ML20214G827
| ML20214G827 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/21/1975 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Maccary R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0036, CON-WNP-36 NUDOCS 8605220543 | |
| Download: ML20214G827 (2) | |
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Note to R. Maccary, Assistant Director for Engineering, TR EVALUATION OF DEYWELL TO WETWELL LEAKAGE FOR WPPSS-2 (TAR-1167) in a memo to R. C. DeYoung, dated May 1,1975, you provided your assessment of the structural aspects of the applicant's study on drywell to wetwell leakage for WPPSS-2 (Mark II containment). The evaluation, however, did not provide us with sufficient information to complete our review of the containment's capability to tolerate drywell to wetwell bypass leakage.
Similar to the approach for Mark III we will need your evaluation of the bypass leakage estimates appearing in the applicant's report related to structural integityy (e.g., the applicant estimates that leakage through the deck will be limited to 0.03 x 10-4 ft2, A/st). This interface was identified on TAR-1167 which we have enclosed for reference. We would also need your recommendation for the factor that should be applied to the containment's bypass capability to establish the acceptance criteria for drywell to wetwell leak tests. You will recall that a factor of one tenth was used on Mark III.
Origital Signed by Robert L. E disco Robert L. Tedesco, Assistant Director for Containment Safety Division of Technical Review
Enclosure:
As stated cc:
C. Lainas S. Hanauer L. Shao F. Schroeder J. Orndoff D. Eisenhut R. Cudlin W. Mcdonald (w/o enc 1)
E. Jacobs J. Kudrick J. Glynn J. Shapaker R. DeYoung A. Giambusso (w/o encl.)
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