ML20057F203
| ML20057F203 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 10/07/1993 |
| From: | Trottier E Office of Nuclear Reactor Regulation |
| To: | Frizzle C Maine Yankee |
| References | |
| TAC-M85794, NUDOCS 9310140287 | |
| Download: ML20057F203 (5) | |
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WASHINGTON, D.C. 20556-0001 October 7, 1993 Docket No. 50-309 Mr. Charles D. Frizzle, President Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336
Dear Mr. Frizzle:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION--MAINE YANKEE PROPOSED AMENDMENT TO RERACK SPENT FUEL STORAGE P0OL (TAC NO. M85794)
The staff has completed a partial review of your request to increase the capacity of the spent fuel storage pool and amend the Maine Yankee Technical Specifications accordingly.
Based on this review, the staff has prepared the following questions:
1.
Please refer to Chapter 9, Installation and Removal Operations, of the Licensing Report (LR) supporting your amendment request dated January 25, 1993:
What loads can the following components of the hoisting system lift a.
before any component part reaches its ultimate stress?
i.
Fuel building overhead crane 11.
Temporary gantry crane (including motorized bridge and trolly) iii.
Lifting rig (including load-to-yield stress)
Iv. Horizontal lifting slings b.
What prevents parts of the temporary gantry crane (the gantry, the motorized bridge or trolly), together with the heavy load being lifted, from falling into the spent fuel pool or damaging dual trains of safe shutdown systems should a seismic event occur?
What are the specific standards (e.g., CMAA-70, NUREG-0554) to which c.
the temporary gantry :rane, and motorized bridge and trolly are designed?
d.' How will load shifting be avoided, in the event of the failure of one leg of the lifting rig?
e.
What is meant by " Free-path test each fuel storage location for acceptability?"
(LR Page 9-2) f.
What is the anticipated minimum separation distance between fuel stored in spent fuel storage racks and em)ty racks being moved in and out of the fuel pool during the rerac(ing process?
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q Charles D. Frizzle October 7,1993 g.
When not in use, what will be the location of the temporary gantry crane, relative to the fuel pool and dual trains of safe shutdown systems?
h.
How does the safe load path minimize the potential for a dropped load to damage spent fuel?
1.
How will the bridge rails be staged to clear a path for an existing spent fuel storage rack?
j.
In the data table presented on LR page 9-6, what is meant by
" Capacity:
20 tons NUREG-0612 useable; ANSI 14.6, 60 ton test" for the temporary gantry crane, and " Rated Capacity:
20 tons NUREG-0612; ANSI 14.6, 60 ton test" for the bridge and trolly?
2.
Please answer the following thermo-hydraulic questions from your submittal:
a.
Table 5.1 of the LR gives 134 degrees Fahrenheit as the maximum spent fuel pool bulk temperature (at inlet to spent fuel heat exchanger) with a normal discharge of spent fuel.
Page 9-55 of the Maine Yankee Final Safety Analysis Report states that the fuel pool cooling system is designed to remove decay heat generated by one-third of an irradiated core and maintain a maximum fuel pool temperature of 100 degrees Fahrenheit. What is the reason for this dif ference?
b.
How many locations in the spent fuel pool contain consolidated fuel elements? What is the expected number of consolidated fuel elements when operating cycle 23 has been completed (final core offload), and has this been considered in the decay heat calculation?
c.
What is the anticipated operation of the spent fuel cooling system during and between refueling?
d.
At what temperature does the deionizer resin start to deteriorate?
How is the resin protected from abnormally high spent fuel pool cooling water temperatures?
e.
Which (if any) of the four alternate methods of cooling the spent fuel pool discussed in the LR can function on loss of offsite power?
As discussed above, these questions result from a partial review of your submittal. We are currently reviewing the balance of your submittal, which may lead to a further request for additional information (RAI). Any further request (s) for additional information will be promptly forwarded to you for a response. Complete and comprehensive responses will assist us in completing our review and preparation of an SE in a timely manner.
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Charles D. Frizzle October 7, 1993 Please do not hesitate to contact me if you have any questions or need additional information to assist you in completing your response to this RAI.
The requirements of this letter affect fewer than 10 respondents, and therefore are not subject to the Office of Management and Budget Review under P.L.96-511.
Sincerely, Original signed by:
E. H. Trottier, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTIQH:
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Charles D. Frizzle October 7,1993 Please do not hesitate to contact me if you have any questions or need additional information to assist you in completing your response to this RAI.
The requirements of this letter affect fewer than 10 respondents, and therefore are not subject to the Office of Management and Budget Review under P.L.96-511.
Sincerely, I
J E. H. Trottier, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
See next page
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I Mr. Charles D. Frizzle Maine Yankee Atomic Power Station cc:
Mr. Charles B. Brinkman Mr. James R. Hebert, Manager Manager - Washington Nuclear Nuclear Engineering and Licensing Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc.
83 Edison Drive 12300 Twinbrook Parkway, Suite 330 Augusta, Maine 04336 Rockville, Maryland 20852 Mr. Robert W. Blackmore Thomas G. Dignan, Jr., Esquire Plant Manager Ropes & Gray Maine Yankee Atomic Power Company One International Place P.O. Box 408 Boston, Massachusetts 02110-2624 Wiscasset, Maine 04578 Mc. Uldis Vanags Mr. G. D. Whittier, Vice President State Nuclear Safety Advisor Licensing and Engineering State Planning Office Maine Yankee Atomic Power Company State House Station #38 83 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Mr. P. L. Anderson, Project Manager Mr. Patrick J. Dostie Yankee Atomic Electric Company State of Maine Nuclear Safety 580 Main Street Inspector Bolton, Massachusetts 01740-1398 Maine Yankee Atomic Power Company P. O. Box 408 Regional Administrator, Region I Wiscasset, Maine 04578 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Graham M. Leitch King of Prussia, Pennsylvania 19406 Vice President, Operations Maine Yankee Atomic Power Company First Selectman of Wiscasset P. O. Box 408 Municipal Building Wiscasset, Maine 04578 U.S. Route 1 Wiscasset, Maine 04578 Mr. J. T. Yerokun Senior Resident Inspector Maine Yankee Atomic Power Station U.S. Nuclear Regulatory Commission P. O. Box E Wiscasset, Maine 04578
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