ML19256D742
| ML19256D742 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/07/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910220669 | |
| Download: ML19256D742 (2) | |
Text
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'4 UNITE D STAT E S
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NUCt. EAR REGULATORY COMMISSION 7 I ) l' !
WASHINGTON, D. C. 20555
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MAR 0 71977 I
MEMORANDUM FOR:
K. R. Goller, Assistant Director for OR, D0R FROM:
D. G. Eisenhut, Assistant Director for OT, D0R
SUBJECT:
METROPOLITAN EDISON COMPANY - SPENT F'JEL P0OL MODIFICATION (TAC:
6545)
Plant Name: Three Mile Island Nuclear Station Unit 1 Licensing Stage: Operating Plant Docket No.: 50-289 Document Reviewed: Spent Fuel Pool Modification Description and Safety Analysis Report dated January, 1977 Branch and Project Manager Requesting Assistance: OBR 4, G. B. Zwetzig Requested Completion Date: March 4, 1977 Operating Reactors Branches Involved: Engineering Branch, Plant Systems Branch, Environmental Evaluation Branch Description of Request: TAC 6545 Review Status: Requesting Additional Information The Engineering Branch, Division of Operating Reactors has reviewed the structural, mechanical and materials aspects of the information submitted by Metropolitan Edison Company in a report entitled "Three Mile Island Nuclear Station Unit 1 Spent Fuel Pool Modification Description and Safety Analysis".
We find that before we can complete o r review, additional information, as indicated in the enclosure, is nec ssary.
- isenhut, s
nt Director for Operational Technology Division of Operating Reactors
Enclosure:
As Stated cc:
V. Stello L. Shao R. Reid R. Stuart G. Zwetzig K. Jabbour S. Hosford 7 910220 h['
CONTACT:
S. Hosford, 28060
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ENGINEERING BRANCH DIVISION OF OPERATING REACTORS Metropolitan Edison Company Three Mile Island Nuclear Station Unit 1 Spent Fuel Pool Modification REQUEST FOR ADDITIONAL INFORMATION c
1.
Provide a detailed summary of the stress margins due to the increoL-d loading of the fuel pool walls and floor for the critical load combinations.
Include a discussion of the possibility of shear failures in the areas of contact of the rack supports with the floor and walls. Compare numerically these results to those for the previous rack structure.
2.
Provide the components of the stress value given in Table 5-2 for load combination "d" (as defined in Section 5.1.2) at grid beam location.
3.
Provide justification for neglecting any amplification of the seismic loads, transferred to the rack analyzed, due to the flexibility of the fuel cans in the adjacent racks.
I453 20L5 5
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