ML100610187
| ML100610187 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/10/2010 |
| From: | Berg W Dairyland Power Cooperative |
| To: | Document Control Desk, NRC/FSME |
| References | |
| LAC-14102 | |
| Download: ML100610187 (8) | |
Text
WILLIAM L. BERG President and CEO DAIRYLAND POWER COOP E RAT IV E February 10, 2010 In reply, please refer to LAC-14102 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 Report for 2009 - Personnel Exposure and Description of Changes, Tests and Experiments
REFERENCES:
(1) LACBWR Technical Specification, Section 6.5.1.1 (2) 10 CFR 50.59(d)(2)
In accordance with Reference 1, we are submitting the Annual Report covering the radiological exposure summary.
Also included are brief descriptions of facility changes, including summaries of evaluations, as required by Reference 2. No tests or experiments were conducted during 2009.
If there are any questions concerning this report, please contact us.
Sincerely, DAIRYLAND POWER COOPERATIVE William L. Berg, President & CEO WLB: JBM: two Enclosures cc/enc: Kristina Banovac, NRC Project Manager William Snell, NRC Region III Peter Lee, Decommissioning Branch, NRC Region III
[1 ~UOC~ (
A Touchstone Energy Cooperative 7~9kf~.
3200 East Ave. S.
- PO Box 817 - La Crosse, WI 54602-0817
- 608-787-1258 - 608-787-1469 fax
- www.dairynet.com
La Crosse Boiling Water Reactor (LACBWR)
Possession Only License No. DPR-45 2009 ANNUAL REPORT PERSONNEL EXPOSURE AND DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602-0817
2009 Dose Distribution Date: 01/20/2010 License No. DPR-45 Licensee: DAIRYLAND POWER COOPERATIVE Affiliated Lic. No.:
Primary &Affiliated All Records for Licensee Records Monitoring Year Number of TEDE Dose Number of TEDE Dose Dose Range (rem) Individuals (person - rem) Individuals (person - rem)
No Meas. Exposure 25 25 Meas. <.100 47 1.165 47 1.165
.100 - .250 1 0.142 1 0.142
.250 - .500
.500 - .750
.750 - 1.000 1.000 - 2.000 2.000 - 3.000 3.000 - 4.000 4.000 - 5.000
> 5.000 Number with Meas. TEDE 48 48 Total Monitored 73 73 Total Collective TEDE 1.307 1.307 Total Collective CEDE
APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 2009 Number o dPersonnel(>100 mRem) Total Man-Rem Contract Contract Work & Job Function Station Utility Workers and Station Utility Workers and Employees Employees Others Employees Employees Others REACTOR SURVEILLANCE Maintenance Personnel 0 0 0 0.225 0.000 0.000 Operating Personnel 0 0 0 0.101 0.000 0.000 Health Physics Personnel 0 0 0 0.171 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.026 0.000 0.105 ROUTINE MAINTENANCE Maintenance Personnel 0 0 0 0.012 0.000 0.000 Operating Personnel 0 0 0 0.014 0.000 0.000 Health Physics Personnel 0 0 0 0.015 0.000 0.000 Supervisory Personnel 0 0 0 0.001 0.000 0.000 Engineering Personnel 0 0 0 0.003 0.000 0.000 INSERVICE INSPECTION Maintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 SPECIAL MAINTENANCE Maintenance Personnel 0 0 0 0.015 0.000 0.000 Operating Personnel 0 0 0 0.289 0.000 0.000 Health Physics Personnel 0. 0 0 0.126 0.000 0.000 Supervisory Personnel 0 0 0 0.142 0.000 0.000 Engineering Personnel 0 0 0 0.012 0.000 0.020 APPENDIX A - (cont'd) 2009 Number of Personnel (>100 mRem) Total Man-Rem Contract Contract Work & Job Function Station Utility Workers and Station Utility Workers and Employees Employees Others Employees Employees Others WASTE PROCESSING Maintenance Personnel 0 0 0 0.013 0.000 0.000 Operating Personnel 0 0 0 0.006 0.000 0.000 Health Physics Personnel 0 0 0 0.011 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 DEFUEL1NG Maintenance Personnel 0 0 0 0.000 0.000 0.000 Operating Personnel 0 0 0 0.000 0.000 0.000 Health Physics Personnel 0 0 0 0.000 0.000 0.000 Supervisory Personnel 0 0 0 0.000 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 TOTAL Maintenance Personnel 0 0 0 0.265 0.000 0.000 Operating Personnel 0 0 0 0.410 0.000 0.000 Health Physics Personnel 0 0 0 0.323 0.000 0.000 Supervisory Personnel 0 0 0 0.143 0.000 0.000 Engineering Personnel 0 0 0 0.041 0.000 0.125 GRAND TOTAL 0 0 0 1.182 0.000 0.125 MAXIMUM INDIVIDUAL DOSE DURING CALENDAR YEAR: 0.142 Rem - Health Physics Technician DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS 2009 FACILITY CHANGES The following facility changes were physically completed in 2009. A summary of the evaluation of each, performed according to 10 CFR 50.59, is included. The determination was made that prior NRC approval was not required for these facility changes.
