ML19332A649
| ML19332A649 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/22/1980 |
| From: | Pawlicki S Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009160592 | |
| Download: ML19332A649 (2) | |
Text
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-4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION t;
WASHINGTON, D. C. 20555
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N3 S2 Docket No. 50-395 MEMORANDUM FOR:
A. Schwencer, Chief Licensing Branch 2 Division of Licensirg FROM:
S. S. Pawlicki, Chief Materials Engineering Branch Division of Engineering
SUBJECT:
V. C. SUMMER CONTAINMENT PRESSURE BOUNDARY FRACTURE TOUGHNESS, SER INPUT Attached is the Materials Engineering initial SER input for Containment Pressure Boundary Fracture Toughness for V. C. Sumer.
The containment pressure boundary is constructed using materials meeting the requirements fo ASME Section III; however, our licensing reviews, including those for V. C. Summer. do not include evaluation of explicit compliance with these codes. Consequently, to complete our final SER for V. C. Summer in re-sponse to the July 18, 1980 memorandum D. G. Eisenhut to R. H. Vollmer we reouf re the following information:
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1.
Identification of the fabrication codes (edition and addenda) and the specific paragraphs in these codes that specify the fracture toughness requirements and acceptance criteria (for weldments and base metals).
Codes and code paragraphs should be identified for all materials which constitute part of the containment pressure boundary (e.g., piping penetrations, personnel airlocks; equipment hatch).
2.
The materials test data that certify that the fracture toughness acceptance standards have been met for each of the identified materials in the con-tainment pressure boundary.
w S. S. Pawlicki, Chief M
Materials Engineering Branch Division of Engineering j
1 cc:
R. H. Vollmer R.L.Tedesco!
V. S. Noonan W. Kane R. M. Gamble W. S. Hazelton B. D. Liaw J. Halapatz 8009160 N 2 L
r V. C. SUMMER SAFETY EVALUATION REPORT INPUT 6.5 Containment Pressure Boundary Fracture Toughness The fracture toughness of the ferritic materials that constitute the contain-ment pressure boundary of the V. C. Summer nuclear plant was reviewed to assess compliance with Criterion 51 of the General Design Criteria (GDC-51),
" Fracture Prevention of Containment Pressure Boundary." The V. C. Summer containment is a load-bearing reinforced concrete structure with - thin steel liner on the inside surface which is designed to serve as a membrane providing leak tightness. Tha fracture toughness requirements of GDC-51 apply to those ferritic stcel parts of the containment pressure boundary which are not supported by concrete and are thus load-bearing. These materials are typically applied in containment penetrations such as the the equipment hatch, personnel hatch, and pipe system penetrations.
The applicant has stated in the FSAR that the ASME Code Section III was applied in the fabr.ication of the hatches penetrations.
Compliance with the requirements of the ASME Code for the ferritic steel parts of the containment pressure boundary satisfies the requirements of GDC-51.
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