ML103010320
| ML103010320 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/12/2010 |
| From: | Brasel M Dairyland Power Cooperative |
| To: | Kristina Banovac, John Hickman NRC/NMSS/DWM/DCB |
| References | |
| Download: ML103010320 (3) | |
Text
Hickman, John From: Michael A Brasel [mab@dairynet.com]
Sent: Thursday, August 12, 2010 6:10 PM To: Banovac, Kristina; Hickman, John Cc: Jeff B Mc Rill
Subject:
Re: clarification RAI re: DPC LAR in support of dry cask storage project at LACBWR Attachments: RAI 9a Clarification.pdf Follow Up Flag: Follow up Flag Status: Flagged John and Kris, Attached is our response to the clarification RAI. If you have any questions please call or email me.
Regards, Michael Brasel Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative S4601 State Road 35 Genoa, WI 54632 608.689.4220 Office 608.790.5288 Cell (See attached file: RAI 9a Clarification.pdf)
I-----
I From: I
---I 1"Banovac, Kristina" <Kristina.Banovac@nrc.gov>
ITo: I IMichael A Brasel <mab@dairynet.com>, Jeff B Mc Rill <jbm@dairynet.com>
---I I----- >
I Cc: I I--------->
-- =1
I"Banovac, Kristina" <Kristina.Banovac(anrc.,ov>
---I I Date: I
---I 107/08/2010 07:44 AM
---I I
Subject:
I I----- >
---I Iclarification RAI re: DPC LAR in support of dry cask storage project at LACBWR
---I Good morning, On March 11, 2010, the U.S. Nuclear Regulatory Commission (NRC) sent Dairyland Power Cooperative (DPC) a Request for Additional Information (RAI) on License Amendment Request for La Crosse Boiling Water Reactor, Possession Only License No.
DPR-45, in Support of Dry Cask Storage Project.
By letter dated May 19, 2010, DPC responded to NRC's request for additional information. The NRC staff seeks clarification on the response to RAI 9a.
In the response, DPC notes that the dose from 1-129 to onsite personnel and members of the public is "immeasurable," with Fuel Element Storage Well (FESW) water level maintained at the current technical specification requirement (16 feet). DPC also notes that the dose from 1-129 to onsite personnel and members of the public is "insignificant," with FESW water level at the proposed decreased water level (11 feet, 6.5 inches). Please provide the numerical dose calculation at both water levels, or provide further explanation as to what is meant by "immeasurable" and "insignificant" doses.
Thank you, Kristina Banovac Project Manager Reactor Decommissioning Branch U.S. Nuclear Regulatory Commission 301-415-5114 2
EMAIL DATED 07/08/2010 07:44 AM:
.Good morning, On March 11, 2010, the U.S. Nuclear Regulatory Commission (NRC) sent Dairyland Power Cooperative (DPC) a Request for Additional Information (RAI) on License Amendment Request for La Crosse Boiling Water Reactor, Possession Only License No. DPR-45, in Support of Dry Cask Storage Project.
By letter dated May 19, 2010, DPC responded to NRC's request for additional information. The NRC staff seeks clarification on the response to RAI 9a. In the response, DPC notes that the dose from 1-129 to onsite personnel and members of the public is "immeasurable," with Fuel Element Storage Well (FESW) water level maintained at the current technical specification requirement (16 feet). DPC also notes that the dose from 1-129 to onsite personnel and members of the public is "insignificant," with FESW water level at the proposed decreased water level (11 feet, 6.5 inches). Please provide the numerical dose calculation at both water levels, or provide further explanation as to what is meant by "immeasurable" and "insignificant" doses.
Thank you, Kristina Banovac Project Manager Reactor Decommissioning Branch U.S. Nuclear Regulatory Commission 301-415-5114 DPC RESPONSE:
The term "immeasurable" used in the response to RAI 9a was quoted from the Technical Report (TR), "Determination of the Potential Onsite Radiological Consequences from a Fuel Handling Accident at the La Crosse Nuclear Facility," LAC-TR-1 34, dated April 1988. This TR was submitted to the NRC by letter LAC-1 2544, dated April 15, 1988. The TR provided the technical basis for not requiring Site Area and General Emergency classifications in the LACBWR Emergency Plan, Revision 10. This Emergency Plan revision and supporting TR were approved by the NRC in the Safety Evaluation Report conveyed by letter dated July 8, 1988, having the subject, "Approval of Emergency Plan (TAC 66420)."
DPC has calculated accident doses for 1-129 with water coverage of 16 feet and 11 feet, 61/2 inches. The calculation conservatively assumed that all fuel rods of all 333 spent fuel assemblies in the FESW were damaged. The numeric dose values for the two water levels are:
Dose w/16' (Rem) Water Part 100 Limit Fraction of Part 100 Boundary to the Thyroid Limit to the Thyroid (Rem)
EAB (338 m) 2.26E-02 300 0.008%
EPZB (100 m) 1.05E-01 300 0.035%
Dose w/11 '-61/2" Water (Rem)
EAB (338 m) 5.87E-02 300 0.020%
EPZB (100 m) 2.72E-01 300 0.091%
The calculated accident dose values for 1-129 are well within (i.e., less than 25 percent, or 75 Rem) the 10 CFR Part 100 exposure limit value of 300 Rem to the thyroid.