06-01-27 Remove Electrical Equipment Room Halon Fire Suppression System The Electrical Equipment Room, below the Control Room, contained equipment related to reactor safety.
Much of this equipment has been removed, and there is no longer a need for automatic Halon fire suppression in the space. The 50.59 screen, prepared in accordance with LACBWR Administrative Control Procedure (ACP) 06.4, "10 CFR 50.59 Evaluations," concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
25-09-15 DPC Genoa Site Back-Up Control Center (BUCC)
Dairyland Power Cooperative constructed a BUCC for business continuity on the Genoa site. The BUCC is supplied potable water from the LACBWR Well Water System. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
37-06-30 Remove Reactor Plant Pipe Heating Resistance heating installed on Reactor Building pipe penetrations no longer in use was disconnected.
The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
38-97-09 Remove Alternate Core Spray System in Turbine Building The Alternate Core Spray System provided river water cooling to the reactor in the event of a maximum credible accident. Motor-operated valves in the Turbine Building and system instrumentation were electrically dismantled. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
47-03-08 Remove Control Room Foxboro Power Supplies and Distribution Panels Foxboro power supplies and distribution panels provided power to various control relays and indications.
Necessary equipment was connected to alternate power sources, and the Foxboro power supplies and panels were removed. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
Page 1 of 3
54-07-25 Drain Piping Removal Various unused vent and drain lines associated with the biological shield upper cavity were removed as interference to the cask preparation area modification for the Dry Cask Storage Project. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
54-09-26 Liquid Waste Flow Indicator Replacement Flow indication equipment for the Liquid Waste System was upgraded. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
55-96-23 Remove 10 Minute Holdup Tank The Off-Gas System was largely dismantled years ago leaving the Holdup Tank orphaned within a concrete shield labyrinth. An addendum to this Facility Change abandoned the Holdup Tank in place awaiting future demolition. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
56-97-03 Remove Decay Heat System Electrical dismantlement of the Decay Heat System was completed. Demolition of the mechanical equipment will be performed at a later date. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
73-09-31 Provide Electrical Controls to Operate Reactor Building Inlet Dampers Two inlet and two exhaust ventilation dampers for the Reactor Building were operated open-closed together by a single control circuit. A modification was made to permit closing of the inlet dampers independently of the outlet dampers to assure air effluent from the Reactor Building is directed to the stack monitoring path at all times. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
74-04-73 Remove Unused Wiring at Main Control Panels Extensive effort was given to research Control Room indicating panel wiring, to document that needed as installed, and to remove all unused wiring. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
74-07-84 Remove Miscellaneous Elapsed Time Meters Run-time meters for various pumps that have been removed were electrically disconnected and drawings were updated. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
Page 2 of 3
77-08-02 Removal of LPSW Seal Water System New, smaller Low Pressure Service Water (LPSW) pumps were installed that do not require filtered seal water flow. The LPSW Seal Water system was dismantled. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
78-05-27 Install 125-V DC Station Power Charger The LACBWR 125-V DC system is supplied by a single battery and battery charger. A new battery charger was installed as an available DC voltage backup in the event of simultaneous failure of the battery and battery charger. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
92-01-04 Removal of Turbine Oil and Hydrogen Seal Oil System The bulk of the turbine/hydrogen seal oil system was dismantled and removed. Empty clean and dirty oil tanks remain for future demolition. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this facility change did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation per ACP-06.4 was not required.
TESTS There were no tests conducted during 2009.
EXPERIMENTS There were no experiments conducted during 2009.
Page 3 of 3