is not safety related. This modification is expected to improve the operability of the meteorological system during a power interruption.
49-85-3 Install an action pack signal conditioner between the containment building high range radiation monitor and the technical support center computer to reduce the impact of noise on the signal.
The safety review shows this installation is not safety related.
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49-85-4 Upgrade the computer link between the technical support center (TSC) and the emergency operations facility (EOF) to prevent lockup of the EOF tensinal when automatic transmission of data from TSC to EOF occurs.
The safety review shows this modification is not safety related since this system is for data gathering only.
50-85-12 Perform wiring changes to channel 1 and 2 reactor water level instruments.
The safety review shows this modification does not change the water level instruments operation or system function.
50-85-13 Replace reactor wide range water level transmitter 50-42-305 with a new transmitter having local rather than remote amplifier.
The safety review shows this modification involves replacement of equipment only. The new equipment is able to withstand harsh environments and is judged to be superior to original equipment.
50-86-15 Remove unused portions of the automatic speed controls from the forced circulation pump (IUP) speed control system.
The safety review shows this modification is not safety related. Removal of this equipment will eliminate a potential malfunction of the FCP controls.
54-85-16 Replace retention tank discharge valve 54-25-006 with a General Twin Seal valve and Kinetrol valve operator.
The safety review shows this replacement does not affect system operation. The valve has the same trips, indications, fail position, shutoff pressure and closing time.
54-86-17 Install a tee and shutoff valves downstream of dewatering ion exchanger outlet valve 54-24-213.
The safety review shows this modification is not safety
, related, it only provides for backwashing of the dewatering ion l exchanger resin screens.
! 55-84-10 Remove offgas compressor and associated equipment and valves.
l The safety review shows this modification is not safety related
( and the equipment is not important to safety.
pc2-6.7.1 3
-57/76-85-2 Upgrade the electronics of the component cooling water (CCW) and turbine condenser liquid radiation monitors.
The safety review shows this modification will provide more sensitive and reliable radiation monitoring capabilities.
62-85-6 Install position indication for shutdown condenser condensate leg drain valve. Open/close lights to be located on control room benchboard.
The safety review shows this modification is not safety related but adds indication of valve position to enhance the operators' ability to assess containment isolation.
62-85-8 Add a level indicating loop to the secondary side of the shutdown condenser.
The safety review shows this installation will provide additional information and control capability.
62-86-10 Upgrade the shutdown condenser vent to offgas piping system from and including valve 62-24-004 up to and including valve 55-24-039 to class 900.
The safety review shows upgrading of the shutdown condenser vent will reduce the consequences of a fail open malfunction of valve 62-25-003 by allowing safe high pressure isolation of the vent line outside of the containment. This change will also permit conformance to current general design criteria for systems penetrating primary containment.
62-86-11 Install a new Junction box on shield wall south of #1 and #2 safety valves.
The safety review shows this facility change is for the addition of a junction box only and does not affect system operation.
64-86-6 Remove unused remote amplifier boxes for transmitters 64-35-301 and 64-35-302.
The safety review shows this modification does not change system design or operation.
64/65-86-7 Remove unused remote amplifier boxes for transmitters 64-35-303 and 65-37-301.
The safety review shows this modification does not change system design or operation.
pc2-6.7.1 4
69-82-2 Install an environmentally qualified level indicator on the overhead storage tank (OHST) which will read out in the control room.
The safety review shows this indicator will provide additional
-information to operators but will not affect the chance of an accident.
69-85-4 Reroute the seal injection emergency make-up supply line and the purification reject line from their points of connection with the high pressure core spray suction line to a point of connection with the containment building spray header at approximately the same elevation.
The safety review shows this modification will reduce the probability of an accident that could cause loss of water to the high pressure core spray (HPCS) system. With the completion of this modification steam Jet impingement concerns for the HPCS line will be satisfied.
74-84-18 Install four 120 V AC outlets around main turbine.
The safety review shows this facility change is not safety related.
