ML20214G459
| ML20214G459 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/13/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0048, CON-WNP-48 NUDOCS 8605220170 | |
| Download: ML20214G459 (2) | |
Text
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Distribution:
DEC 131974 Docket File: 50-397 L-Rdg SEB RF Docket No. 50-397 R. C. DeYoung, Assistant Director for Light Water Reactors. Group 1 Directorate of Licensing WPPSS NUCLEAR PROJECT #2 (FORERLY HANFORD #2) - TECHNICAL REPORT WPPSS 2-R5 "DRYWELL TO WETWELL LEAKAGE STUDY" DATED JULY 1974 STRUCTURAL EVALUATION, POSITION AND STATEMENTS (TAR-1167)
Plant Name: WPPSS #2 Docket No.: 50-397 Licensing Stage: Post - CP Review Branch and Project Leader Requesting Assistance: LWR 1-2; J. Orndoff Requested Completion Date: December 15, 1974 Technical Review Branches Involved: Structural Engineering Containment Systems Description of Request: Memo dated October 16,1974 (LWR 1-2; TAR-1167)
Review Status: Waiting for Information In accordance with your request the Structural Engineering Branch, Directorate of Licensing, has reviewed and evaluated structural sections of the applicant's report: WPPSS 2-R5 dated July 1974.
We find that additional infomation is required before we can complete our review. The additional information requested, which concerns structural aspects, is contained in the enclosure.
R. R. Maccary, Assistant Director for Engineering l
Directorate of Licensing
Enclosure:
WPPSS; Request for Additional Information cc w/o enc 1:
cc w/ enc 1:
S. Varga, L A. Gianbusso, L S. Hanauer DRTA D. Eisenhut, L W. Mcdonald, L F. Schr L
W. Butler L R.
r, L R. Tedesco, L J.
.L L. Shao. L
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12/11/74 12/M74 12//974 o,.*
Forse AEC 31S (Rev. 9-93) AECM 0240 W u. s. sovapausar Pmarine opricas is 4. ea e.s ee 8605220170 741213 PDR ADOCK 05000397 A
s ICPSS NUCLEAR PROJECT f 2 (FCRMEF.LY HANFORD f 2)
DOCKET # 50-397 TECHNICAL REPORT (WPPSS 74-2-R5)
"DRYWELL TO WETWELL LEAKAGE STUDY" DATED JULY 1974 STRUCTURAL POSIT!0tl STATEMENTS AND.
REQUEST FOR ADDITIONAL INFORMATION (TAR-1167)
It is the position of the Structural Engineering Branch, Directorate of Licensing that: wherever practical the design criteria and the design methods for the concrete drywell intermediate floor should be in accord-ance with the: " Proposed Standard Code for Concrete Reactor Vessels and Containments" (Proposed Section III. Division 2) ASME Boiler and Pressure Vessel Code.
Therefore, 1.
Provide a statement that the design criteria and the design methods for the intermediate concrete floor are in accordance with the code cited above, and, if exceptions are made, list them:
2.
Justify the omission of a steel liner for the intermediate floor.
3.
Describe the design criteria and design methods for the structural elements supporting this floor and for its connections with the drywell wall.
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