ML090570059

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Dairyland Power Cooperative - Annual Report for 2008 - Report of Changes, Tests and Experiments
ML090570059
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 01/29/2009
From: Berg W
Dairyland Power Cooperative
To:
Document Control Desk, NRC/FSME
References
LAC-14061
Download: ML090570059 (7)


Text

LA CROSSE BOILING WATER REACTOR (LACBWR)

DAIRYLAND POWER

'COOP E RATIVE January 29, 2009 In reply, please refer(to LAC-14061 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 2008 - Report 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 2008.

If there are any questions concerning this report, please contact us.

Sincerely, DAIRYLAND POWER COOPERATIVE William L. Berg, Presiden & CEO WLB: JBM: two Enclosures cc/enc: Kristina Banovac, NRC Project Manager William Snell, NRC Region III Peter Lee, Decommissioning Branch, NRC Region III A Touchstone Energy Cooperative "A----'jc/2 S4601 State Highway 35 ° Genoa, WI 54632-8846

  • 608-689-2331
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La Crosse Boiling Water Reactor (LACBWR)

Possession-Only-License No. DPR-45 2008 ANNUAL REPORT PERSONNEL EXPOSURE AND DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602-0817

2008 Dose Distribution Date: 01/21/2009 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 30 30 Meas. <.100 34 0.867 34 0.867

.100 - .250 6 0.892 6 0.892

.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 40 40 Total Monitored 70 70 Total Collective TEDE 1.759 1.759 Total Collective CEDE

APPENDIX A STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 2008 Number of Personnel (>I100 mRem) I 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 0.000 0.000 0.000 Operating Personnel 1 0 0 0.205 0.000 0.000 Health Physics Personnel 0 0 0 0.100 0.000 0.000 Supervisory Personnel 0 0 0 0.050 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.024 ROUTINE MAINTENANCE Maintenance Personnel 0 0 0 0.189 0.000 0.000 Operating Personnel 0 0 0 0.032 0.000 0.000 Health Physics Personnel 0 0 0 0.0 10 0.000 0.000 Supervisory Personnel 0 0 0 0.03 1 0.000 0.000 Engineering Personnel 0 0 0 0.019 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 1 0.2 10 0.000 0.200 Operating Personnel 0 0 0 0.003 0.000 0.000 Health Physics Personnel 0 0 0 0.0 13 0.000 0.000 Supervisory Personnel 0 0 0 0.003 0.000 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.000 APPENDIX A - (cont'd) 2008 AJmnlwr nfP~r~nnno1 (>lflfl mkom) Tntnl MA/n-Rpm Contract Contract Work & Job Function Station Utility Workers and Station Utility Workers and Employees Employees Others Employees Employees Others WASTE PROCESSING Maintenance Personnel 2 0 0 0.364 0.000 0.000 Operating Personnel 0 0 0 0.042 0.000 0.000 Health Physics Personnel 2 0 0 0.243 0.000 0.000 Supervisory Personnel 0 0 0 0.021 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 1 0.763 0.000 0.200 Operating Personnel 1 0 0 0.282 0.000 0.000 Health Physics Personnel 2 0 0 0.366 0.000 0.000 Supervisory Personnel 0 0 0 0.105 0.000 0.000 Engineering Personnel 0 0 0 0.019 0.000 0.024 GRAND TOTAL 5 0 1 1.535 0.000 0.224 MAXIMUM INDIVIDUAL DOSE DURING CALENDAR YEAR: 0.183 mRem - Plant Electrician DESCRIPTION OF CHANGES, TESTS, AND EXPERIMENTS 2008 FACILITY CHANGES The following facility changes were physically completed in 2008. 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.

17-08-03 Remove Extension Building South Side of WTB An abandoned concrete block building extension (4'W X 4'D X 8'H) was dilapidated and in danger of collapse. The structure was removed from the south side of the Waste Treatment Building. 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.

19-07-25 Set Up Decon Area in Turbine Building Decon sinks removed from the Waste Treatment Building were used in establishing a larger, more easily accessible, and more functional decontamination area in the Turbine Building. 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.

51-07-03 Abandon Primary Purification Pump in Place The purification pump took suction through a nozzle appurtenance on the lower head of the reactor pressure vessel (RPV); the system returned filtered flow to 1B Forced Circulation Pump (FCP) loop. The RPV has been disposed of and FCP loop remnants have been filled with grout. The purification pump was electrically dismantled and abandoned in place awaiting mechanical removal 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.

64-97-11 Remove Main Steam Equipment in Turbine Building Various piping and valves comprising the main steam supply to the turbine, including turbine inlet valves, 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.

74-07-83 Restore 120-V Receptacles and Lighting in Reactor Building For RPV disposal, bio-shield cutting and removal sacrificed some Reactor Building mezzanine level gallery lighting and 120-V receptacles. Temporary services were installed during the project. This change restored normal gallery lighting and receptacles. 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.

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74-08-85 Modify RB MCC Feeds MCA Trip The "Reactor Building MCA Feeds-MCA Trip" control switch, located on the Control Room benchboard provided the capability to de-energize the three 480-V AC motor control centers (MCCs) located in the Reactor Building. Maximum Credible Accident (MCA) was the equivalent of a loss of coolant accident (LOCA). Operation of the MCA Trip control switch, in accordance with the Operating Manual emergency procedure, was a required action in response to a major primary system leak. During MCA conditions, electrical sources in the Reactor (Containment) Building were de-energized prior to flood-up of the building with river water. These shunt trip functions were removed from the Reactor Building MCC feed breakers. One remote trip function, available from the Control Room switch, was maintained for the feed to a power disconnect used to supply the RPV removal lifting device. 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.

75-99-14 Remove Sprinkler Heads and Piping Sprinklers installed over the turbine oil tank obstructed dismantlement of the turbine oil system. Sections of the sprinkler system were removed to clear obstruction. This removal did not decrease the effectiveness of the Fire Protection Program. 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.

91-08-07 Replace 1B LPSW Pump 1B Low Pressure Service Water (LPSW) pump failed mechanically. The 3000-gpm pump was driven by a 150-hp, 2400-V AC, Allis Chalmers motor. Due to reduced LPSW system demand, the unit was replaced by a more economical 600-gpm, 40-hp, 480-V AC, Goulds pump and motor. 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 2008.

EXPERIMENTS There were no experiments conducted during 2008.

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