ML20004C122
| ML20004C122 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/27/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8106010559 | |
| Download: ML20004C122 (2) | |
Text
Y TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II May 27, 1981 Director of Licensing Attention:
Mr. Thomas A. Ippolito, Chief Operating Reactors Branch No. 2 U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Ippolito:
In the Patter of the
)
Docket No. 50-259 Tennessee Valley Authority
)
50-260 50-296 My letter to you dated February 10, 1981, responded to questions transmitted by T. M. Novak's letter to H. G. Parris dated August 4, 1980, regarding the Browns Ferry Nucicar Plant reactor 5uilding crane. Enclosed is our revised response to several of f.hese questions. Additionally, the interim guidelines of NUREG-0612 have been implemented at Browns Ferry and a periodic inspection of the reactor building crane was performed in April to ensure compliance with ANSI B30-2.0-1976.
NUREG-0612 states that only two options are provided for control of
" heavy loads" on a BWR refuel floor; either the reactor building crane must meet the single failure proof criteria provided in NUREG-0559 or all heavy loads must be analyzed to verify that, if dropped, they do not constitute a release of radioactivity to the general public. These criteria are not met by the Browns Ferry reactor building crane and the latter option does not appear to be economically feasible. Therefore, before scheduling testing or initiating modifications on the Browns Ferry crane as delineated in our initial response, we request confiratation from NRC verifying that the Browns Ferry reactor building crane will be acceptable if these actions are taken, iery truly yours, TENNESSEE VALLEY AUTHORITY n
I M. Mills, Manager Nuclear Regulation and Safety Subscribe
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J Notary Public My Commission Expires Enclosure E10601og59
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o ENCLOSURE
+.
REVISED RESPONSE TO T..M. NOVAK'S AUGUST 4, 1980, LETTER TO H. G. PARRIS BROWNS PERRY NUCLEAR PLANT 6.
The auxiliary hoist is used in handling some critical loads.
The maximum critical. load (MCL) handled by the auxiliary hoist is limited by the Browns Ferry Technical Specification to 1,000 pounds over spent fuel assemblies in the spent fuel storage pool. The design rated load (DRL) and maximum working load (MWL) is five tons.
7.
For a MCL of 1,000 pounds for the auxiliary hoist the mar' aus dynamic rope stress is 2.08 percent of the breaking strength.
9b.
All slings used on the refuel floor have been proof-load tested as specified in ANSI B30.9-1071. Some slings used on the refuel floor are not tagged for intended use.
.