ML13346A142
| ML13346A142 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/16/2013 |
| From: | John Hickman NRC/FSME/DWMEP/DURLD/RDB |
| To: | Berg W Dairyland Power Cooperative |
| Hickman J | |
| References | |
| TAC J52956 | |
| Download: ML13346A142 (7) | |
Text
December 16, 2013 Mr. W. L. Berg President and Chief Executive Officer Dairyland Power Cooperative 3200 East Avenue South P.O. Box 817 La Crosse, WI 54602-0817
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO DAIRYLAND POWER COOPERATIVE REQUEST FOR REVIEW AND APPROVAL OF MAJOR CHANGES TO THE LACROSSE BWR EMERGENCY PLAN (TAC NO. J52956)
Dear Mr. Berg:
The U.S. Nuclear Regulatory Commission is reviewing your request dated August 6, 2013 for a license amendment approving major changes to the LaCrosse BWR Emergency Plan. We have identified additional information we will need to complete our review. Please respond to the attached request for additional information as soon as possible. Should you have any questions or wish to discuss the request for additional information please contact me at 301-415-3017 or by e-mail at John.Hickman@nrc.gov.
Sincerely,
/RA/
John B. Hickman, Project Manager Reactor Decommissioning Branch Decommissioning and Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No.: 50-409 License No.: DPR-45
Enclosures:
Request for Additional Information cc: La Crosse Boiling Water Reactor Service List
Mr. W. L. Berg President and Chief Executive Officer Dairyland Power Cooperative 3200 East Avenue South P.O. Box 817 La Crosse, WI 54602-0817
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO DAIRYLAND POWER COOPERATIVE REQUEST FOR REVIEW AND APPROVAL OF MAJOR CHANGES TO THE LACROSSE BWR EMERGENCY PLAN (TAC NO. J52956)
Dear Mr. Berg:
The U.S. Nuclear Regulatory Commission is reviewing your request dated August 6, 2013 for a license amendment approving major changes to the LaCrosse BWR Emergency Plan. We have identified additional information we will need to complete our review. Please respond to the attached request for additional information as soon as possible. Should you have any questions or wish to discuss the request for additional information please contact me at 301-415-3017 or by e-mail at John.Hickman@nrc.gov.
Sincerely, John B. Hickman, Project Manager Reactor Decommissioning Branch Decommissioning and Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Program Docket No.: 50-409 License No.: DPR-45
Enclosures:
Request for Additional Information cc: La Crosse Boiling Water Reactor Service List DISTRIBUTION: JTapp/RIII ROrlikowski, RIII MNorris, NSIR ML13346A142 OFC DWMEP:PM DWMEP:LA DWMEP:BC DWMEP:PM NAME JHickman CHolston BWatson JHickman DATE 12/13/2013 12/13/2013 12/16/2013 12/16/2013 OFFICIAL RECORD COPY
La Crosse Boiling Water Reactor Service List Mr. Thomas Zaremba Wheeler, Van Sickle and Anderson Suite 801 25 West Main Street Madison, WI 53703-3398 Mr. George Kruck Chairman, Town of Genoa S5277 Mound Ridge Road Genoa, WI 54632 Mr. Jeffery Kitsembel Electric Division Wisconsin Public Service Commission P.O. Box 7854 Madison, WI 53707-7854 Mr. Paul Schmidt, Manager Radiation Protection Section Bureau of Environmental and Occupational Health Division of Public Health Wisconsin Department of Health Services P.O. Box 2659 Madison, WI 53701-2659 Mr. Don G. Egge, Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI 54632-8846 Mr. Jeff McRill, Technical Support Engineer La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Highway 35 Genoa, WI 54632-8846 Regional Administrator Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road Lisle, IL 60532-4352
Enclosure REQUEST FOR ADDITIONAL INFORMATION LA CROSSE BOILING WATER REACTOR LICENSE AMENDMENT REQUEST DOCKET NOs. 50-409 and 72-046 TAC J52956 By letter dated August 6, 2013 (Agency-wide Documents Access and Management System (ADAMS) Accession No. ML13220A953), Dairyland Power Cooperative, Inc. (DPC) requested a license amendment as required by Section 54(q)(ii)(4) to Title 10 of the Code of Federal Regulations (10 CFR) Part 50 for the La Crosse Boiling Water Reactor (LACBWR) Emergency Plan. Specifically, DPC requested review and approval of major changes to the LACBWR Emergency Plan.
The following requests for additional information (RAIs) are required to facilitate the technical review being conducted by the NRC:
RAI 1
, Section 3.0 Proposed Changes, provides in part, All Sections of the LACBWR Emergency Plan (E-Plan) are reformatted and content is structured using Spent Fuel Storage and Transport, Interim Staff Guidance No. 16 (SFST - ISG-16) as a model.
, Section 4.1 Classification of Accidents, provides in part, The LACBWR ISFSI Emergency Plan provides an emergency classification system based on Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors."
