ML20204D837
| ML20204D837 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/31/1998 |
| From: | Berg W, Johnsen M DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LAC-13674, NUDOCS 9903240294 | |
| Download: ML20204D837 (6) | |
Text
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.D DAIRYLAND
! COOPERATIVE . 3200 EAST AVE. SO. . P.O. BOX 817 LA CROSSE, WISCONSIN 54602-0817 OFFICE (608)787-1258 WI ' BE FAX (608)7871469
,, ,ydCEO March 3,1999 WEB SITE: www.dairynet.com In reply, please refer to LAC-13674 DOCKET NO. 50-409 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 Annual Repon for 1998 - Report of Changes. Tests and Exoeriments
REFERENCES:
(1) LACBWR Technical Specification, Section 6.5.1.1 (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 facinty changes, including summaries of their safety evaluations, as required by Reference 2. There were no tests or experiments conducted during 1998.
If there are any questions concerning this report, please contact us.
Sincerely, DAIRYLAND POWER COOPERATIVE 9903240294 981231 PDR ADOCK 05000409 -
Mb R PDR $ William L. Berg, President & CEO WLB:MNJ:dh l
Enclosures I
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i DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS 1998
. FACILITY CHANGES The following Facility Changes, which did not require prior NRC approval, were physically completed in 1998 A summary of the safety evaluations performed .
in accordance with 10 CFR 50.59 type criteria is included. It was determined that j there were no unreviewed safety questions for these facility changes. ;
I 37-98-24 Reactor Containment Buildina Freicht Door Block Shield Wall Removal The concrete block shield wall outside the Reactor Containment Building freight door reduced radiation streaming in the event of a reactor accident. With reactor operation no longer allowed, this is nc, longer a concern. Concrete block was used to facilitate removal for access to the l freight door. The removal of this shield wall has no effect on safety. )
1 47-98-07 Install Videoarachic Recorder The Videographic recorder was installed under a LACBWR substitution j request. This facility change provided for drawing / document updates l and revision along with changing the power supply for the recorder to the Non-Interruptible Bus 1C. This change documents replacement of obsolete equipment and has no effect on equipment important to safety.
64-96-08. Remove Main Steam B/P Valve Accumulator System The Main Steam Bypass valve had provided steam pressure control. In SAFSTOR the hydraulic control system for this valve has no purpose and was removed to facilitate removal of steam line shielding in the Feed l Pump Area. This Facility Change completed removal of obsolete equipment and has no effect on structures, systems or components associated with spent nuclear fuel storage or SAFSTOR.
64-96-09 Remove Steam Line Shieldina in Feed Pumo Area N16 Gamma shielding for the Main Steam, located in the Feed Pump area, no longer served any purpose and was removed. This Facility Change removed obsolete equipment. There is no effect on s;ructures, systems, or components as.sociated with spent nuclear fuel storage or ;
SAFSTOR. I 70-96-06 Remove Backup Air Compressor The power supply to 1 A station air compressor was changed to essential power to allow 1 A station air compressor to fulfill the purpose of the ,
backup air compressor. The backup air compressor was removed. !
Shifting to the newer, more reliable 1 A station air compressor is an enhancement to the existing air system and has no effect on safety.
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DESCRIPTION OF CHANGES. TESTS. AND EXPERIMENTS -(cont'd) 70 98-07 Replace 18 Air Compressor The 18 station air compressor was replaced with one sized for the air demand of the shutdown plant. New air filters and a control air dryer were installed as part of this upgrade. This new equipment does not change the basic function of equipment being replaced. It also provides increased reliability and a reduction in maintenance problems associated with aged equipment. l l'
74-97-45 Install Outlet in LACBWR Switchyard A 240-V AC single-phase receptacle outlet was installed on the exterior wall of the turbine building inside the LACBWR switchyard to provide power for oil purification equipment use by the electrical maintenance q department. This change has no effect on safety as it relates to a plant in SAFSTOR. l l
74-98-48 Remove 18 Static inverter from Service I The Non-Interruptible Bus 1B no longer powered essen'.lal reactor instrumentation or reactor control circuits. The Non-interruptible Bus 1B was placed on the reserve feed supplied by the regulated bus and renamed the regulated Bus Auxiliary panel. The 1B Static Inverter that was the normal supply for the Non-Interruptible Bus 18 was then removed from service. This Facility Change removed obsolete equipment. There is no effect on structures, systems, or components associated with spent nuclear fuel storage or SAFSTOR.
76-98-02 Install Manviav in Circulatina Water Supply Line A prefabricated 24-inch diameter manway was installed on the circulating water intake tunnel to provide access to repair an existing leak and provide access for future inspection. This change has no effect on safety as it relates to a plant in SAFSTOR.
TESTS There were no tests conducted during 1998. ;
EXPERIMENTS j There were no experiments conducted during 1998. >
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