ML060040301
| ML060040301 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/13/2005 |
| From: | Berg W Dairyland Power Cooperative |
| To: | Document Control Desk, NRC/FSME |
| References | |
| +sispmjr200601, LAC-13890 | |
| Download: ML060040301 (5) | |
Text
LA CROSSE BOILING WATER REACTOR (LACBWR)
DAIRYLAND POWER C OO P E R A T I V E December 13, 2005 In reply, please refer to LAC-13890 DOCKET NO. 50409 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 License Amendment Request
REFERENCES:
(1) LACBWR Possession-Only License No. DPR-45, Appendix A, Technical Specifications (2) LACBWR Decommissioning Plan, Revised November 2005 (3) NRC Letter, Ziemann to Linder, dated February 4, 1980, transmitting Amendment No. 18 to Provisional Operating License No. DPR-45 with NRC Safety Evaluation (4) NRC Letter, Fairtile to Berg, dated April 11, 1997, transmitting Amendment No. 69 to Facility Possession-Only License No. DPR-45 with NRC Safety Evaluation (5) DPC Letter, LAC-5477, Madgett to Director of Nuclear Reactor Regulation, dated September 25, 1978, transmitting NES SIAOS5O, Rev. 2, dated September 20, 1978, "Spent Fuel Shipping Cask Drop Analysis for the La Crosse Boiling Water Reactor" Pursuant to the requirement of 10 CFR 50.90, Dairyland Power Cooperative (DPC) requests the following changes to the LACBWR license Appendix A, Technical Specifications.
These changes are needed to accommodate processing and shipment of Class B and Class C radioactive waste currently stored in the LACBWR Fuel Element Storage Well (FESW). This waste consists of 10 control rods, 2 antimony-beryllium startup sources, 24 stainless steel fuel element shroud cans, and 73 zirconium alloy fuel element shroud cans. These components will be removed, packaged, and disposed of at the Barnwell Waste Management Facility. Removal of irradiated hardware and other B&C wastes has been included in the scope of work during the Reactor Pressure Vessel Removal Project begun in August 2005.
A Touchstone Energy Cooperative __
S4601 State Highway 35 . Genoa, WI 54632-8846
- 608-689-2331 . 608-689-4200 fax
- www.dairynet.com
NRC Document Control Desk LAC-13890 Page 2 December 13, 2005 Currently Technical Specification (TS) 4.1.1.3 of Reference (1) states:
With the exception of a spentfuel shipping cask or transfercask the core spray bundle, the transfercanal shieldplug and the other components andfixtures that are normally locatedand used within the storage well, no objects heavier than afuel assembly shallbe handled over the FuelElement Storage Well.
The proposed wording of the change to TS 4.1.1.3 is as follows:
With the exception of a shipping cask or transfercask, the core spray bundle, the transfer canal shieldplug and the other waste processingcomponents andfixtures weighing less than 50 Tons that are located and used within the storage well, no objects heavierthan a fuel assembly shall be handled over the Fuel Element Storage Well.
The proposed wording of the change to TS 4.1.1.3 contains four discrete changes and are described following.
Proposed Change I DPC proposes to delete the phrase "spentfuel" in describing the type of shipping cask allowed to be handled over the FESW. Shipment of B&C waste located in the FESW will require a cask very similar to the spent fuel shipping cask anticipated in the current TS 4.1.1.3. The waste cask characteristics, weight, size, and handling methods will be conservatively enveloped by the cask drop analyses performed for the LACBWR FESW. The weight of the heavy load drop used in the most limiting analysis was assumed to be 50 Tons in Reference 5, the capacity of the Reactor Building overhead polar crane. The results of these analyses were submitted to the NRC previously and have been found acceptable in NRC staff Safety Evaluations in References 2, 3, and 4. The following statement is found on page 4 of the NRC Safety Evaluation in Reference 4:
The licenseeperformed an analysis ofa shippingcask or otherheavy loaddrop into the pool that assumed loss ofallgap activy in al 333 spentfuel assemblies. This analysis was performed in Section 9.3 of the LACMWR DecommissioningPlan andpreviously found acceptableby the staff, therefore, it is acceptable to allow a transfer cask to be handled over the spentfuel pool.
