ML110910244
ML110910244 | |
Person / Time | |
---|---|
Site: | La Crosse File:Dairyland Power Cooperative icon.png |
Issue date: | 03/17/2011 |
From: | Berg W Dairyland Power Cooperative |
To: | Document Control Desk, NRC/FSME |
References | |
LAC-14164 | |
Download: ML110910244 (8) | |
Text
WILLIAM L. BERG President and CEO DAIRYIAND POWER COOP E RAT IV E March 17, 2011 In reply, please refer to LAC- 14164 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 2010 - 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 2010.
If there are any questions concerning this report, please contact us.
Sincerely, DAIRYLAND POWER COOPERATIVE 1&h)awlyh /_
6~
William L. Berg, Preside and CEO WLB: JBM: jkl Enclosures cc/enc: John Hickman, NRC Project Manager Mark Satorius, Regional Administrator, NRC Region III Peter Lee, Decommissioning Branch, NRC Region III A Touchstone Energy Cooperative 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 2010 ANNUAL REPORT PERSONNEL EXPOSURE AND DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602-0817
2010 Dose Distribution Date: 01/14/2011 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 32 32 Meas. < .100 67 1.520 67 1.520
.100 - .250 11 1.451 11 1.451
.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 78 78 Total Monitored 110 110 Total Collective TEDE 2.971 2.971 Total Collective CEDE
APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 2010 Number c/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 REACTOR SURVEILLANCE Maintenance Personnel 0 0 0 0.416 0.000 0.000 Operating Personnel 0 0 0 0.205 0.000 0.000 Health Physics Personnel 0 0 0 0.192 0.000 0.000 Supervisory Personnel 0 0 0 0.050 0.000 0.000 Engineering Personnel 0 0 0 0.032 0.000 0.042 ROUTINE MAINTENANCE Maintenance Personnel 0 0 0 0.026 0.000 0.000 Operating Personnel 0 0 0 0.035 0.000 0.000 Health Physics Personnel 0 0 0 0.004 0.000 0.000 Supervisory Personnel 0 0 0 0.006 0.000 0.000 Engineering Personnel 0 0 0 0.000 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 2 0 5 0.247 0.000 0.937 Operating Personnel 0 0 0 0.200 0.000 0.000 Health Physics Personnel 0 0 0 0.131 0.000 0.000 Supervisory Personnel 0 0 0 0.084 0.000 0.120 Engineering Personnel 0 0 0 0.000 0.000 0.043
APPENDIX A - (cont'd) 2010 Number ofPersonnel(>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 0.026 0.000 0.166 Operating Personnel 0 0 0 0.003 0.000 0.000 Health Physics Personnel 0 0 0 0.006 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 DEFUELING 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 2 0 5 0.715 0.000 1.103 Operating Personnel 0 0 0 0.443 0.000 0.000 Health Physics Personnel 0 0 0 0.333 0.000 0.000 Supervisory Personnel 0 0 0 0.140 0.000 0.120 Engineering Personnel 0 0 0 0.032 0.000 0.085 GRAND TOTAL 2 0 5 1.663 0.000 1.308 MAXIMUM INDIVIDUAL DOSE DURING CALENDAR YEAR: 0.189 Rem - LACBWR Maintenance
DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS 2010 FACILITY MODIFICATIONS The following facility modifications were physically completed in 2010. The changes were performed under the work control process and documented in work order files. Each modification is associated with a specific Work Order (WO). Asummary of the evaluation of each, performed according to 10 CFR 50.59, is included. It was determined that prior NRC approval was not required for these facility modifications.
WO-09-01 LACBWR ISFSI Site Vibro-Compaction and Verification Testing This activity involved the improvement of the soil beneath the LACBWR ISFSI site using the vibro-compaction technique to support the loads projected to be imparted by the concrete ISFSI pad under both static and dynamic (seismic) loading conditions. The activity also included a post-vibro-compaction soil density test to confirm the soil met the minimum specified requirements. All work was accomplished on the ISFSI site located south of the LACBWR facility within the licensed site. The 50.59 screen, prepared in accordance with LACBWR Administrative Control Procedure (ACP) 06.4, "10 CFR 50.59 Evaluations,"
concluded that this activity did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-09-05 Vertical Concrete Cask (VCC) Construction Five VCCs for the NAC-MPC system were constructed on site in accordance with NAC-MPC FSAR and NAC QA program requirements. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this activity did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-09-08 Administration Building Grading and Drainage Work This modification included grading and drainage activities associated with site preparation for the ISFSI Administration Building, parking lot, and heavy haul path south of the lime haul road and east of the ISFSI site. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this modification did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-09-09 ISFSI Outer Perimeter Fence Installation (Owner Controlled Area)
This modification installed woven fabric fencing and gates around the outer perimeter of the area controlled by Dairyland Power Cooperative within which the ISFSI is located. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-09-10 Administration Building Construction and BRE Installation This modification documented the construction of the 30' by 60' ISFSI Administration Building and installation of the attached Bullet Resistant Enclosure. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
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WO-10-03 LACBWR ISFSI Pad Installation The 32' by 48' reinforced concrete ISFSI pad was installed in accordance with NAC-MPC FSAR requirements. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-04 Interference Removal in the Reactor Building Piping and conduits below Reactor Building mezzanine floor north were moved prior to floor supports and cask pool installation. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this modification did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-06 Not Important to Safety ISFSI Perimeter Fencing Installation This activity installed the ISFSI interior perimeter fencing (Protected Area), exterior perimeter fencing (Isolation Zone), and fencing around the ISFSI standby diesel generator. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-10 Install Electrical Security Foundations at the ISFSI This activity involved the necessary grading, buried utilities excavation, culvert work, concrete placement, and fencing installation around the LACBWR ISFSI concrete pad including:
- 1. Camera tower foundations
- 2. Light pole foundations
- 3. Microwave Link and perifield fence foundations and posts
- 4. Cask RTD support structure foundations
- 5. Conduit trenching as required to provide power to the towers and fencing around the ISFSI pad The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-11 Excavation and Backfill of the ISFSI Pad Foundation and Heavy Haul Path Approach Areas This activity included all work and testing necessary to provide the engineered soil subgrade to construct the concrete pad and heavy haul path approach at the appropriate elevation. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that implementation of this modification did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-15 Reactor Building Bio-Shield Liner Work This activity involved the installation of appropriate interfacing modifications to the bio-shield concrete and upper cavity steel liner to ensure water retention in the area between the upper cavity liner, the cask pool, and cask pool gate. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
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WO-10-23 Installation of the Diesel Generator at the ISFSI Administration Building This activity installed an 80-kW diesel generator at the ISFSI Administration Building for standby power.
The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this installation did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-26 Paving of the Heavy Haul Path (HHP) Alongside the G-3 Coal Pile This modification included all necessary erosion control, grading, drainage, buried utilities excavation, culvert work, and road construction to prepare and install the stone paved portion of the HHP along the east side of the G-3 coal pile. The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this modification did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
WO-10-27 Underground Electrical Work at the ISFSI This activity included installation of conduit to light pole foundations, setting camera towers, setting light poles, pulling all cables, installing junction boxes, installing ISFSI lighting, terminating diesel generator, and excavation and installation of all manholes (pull boxes). The 50.59 screen, prepared in accordance with ACP-06.4, concluded that this activity did not require prior NRC approval, that there was no need for any change to Technical Specifications, and that a 50.59 Evaluation was not required.
TESTS There were no tests conducted during 2010.
EXPERIMENTS There were no experiments conducted during 2010.
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