ML20079N845
| ML20079N845 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/04/1991 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19336D681 | List: |
| References | |
| 1CAN10905, NUDOCS 9111120045 | |
| Download: ML20079N845 (3) | |
Text
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hfCMV Entsrgy OperaHons,Inc.
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mcusse-October 4, 1991 1CAN109105 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555
Subject:
_Arkannas Nuclear One - Unit.li Docket N". 50-313 License No. DPR-51 Technical-Specification Change Request.
Revised Detail Engineering Calculation:
Auxiliary. Building Crano Gentlemen:
On September 20, 1991, a conference call was conducted between tim AND-1 NRR Project. Manager, the NRC Staff Technical Review and members of the.
ANO Design Engineering and Licensing organization.
The purpose of this call was_to provide clarifying information with respect tolthe-calculation submitted in Entergy's letter of August 22, 1991 (ICAN089106). This calculation was submitted in support of;the ANO-_1, Technical Specification Change Request dated June-27,11991 (1CAN069104).
This Technical Specification Change Request:would allow-an' exception tol a
ANO-1-Technical' Specification 3.8.15_,- which currently prohibits?the use=
of the Auxiliary Building crane for._ spent fuelishipping cask mcvement.
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The calculation demonstrates, assuming a failure of the Auxil1~ry n
Building crano, that a dropped 17-ton cask with a 28-inch diameter would be supported by the floor slab which:the cask will travel over and that-the concrete _will not spall to cause damage to equipment below the slab.,
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Based:upon this telephone conversation, Entergy Operations has revised calculation 91-E-0094 to clarify.the' points. discussed. This revised calculation is attached-for your information'.': Also provided,.isia copy-of the design data bulletin published-by llexcel', which was utilized in-our1 calculation:to predict the energy absorbtion properties of the-crushable material to he placed'under the-caskLif raised _ greater:than.3-inches above.the floor. : If a dif ferent-typr of material,is utilized,- an -
l Engineering evaluation willLbe' conducted _to assuro its energy abscrbing-proporties are equni to or greater than that ' assumed in calculation :
91-E- 0094- 01.
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t U. S. NRC October 4, 1991 Page 2 We trust this additional information will assist you in your review of the Technical Specificacion Change Request.
Should you have any additional questions, please contact my office.
Very truly yours, d'/W&
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[ James J.
1sicato Director, Licensing JJF/DEJ/sjf Attachments cc:
Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-D-23 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Ms. Sheri Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-D-23 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852
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-f*va Ad.dh t'R0t1 FEXCEL PRINGTON TO 1S015546579
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HEXCEL CORPORATION
$b First City Bank Building 201 E. Abrem. Suho 570 Ailington. TX 7M10 -
PHONE #
(817) 274-2578 FAX #:
(817) 274-1121-DATE:
OCTODER 25, 1991 ATTN:
LORI POTTS LOCATION:
COMPANY:'
ENTERGY OPCRATIONS, INC.
FAX #:
FROM:
"I* RODGERS/SR LOCATION:
ARLINGTON SALES
SUBJECT:
DATA SHEET (TSTC 122 COVER PLUS:
0 PAGE(S) m x__
l PER OUR TELECON THIS DATE, IT IS OK To t@XE COPICS OF THE T50122 FOR INTERNAL USE AT NRC.
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