ML20249A688
| ML20249A688 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/15/1998 |
| From: | Michael Webb NRC (Affiliation Not Assigned) |
| To: | Meisner M Maine Yankee |
| References | |
| TAC-MA0659, TAC-MA0660, TAC-MA659, TAC-MA660, NUDOCS 9806180101 | |
| Download: ML20249A688 (4) | |
Text
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l Mr. Michul J. M:isn:r, Prerid:nt June 15, 1998 M: ins Ycnkes Atomic Powar Company P.O. Box 408 Wiscasset, Maine 04578 i
l
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION FOR EXEMPTION FROM l
FINANCIAL PROTECTION REQUIREMENT LIMITS (TAC NOS. MA0659 AND MA0660)
Dear Mr. Meisner:
l We are conducting our review of your proposed exemptions to certain insurance coverage and financial protection requirement limits of 10 CFR 50.54(w) and 10 CFR 140.11, as detailed in your letter to us dated January 20,1998. However, in order for us to complete our evaluation of the spent fuel heatup analysis that you conducted to determine the time 1
at which the Maine Yankee fuel would not exceed 565*C should the spent fuel pool be drained of all water, we require additional information as specified in the enclosed. This request affects nine or fewer respondents and therefore, is not subject to Office of Management and budget review under P.L.96-511.
If you have any questions regarding this request, please contact me at (301) 415-1347.
Sincerely, 1
ORIGINAL SIGNED BY:
Michael K. Webb, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosure:
As stated cc w/ enclosure: See next page i
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%, *****p June 15, 1998 Mr. Michael J. Meisner, President Maine Yankee Atomic Power Company P.O. Box 408 Wiscasset, Maine 04578 l
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION FOR EXEMPTION FROM FINANCIAL PROTECTION REQUIREMENT LIMITS (TAC NOS. MA0659 AND MA0660)
Dear Mr. Meisner:
We are conducting our review of your proposed exemptions to certain insurance coverage and financial protaction requirement limits of 10 CFR 50.54(w) and 10 CFR 140.11, as detailed in your letter to us dated January 20,1998. However, in order for us to complete our evaluation of the spent fuel heatup analysis that you conducted to determine the time at which the Maine Yankee fuel would not exceed 565 C should the spent fuel pool be drained of all water, we require additional information as specified in the enclosed. This request affects nine or fewer respondents and therefore, is not subject to Office of Management and budget review under P.L.96-511.
If you have any questions regarding this request, please contact me at (301) 415-1347.
Sincerely,
'/l b Y 2 d d b Michael K. Webb, Project Manager Non-Power Reactors and Decomn.issioning Project Directorate Division of Reactor Program Managemen+.
Office of Nuclear Reactor Regulation Docket No. 50-309
Enclosure:
As stated cc w/ enclosure: See next page
e Maine Yankee Atomic Power Station Docket No. 50-309 cc:
Mr. Charles B. Brinkman Friends of the Coast Manager - Washington Nuclear P.O. Box 98 Operations Edgecomb, ME 04556 ABB Combustion Engineering 12300 Twinbrook Parkway, Suite 330 Mr. William O' Dell Rockville, MD 20852 Operations Director Maine Yankee Atomic Power Company Thomas G. Dignan, Jr., Esquire P.O. Box 408 Ropes & Gray Wiscasset, ME 04578 One International Place Boston, MA 02110-2624 Mr. George Zinke, Director Nuclear Safety and Regulatory Affairs Mr. Uldis Vanags Maine Yankee Atomic Power Company State Nuclear Safety Advisor P.O. Box 408 State Planning Office Wiscasset, ME 04578 State House Station #38 Augusta, ME 04333 Mr. Jonathan M. Block Attorney at Law Mr. P. L. Anderson, Project Manager P.O. Box 566 Yankee Atomic Electric Company Putney, VT 05346-0566 580 Main Street Bolton, MA 01740-1398 Mr. Michael J. Meisner, President Main Yankee Atomic Power Company Regional Administrator, Region i P.O. Box 408 U.S. Nuclear Regulatory Commission Wiscasset, ME 04578 475 Allendale Road King of Prussia, PA 19406 Mr. Robert Fraser, Director Engineering First Selectman of Wiscasset Maine Yankee Atomic Power Company Municipal Building P.O. Box 408 U.S. Route 1 Wiscasset, ME 04578 Wiscasset, ME 04578 Mr. Patrick J. Dostie Mr. Richard Rasmussen State of Maine Nuclear Safety Senior Resident inspector inspector Maine Yankee Atomic Power Company Maine Yankee Atomic Power Company U.S. Nuclear Regulatory Commission P.O. Box 408 P.O. Box E Wiscasset, ME 04578 Wiscasset, ME 04578 Mr. Mark Ferri Mary Ann Lynch, Esquire Decommissioning Director Maine Yankee Atomic Power Company Maine Yankee Atomic Power Company P.O. Box 408 P.O. Box 408 I
Wiscasset, ME 04578 Wiscasset, ME 04578 1
l
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I e
REQUEST FOR / DDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ASSESSMENT OF THE LOSS OF WATER FROM THE SPENT FUEL POOL AT MAINE YANKEE (MY) ATOMIC POWER STATION
- 1. The information submitted by MY does not contain sufficient information about the building temperature during the scenario being analyzed. Provide your building temperature analysis.
- 2. The information submitted by MY does not contain sufficient information about the basis for the decay heat used in your analysis. Provide the supporting information for your decay heat values. This should include detailed information about your experimental measurements and the method used to reduce the data. Compare the decay heat used by MY to the current ANS decay heat standard and describe your treatment of uncertainties.
- 3. The information submitted by MY does not contain sufficient information about the adequacy of TRAC for the analysis. Provide information that demonstrates that the models contained in TRAC (including heat transfer and wall drag correlations) are adequate for the geometry and conditions that are being analyzed include any information about code assessment applicable to the conditions MY is using the code for.
- 4. The information submitted by MY does not contain sufficient information about the adequacy of the modeling approach used in the analysis. Provide information showing that the additive form loss coefficients used in the analysis are appropriate for the geometry and flow conditions present in the analysis. Also provide information showing that the single hot channel modeling results are conservative compared to an approach that would include parallel flow paths through lower powered bundles.
5, TRAC and other NRC computer codes are not developed and maintained under an Appendix B QA program. Computer coaes used by the industry in regulatory analyses must meet Appendix B QA standards. This means that someone has to verify that the models are correctly coded in TRAC and that code assessment must be performed to show that the code is adequate for the analysis. Please certify that the version of TRAC used in the analysis meets Appendix B QA standards.
C. Provide a discussion of the available margin determined by the analysis and an estimate of the calculation uncertainties.
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ENCLOSURE
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