ML19261F073
| ML19261F073 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/20/1972 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910180686 | |
| Download: ML19261F073 (2) | |
Text
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JUN z 0 M 4
o Richard C. DeYoung, Assistant Director for FWE's, Directorate of Lic.ensing METROPOLITAN EDISON CEPANY - THREE MILE ISLE.'D UNIT 30.1 - DOCKET No.,50-289 s
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The Materials Engineering Branch, L, originally submitted the OL Safety Evaluation for Three Mile Island - Unit 1 by memorandum, Case to Morris, on April 29, 1971. This supplement to that sencrandum completes those areas tret were open iasues. The open issues and their resolution are as follows:
1.
Fracture Toughness Critaria - Delsta the last sentence in the April 29 meno in the Fracture Toughness section 2.
Flywheel Integrity - Delete the final paragraph which was submitted in parentheses 3.
Containment Integrated Leak Tect Program - Rewritten section enclosed.
ec. sistned DY R. R. Maccory ggpg9 R. R. Maccary, Assistant Director for Reactor Safety Directorate of Licensing
Enclosure:
Safety Evaluation for Containment Leak Test Program cc w/encle J. M. Hendrie, L K. Ental, L H. E. Schierling, L 1486 20,6
- 3. S. Pawlicki, L M. B. Fairtile, L cc w/o encle A. Giambusso, L W. C. Mcdonald, L
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I4 THREE L ISLAND 1 CONTAIMENT Leaksee Testine Procram The primary reactor containz::nt and components which will be subjected to contair-ant test conditions will be designed so that periodic integrated leakas rate testing can be conducted at peak accident pressure. We have reviewed the proposed test procedures for determination of the pri=ary containnent overall leakage, as well as penetration and isolation valve leakage, for both preservice and inservice containment leakage tests.
Penetrations, including personnel and equipment hatches and airlocks, and isolation valves, are being designed with the capability of being individually leak-tested at peak accident pressure.
We conclude that the design of the containment system will permit the conduct of the containment leak test program in compliance with the AEC proposed " Reactor Containment Leakage Testing for Water Cooled Power Reactors", 50.54(o), Appendix J, published in the Federal Register on August 27, 1971.
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