ML19276H294
| ML19276H294 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/04/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910160638 | |
| Download: ML19276H294 (2) | |
Text
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Docket File 50-289 L-Rdg SEB RF Docket No. 50-289 Voss A. Moore, Jr., Assistant Director for Light Water Reactors, Group 2 Directorate of Licensing METROPOLITAN EDISON COMPANY - THREE MILE ISLAND STATION, UNIT fl RING GIRDER SURVEILLANCE REQUEST FOR STRUCTURAL INFORMATION, FSAR REVIEW Plant Name: Three Mile Island Unit #1 Licensing Stage:
FSAR Review Docket Nimber:
50-239 Responsible Branch and Project Manager:
Light Water Reactors Branch 2-2; R. M. Bermero Requested Completion Date: January 7,1974 Applicant's Response Date Necessary for Ccapletion of Next Action Planned on Project: N/A Description of Response: Report Review Status: Awaiting additional infomation The review of the applicant's report " Reactor Building Ring Girder -
Surveillance Report" dated November 1973 has been completed by the Structural Engineering Branch and we find that additional information is required before we can complete our review. The additional infor-mation requested, which concerns structural aspects, is contained in the enclosure.
The material reviewed to date consisted of information provided in the report ci,ted above.
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R. R. Maccary, Assistant Director for Engineering Directorate of Licensing
Enclosure:
Request for Additional Information for Three Mile Island, Unit #1 cc w/o enc 1:
cc w/ encl:
J4l9 yUn A. Giambusso, L
- 5. Hanauer DRTA L. Shao, L W. Mcdonald, L J. Hendrie, L R. Bernero, L S. Yarga, L A. Gluckmann, L A. Schwanear. I f
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+43.cn Form AEC Ste t Rev. 9.U) AECM 3240
.ETROPOLITAN EDISON CDM?ANY THREE MILE ISLAND STATION, UNIT # 1 (DCCKET #50-289)
APPLICANT'S REPORT ENTITLED " REACTOR BUILDING RING GIRDER -SURVEILLANCE REPORT" DATED NOVEMBER 1973 REOUEST FOR ADDITIONAL STRUCTURAL INFORMATION The cited report does not include any information on the repaired ring girder surveillance durina the acceptance test.
It is essential to knew the behavior of the girder at that time.
Therefore:
1.
Describe the procedure which will be used to observe the behavior of the girder durina the acceptance test of the containment; this procedure should cover at least the observation of deformations, stresses and cracking patterns.
2.
Provide a comparison with predicted deformations, stress and/or strain values, and cracking patterns and the observed values cetore prestressinc, during prestressing and during and after the acceptance test.
Discuss any discrepancies between the predicted and the observed values.
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