ML20030A565
| ML20030A565 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/01/1974 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101100064 | |
| Download: ML20030A565 (3) | |
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%gulal0ry Docket File el July 1, 1974 Acq
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-4 Mr. Karl R. Goller Re:
Docket 50-155 Assistant Director for Operating Reactors License DPR-6 Directorate of Licensing US Atomic Energy Commission Washington, DC 205b5
Dear.Mr. Goller:
By letter dated February 4,1974, it vas requested that we pro-vide an analysis and other relevant information needed to determine the possible damage in the event of a cask drop caused by a system failure and whether design or procedural modifications would be appropriate to reduce the probability of occurrence for our Big Rock Point Plant. This study of a postulated cask drop accident was performed by Bechtel Corporation at Consumers Power Company's request. The results of this study are con-tained in Attachment A.
The results of this analysis reveal that a cask being dropped into the spent fuel pool could result in a leak in the fuel pool which might be larger than the makeup capcbility of the backup systems. The decay heat being generated inside each fuel pin would eventually melt the fuel pin cladding. The resulting site boundary dose with more than ten (10) bundles in the fuel pool would exceed those limits as specified in 10 CFR 100.
In order to eliminate this potential cask drop accident as well as other less severe cask drop accidents from occurring, detailed modifi-cations to the present procedures, equipment and structures are proposed.
These proposed modifications were based on a multilevel concept of system safety and include:
1.
Modifications of the crane coupled with detailed handling procedures to eliminate the possibility of a cask drop.
2.
Limit-switches and specific cask movement paths minimize possible endangered areas and restrict the maximum drop heights.
3 Poter ;ial impact areas inside those restricted areas are protected if necessary and the fuel bundles relocated to provide a further safety factor.
V/O//Qoo&Y
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Mr. Kerl R. Goller 2
Docket 50-155, License DPR-6
-July 1, 1974 In addition, the low usage factor of the crane for those weights approaching the crane capacity help to minimize stresses in the crane systems and, therefore, _significantly reduce any probability of failure. The 60-ton refueling cask is expected to be utilized only two to three times per year.
The procedures as described above are being written and imple-mented while the modification to the crane and the fabrication and instal-lation of the impet pad will be initiated upon your approval of these recommended modifications.
It is estimated that these modifications can be completed within one year of receipt of your approval.
Yours very truly, 5
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JSR/ map R. B. Sewell-Nuclear Licen:ing Administrator CC; JGKeppler, USAEC J
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DATE OF DOC DATE REC'D LTR TWX RPT OTHER
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Consumers Power Company J2ckson, Michgian 49201 7-1-74 7-3-74 x
R. B. Sewell TO '.
K. R. Coller 1 sigced SENT LOCAL PDR__
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PROP INFO IhPUT NO CYS REC'D DOCKET NO:
xx 40 50-155 DESCRIPTION:
ENCLOSURES:
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Information on Postulated cask drop accident aw /kpphJak ACKNOWLEDGED DO NOT REMOVE PLANT NAIT,. Big Rock Point
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