, Section 4.2 Emergency Classification Levels (ECL), provides in part, EALs include predetermined values or conditions and are used to determine that the severity of an event has progressed to that which warrants being given the Emergency Classification Level of Unusual Event.
Staff Evaluation Section 3.4 of SFST-ISG-16, provides in part, Regulations for ISFSI installations located away from a reactor site require only one level of emergency classification, an Alert.
NEI 99-01, Rev 6, provides in part,
2 In addition, appropriate aspects of IC HU1 and IC HA1 should also be included to address a HOSTILE ACTION directed against an ISFSI.
10 CFR 72.32(a), provides, Each application for an ISFSI that is licensed under this part which is: Not located on the site of a nuclear power reactor, or not located within the exclusion area as defined in 10 CFR part 100 of a nuclear power reactor, or located on the site of a nuclear power reactor which does not have an operating license, or located on the site of a nuclear power reactor that is not authorized to operate must be accompanied by an Emergency Plan that includes the following information:
(3) Classification of accidents. A classification system for classifying accidents as alerts."
RAI What is the technical basis for removal of the Alert classification in Revision 33 (Revision 32 also) as it was originally approved by the NRC on July 8, 1988 in Revision 10 of the Emergency Plan?
RAI 2
, Table 4.1, provides in part, There are specific dose rates on the VCC to declare an Unusual Event listed in the Table.
, Section 5.4 Radiological Assessment, provides in part, The Security Shift Supervisor (SSS) shall perform the initial assessment of ISFSI dose rates after any natural phenomena event or accident condition. If this assessment indicates increased dose rates an Unusual Event will be declared.
Staff Evaluation 10 CFR 50.47 (b)(9), as exempted for the LACBWR facility, provides, (9) Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.
10 CFR 72.32(a), provides, (4) Detection of accidents. Identification of the means of detecting an accident condition.
RAI Is the SSS qualified to operate radiation monitoring equipment to determine the specific radiation levels to declare the Unusual Event? If so, is the equipment readily available? If not, what is the timeliness of the assessment and classification?
3
RAI 3
, Section 2.0 Background, provides in part, With all spent fuel removed from the LACBWR plant, there are no longer any SAFSTOR accidents previously described in the LACBWR Decommissioning Plan that increase risk to the health and safety of the public.
, Section 4.1 Classification of Accidents, provides in part, The LACBWR ISFSI Emergency Plan provides an emergency classification system based on Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors."
Staff Evaluation NEI 99-01, Rev 6, provides in part, PD-AU1 Release of gaseous or liquid radioactivity greater than 2 times the (site-specific effluent release controlling document) limits for 60 minutes or longer.
RAI Would this EAL be applicable to the LACBWR facility until such time as the facility is decommissioned?
RAI 4
, Section 5.5.2 Background, provides in part, There are no evaluated normal, off-normal, or accident conditions for the NAC-MPC system that result in the breach of the canister and the subsequent release of fission products. For this reason, contamination of individuals at the ISFSI, injured or not, is not a credible event.
A decontamination capability is maintained during plant decommissioning activities and is addressed in the LACBWR Radiation Protection Program and implementing Health and Safety Procedures (HSPs). An emergency Decontamination Kit is maintained at the Plant Administration Building if needed at the ISFSI.
Staff Evaluation 10CFR 50.47(b), provides, (12) Arrangements are made for medical services for contaminated injured individuals.
10CFR 72.32(a), provides in part, (8) Notification and coordination. A commitment to and a brief description of the means to promptly notify offsite response organizations and request offsite assistance, including medical assistance for the treatment of contaminated injured onsite workers when appropriate.
4 RAI After the LACBWR facility is decommissioned, will the ISFSI have the capability to perform decontamination or monitor for contamination?
RAI 5
, Section 3.0 Proposed Changes, page 7 0f 11, provides in part, A change is made from the previous Revision 31 in that the E-Plan exercise will be conducted biennially in accordance with 10 CFR 50, Appendix E (IV)(F)(2)(b).
RAI What is the technical basis for the change from an annual exercise as it was originally approved by the NRC on July 8, 1988 in Revision 10 of the Emergency Plan?
RAI 6
By letter dated July 31, 2013, the NRC approved exemptions to specific emergency planning requirements in 10 CFR 50.47 and Appendix E to Part 50 for the La Crosse Boiling Water Reactor Facility. The La Crosse Boiling Water Reactor facility is the holder of Possession Only License No. DPR-45 which a Part 50 license and is subject to the emergency planning regulations as exempted.
, Section 1.0 Introduction, page 1 of 1, provides in part, This document describes the plan established by Dairyland Power Cooperative (DPC) for responding to emergencies that may arise at the La Crosse Boiling Water Reactor (LACBWR)
Independent Spent Fuel Storage Installation (ISFSI).
RAI Please provide the emergency plan as exempted for the La Crosse Boiling Water Reactor facility.