74-85-27 Replace the generator plant batteries and battery charger with larger batteries and charger.
The safety review shows this modification is necessary due to the age of the battery and will allow for future DC power system expansion.
74-85-28 Add a second AC power supply to OCB 2NB11 from a 120/240 volt AC distribution panel located in the Genoa switchyard.
The safety review shows this modification is not safety related and will not adversely affect the reliability of the offsite power link.
74-86-29 Supply lA high pressure service water (HPSW) diesel tank heater with a power source separate from IB HPSW diesel tank heater.
The safety review shows this modification will provide a more r reliable source of power for the engine heaters and will prevent nuisance circuit trips, i 74-86-31 Replace 1A inverter with a newer and larger unit.
The safety review shows this replacement will improve the
! performance capability of the inverter since the new inverter i synchronizes the inverter to the alternate power source, reducing the possibility of an inadvertent scram due to a transfer of loads.
l pc2-6.7.1 5
74-86-32 Install new washing machine, including a 240 V AC power source in turbine building laundry area.
The safety review shows this installation is not safety related.
75-86-6 Relocate 1B high pressure service water (HPSW) diesel starting battery to provide separation and protection from lA HPSW diesel battery to satisfy Appendix "R" coussitment.
The safety review shows equipment functions are unchanged, only the location is changed.
78-86-11 Install contact 13/14 in the automatic close portion of the IB emergency generator output breaker close circuit.
The safety review shows this modification will make resetting the auto-pump circuit conform with the design of the lA emergency generator output breaker. This change will not affect the operability of the IB emergency generator output breaker.
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c TESTS There were no tests performed during 1986 which required prior NRC approval. The following tests not discussed in the SAR were performed during 1986.
OP-35-04 Procedures for certain tests required during the first startup and power escalation after the 1986 refueling outage, including comparison of the worth of nine new ASEA-ATOM control rods with Allis-Chalmers control rods.
The safety review concluded this testing was similar to that performed after initial reactor startup and previous refuelings and did not involve an unreviewed safety question.
OP-64-02 Leak test of turbine building main r. team isolation valve 64-25-030.
The safety review concluded that performance of the test during cold shutdown is basically a continuation of the primary system valve leak test and does not defeat containment integrity in any way.
pc2-6.7.1 7
EXPERIMENTS There were no experiments conducted during 1986. While the following procedure did not involve an experiment, it generated sufficient interest to be included in this report.
M-56-01 Repair of 8-inch decay heat pump suction pipe leaks.
The safety review concluded that the procedure restores the piping to a condition equal to or better than the original design and does not involve an unreviewed safety question.
SAFETY VALVE FAILURES AND OPERATIONS There were no safety valve failures or operations for pressure relief purposes during 1986.
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- P O. BOX 817
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- LA CROSSE. WISCONSIN 54602-0817 (608) 788-4000
!, JAMES W. TAYLOR General Manager January 27, 1987 In response, please refer to LAC-12065
[
Document Control Desk U.S. Nuclear Regulatory Commiission Washington, DC 20665
Subject:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 '
' ANNUAL REPORT IDR 1986 - REPORT OF CHANGES, TESTS AND EXPERIMENTS
References:
(1) LACBWR Technical Specifications, Section 6.9.1.5 (2) 10 CFR 50.59 (b)
(3) NUREG-0737, dated October 31, 1980,Section II.K.3 (3)
Gentlesen: i In accordance with Reference (1), we are submitting the Annual Report for 1986 covering the radiological exposure summary.
Also included are brief descriptions of changes, tests, and experiments, including sumanaries of the safety evaluations of each required by the provisions of Reference (2).
In accordance with Reference (3), this report also includes the annual report of safety valve operations and failures. There were no safety valve operations or failures during 1986.
If there are any questions concerning this report, please contact us.
i ncerely, i
JWT/LSG/ lam Enclosures
] cc: NHC Resident Inspector
, James Keppler, Region III Roby Bevan, NRC i
pc2-6.7.1 /
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