ML19326C479
| ML19326C479 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/19/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 1-078-13, 1-78-13, NUDOCS 8004230602 | |
| Download: ML19326C479 (5) | |
Text
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2 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50--313 REC: REID R W ORG: WILLIAMS D H DOCDATE: 07/19/78 NRC AR PWR & LIGHT DATE RCVD: 07/25/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 40 FURNISHINO REQUEST FOR REVIEW AND CONCURRENCE OF ENCL RESULTS OF AN ANALYSIS TO ALLOW HANDLING OF A 25 TON CASK (NAC-1) IN THE FUEL HANDLING & STORAGE AREA (ELEVATION 404) AT SUBJECT FACILITY. TO ALLOW SHIPMENT OF B4C TEST RODS TO BLW DURING CYCLE 2 OPERATToAs l:52.r-D ELOG6 T't MAAJC4(
PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL: R 0o000o***********
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
BR CHTFr NBM4 BC**W/7 ENCL wf DRW65 INTERNAL:
REG FI
/ ENCL NRC PDR**W/ ENCL
- W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJ**W/CNCL ENGINEERING BR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S RUSSELLVILLE, AR**W/ ENCL TERA **W/ ENCL 3
NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NBR:
h SIZE: 2P+2P+3P
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ARKANSAS POWER & LIGHT COMPANY i;
IJ POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-40d0 I
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q 1-078-13 Director of Nuclear Reactor Regulation ATTN:
Mr. R. W. Reid, Chief Operating Reactor Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No.
DPR-51 Cask llandling (File:
1510)
Gentlemen:
a We hereby request your review and concurrence with the attached results of an analysis to allow handling of a 25 ton cask (NAC-1) in the fuel handling and storage area (elevation 404) at Arkansas Nuclear One -
Unit 1 (ANO-1).
Your approval of our request would allow shipment of B C test rods to Babcock 6 Wilcox following irradication during cycle 4
2 operation.
Currently the ANO-1 Technical Specifications de not allow a spent fuel shipping cask to be carried by the auxiliary building crane.
This ensures that a spent fuel cask drop accident cannot occur prior to com-pletion of your staff's review of our design to preclude this potential accident or mitigate its consequences.
Our analysis (see Attachment 1) was performed assuming a 25 ton cask was dropped onto the fuel handling arca floor.
Ca::
~ assumed a drop of three (3) inches travel with no hexagonal honeycomb. Case II assumed a drop of nine (9) inches travel with two (2) inches of hexagonal honeycomb separating the cask bottom and the floor.
Concrete and reinforcement strength values used were actual versus design. The crane and handling equipment, and their control, is described in section 5.2.2 of the ANO-1 FSAR and further described in section 9.1.4.2.10 of the ANO-2 FSAR. The auxiliary building crane was tested upon completion of crection to lift and handle 130 tons.
In neither case was damage to the concrete floor allowede
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-078-13 Mr. R. W. Reid July 19, 1978 While the result of Case I were found to be acceptable, we propose to use the two (2) inches of hexagonal honeycomb material and' limit the travel height to nine (9) inches (Case II). We therefore feel a more than adequate margin of safety is shown to allow handling of this cask.
Attached for your information in reviewing our request is one set of fuel handling area drawings showing proposed travel paths for the 25 ton shipping cask. Your expeditious review and approval of this request will allow shipment of the test rods before decay reduces their usefulness.
Very truly yours, t-WC Daniel 11. Williams Manager, Licensing DilW/DGM/ew Attachment
Attechmtnt 1
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paga 1 of 2 DROP EVALUATION
SUMMARY
FOR
' THE 25 TON HANDLING CASK AT ELEVATION 404 (Over Control Room)
DATA Concrete Str eng th, fc', = 4,850 psi at 28 days (pour No. 517)
Reinforcement Str eng th, fy, = 48,300 psi from mill certificate Hexagonal Honeycomb - by Hexcel Standard Products Strength, fct, = 260 psi - 2 inches thick Loading Combination Evaluated Y =--
-(1.0 D + 1.0 CD) re 211.0 D+CD j
Capacity 2.1.0 Computed Y - Ultimate capacity D - Dead Load -
3'-9" slab plus 25 psf (dunage and personnel)
CD - Cask Loading Structural Capacities The capacities were developed using Bechtel BC-TOP-9 and the ult $ mate strength values from ACI 318-63 equations Shear capacity
= 807 kips Moment capacity
= 6,345 kip-ft Bond stress capacity = 543 psi Drop _ Analysis The analysis was based on Bechtel BC-TOP-9.
Shear, moment, and bond stress were computed for two cases as follows:
Case I
- A drop evaluation for 3" travel height with no hexagonal i
honeycomb.
Case II - A drop evaluation for 9" travel height with 2 inches of hexagonal honeycomb.
I Paga 2 of 2
. Efpulting, Safety _ Factors (Based on Ultimate Strength Design Methada)
Case I Shear; shear capacity 807 kips
= 1. 03 > 1. 0
=
shear computed 780 kips Moment; moment capacity 6345 kip-ft
= 1.15 > 1.0
=
moment computed 5506 kip-ft Bond; bond stres's capacity 543 psi
= 3.07 > 1.0
=
bond stress computed 177 psi Case II Shear; shear capacity 807 kips
= 2.01 > 1.0
=
shear computed 401 kips Moment; moment capacity 6345 kip-ft
= 2.22 > 1.0
=
moment computed 2859 kip-ft Bond; bond stress capacity 543 psi
-= 5.84 > 1.0 bond stress computed 93 psi s
.-