Proposed Change 2 DPC proposes to add the phrase "wasteprocessing" to describe other components allowed to be located or used in the FESW. The purpose of this change is to include equipment used to accomplish the task of B&C waste removal from the FESW.
NRC Document Control Desk LAC-13890 Page 3 December 13, 2005 Proposed Change 3 DPC proposes to add the phrase "weighing less than 50 Tons' to describe other components and fixtures located and used in the FESW. The purpose of this change is to limit the weight of such items to that found acceptable in the cask drop analyses performed for the LACBWR FESW.
Proposed Change 4 DPC proposes to delete the word "normally" to describe items located and used in the FESW.
The word is ambiguous and does not represent waste and spent fuel disposal operations during the SAFSTOR period. In a limited number of campaigns, equipment will be used in the FESW that is different from that referred to as normally used for fuel handling and fuel storage.
This waste processing equipment is commonly used in the industry for such disposal operations.
Analysis of No Slinificant Hazards Considerations as required by 10 CFR 50.91(a):
(1) Does the proposed change involve a significant increasein theprobabilityor consequences of an accidentpreviously evaluated? NO The shipping cask, whether it is a spent fuel shipping cask or a waste shipping cask, will be handled with the same equipment, under essentially the same LACBWR crane operating procedures and precautions, and will be conservatively enveloped by previous accident evaluations that assumed a heavy load drop weighing 50 Tons. Allowing the placement of typical waste processing equipment in the FESW and the handling of a waste shipping cask limited to weighing less than 50 Tons over the FESW may increase the number of cask movements over the FESW slightly but will not increase the probability nor consequences of an accident previously evaluated during a given cask handling.
(2) Does the proposed change create the possibilityof a new ordifferent kind ofaccident from any accidentpreviously evaluated? NO Simply changing the name of the heavy load handled over the FESW from "spent fuel shipping cask" to the generic term "shipping cask," as long as the heavy loads are limited to the analyzed drop weight of 50 Tons and their methods of handling are essentially equivalent, does not create the possibility of a new or different kind of accident from any accident previously evaluated. Other waste processing equipment will likewise be limited to the analyzed drop weight.
NRC Document Control Desk LAC-13890 Page 4 December 13, 2005 (3) Does the proposed change involve a significantreduction in a margin ofsafety? NO Any shipping cask or other waste processing equipment to be handled over the LACBWR FESW will be conservatively enveloped by the load and conditions in the heavy load drop analysis, which assumed a drop weight of 50 Tons, performed for the LACBWR FESW and, therefore, the TS change will not involve a significant reduction in a margin of safety.
If you have any questions regarding this amendment request, please call Roger Christians, Mike Johnsen, or Dr. Seymour Raffety of my staff at 608-689-2331.
Sincerely, DAIRYLAND POWER COOPERATIVE William L. Berg, President & CEO WLB:SJR:JBM:dh Attachment cc: James L. Caldwell, Regional Administrator U. S. Nuclear Regulatory Commission, Region 1I Kristina Banovac, NRC Project Manager
4/5. PERFORMANCE REQUIREMENTS 4.1 FUEL STORAGE AND HANDLING 4.1.1 GENERAL FUEL STORAGE AND HANDLING REQUIREMENTS 4.1.1.1 Irradiated fuel assemblies shall be stored underwater In spent fuel storage racks that are positioned on the bottom of the Fuel Element Storage Well or In approved on-site dry storage containers, or in an approved shipping cask.
4.1.1.2 During the handling of irradiated fuel assemblies that have been operated at power levels greater than I Mwt, the depth of water in the Fuel Element Storage Well shall be at least 2 feet above the active fuel, and only one fuel assembly will be moved at a time.
4.1.1.3 With the exception of a shipping cask or transfer cask, the core spray bundle, the transfer canal shield plug and the other waste processing components and fixtures weighing less than a cask that are located and used within the storage well, no objects heavier than a fuel assembly shall be handled over the Fuel Element Storage Well.
TS 4/5-1 Amendment 70