ML20041F133
| ML20041F133 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/12/1982 |
| From: | Rausch T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 3616N, NUDOCS 8203160219 | |
| Download: ML20041F133 (3) | |
Text
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0 h Commonwealth Edison C
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Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation W
'S U.S. Nuclear Regulatory Commission
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Washington, DC 20555 3
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Subject:
Quad Cities Station Units 1 and 3 cc Transmittal o f Supplement 8 to Revision 1 of the Licensing Report on High Density Fuel Racks NRC Docket Nos. 50-254 and 50-065 t
Reference (a):
D. V.
Vassallo letter to L. DelGeorge dated February 8, 1982.
Dear Mr. Denton:
i Enclosed is Supplement 8 to Revision 1 o f the report prepared by Joseph Oat Corporation for Commonwealth Edison entitled
" Licensing Report on High Density Fuel Racks for Quad Cities Units 1 and 2."
This supplement provides resposes to the questions provided i
in Reference (a).
These responses are for questions numbered as follows:
12.5.1 12.5.2 Please address any questions you may have concerning this matter to this office.
One (1) signed original and thirty-nine (39) copies of this transmittal are provided for your use.
Very truly yours, h
"*h Thomas J. Rausch g)
Nuclear Licensing Administrator 1m j
Enclosure cc:
Region III Inspector - Quad Cities 3616N 8203160219 820312 PDR ADOCK 05000254 i
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k 12.5 Questions from D.B. Vassallo to L.
DelGeorge transmitted on February 8, 1982 12.5.1 Question:
Provide sufficient information, on the rigging to be used in removing the existing storage rack, to permit an independent evaluation of its adequacy.
Section 3.3 of the 11/2/81 Supplement #5.
Response
A locking safety hook and wire rope sling meeting the appropriate requirements of ANSI B30.9-1971 will be used to remove the existing storage racks.
The specific requirements for wire rope slings identified in Chapter 9-2 will be met by using a 4 ton double wire rope sling for lifting the 1850# existing racks.
With the weight of existing racks being well below 10,000#, the additional requirements of ANSI N14.6-1978 would not apply.
12.5.2 Question:
For both the rigging identified above and the yo'ke lifting device described in Section 3.3 of Supplement
- 5 identify, describe and discuss all areas where the 4
applicable requirements of ANSI B 30.9-1971 and/or ANSI N 14.6-1978 are not met.
Response
For the sling for removing the existing storage racks, all applicable requirements of ANSI B 30.9-1971 will be met, except as noted below:
The operating practices of Section 9-2.9 have not been i
reviewed in detail.
Operations will be in accordance with station procedures and as submitted in response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants.
f For the lifting device described in Section 3.3 and Figure 3-8 of the Licensing Report all applicable requirements of 4
I ANSI B 30.9-1971 and ANSI N 14.6-1978 will be met, except as noted below:
Acceptance testing, maintenance, and assurance of con-tinued compliance as specified in Section 5 of N 14.6 will be applied and controlled through station procedures and as submitted in response to NUREG-0612.
6
e 1
The critical load requirements of Section 6 of N 14.6 are not considered applicable for the new rack instal-1ation process.
However, several of-the requirements 8
4 such as the use of fail safe crane systems, single component failure criteria, and maintenance of vertical load balance during the lift will be employed.
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