ML20199B414

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Forwards Rev 3 to 15737-2-G07-105, ...Heavy Load Handling Inside Containment. Rev Corrects Equations for Handling Loads Over Fuel Canister Storage Racks & Replaces Equation for Load Handling in Fuel Transfer Canal
ML20199B414
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/02/1986
From: Standerfer F
GENERAL PUBLIC UTILITIES CORP.
To: Travers W
Office of Nuclear Reactor Regulation
Shared Package
ML20199B420 List:
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 0436A, 436A, 4410-86-L-0084, 4410-86-L-84, NUDOCS 8606170135
Download: ML20199B414 (1)


Text

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=e mes ar8o Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber:

(717) 948-8461 4410-86-L-0084 Document ID 0436A June 2, 1986 TMI-2 Cleanup Project Directorate Attn: Dr. W. D. Travers Director US Nuclear Regulatory Commission c/o Three Mile Island Nuclear Station Middletown, PA 17057

Dear Dr. Travers:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Safety Evaluation Report for Heavy Load Handling Inside Containment, Revision 3 Attached for your information is the Safety Evaluation Report (SER) for Heavy Load Handling Inside Containment, Revision 3. This revision corrects equations for handling loads over the fuel canister storage racks, replaces the equation for load handling in the shallow end of the fuel transfer canal with a height-weight table and corrects the revision numbers of certain references.

The correction to the load handling guidelines is significant in that it generally reduced the allowable lift height for loads less than 3355 pounds.

Movement of loads weighing greater than 3355 pounds is prohibited over the fuel canister storage racks; consequently, such loads are unaffected by the revision. Because of the reduction in allowable lift heights, GPU Nuclear performed a review in accordance with 10 CFR Part 21 to determine if a substantial safety hazard was created. This review determined that any offsite release resulting from a load drop would constitute a small fraction (i.e., less than 5%) of the 10 CFR Part 100 limits. Therefore, a substantial safety hazard was not created and this deviation is not reportable pursuant to 10 CFR Part 21.

Sincerely, 8606170135 060602 .

PDR ADOCK 05000320 P PDR gW f

. R. Standerfe Vice President / Director, TMI-2 3

1 gh FRS/RBS/cml GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation