ML20209D045
| ML20209D045 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 11/01/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML082410749 | List:
|
| References | |
| FOIA-86-197 NUDOCS 8704290161 | |
| Download: ML20209D045 (2) | |
Text
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4 ATTACHMENT PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-275/323 MATERIALS APPLICATION SECTION MATERIALS ENGINEERING BRANCH 5.2.4 Fracture Toughness 1.
Compliance with Appendices G and H, 10 CFR 50 In previous safety evaluations (Supplement Nos. 9 and 13) the staff determined that exemptions to Sections III.C.2 and IV.A.4 of Appendix G, 10 CFR 50 and Sections II.B and II.C.2 of Appendix H, 10 CFR 50 would l-j be required and were justified.
Since those evaluations were published, Appendices G and H have been revised. The revised Appendices G and H were published in the Federal Register on May 27, 1983 and became l
effective on July 26, 1983.
The exemptions to Appendices G and H, t
i which were discussed in our previous safety evaluations, are no longer 1
l required, because the Diablo Canyon materials and surveillance program
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complies with the revised Appendices G and H requirements. A discussion
'l of these requirements follows.
1:
Section III.C.2 and IV.A.4 in previous revisions of Appendix G had y
specific requirements for preparation of reactor vessel beltline weld i
l metal test specimens and minimum fracture toughness requirements for reactor coolant pressure boundary ferritic bolting, respectively.
In i
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lieu of these specific requirements, the revised Appendix G requires that reactor vessel beltline weld metals test specimens and reactor 8704290161 870417
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l' coolant pressure boundary ferritic bolting comply with the requirements k
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in ASME Code edition and addenda that was permitted by paragraph 50.55a, 10 CFR 50.
In a previous safety evaluation, we determined that the reactor vessels for Diablo Canyon were fabricated to ASME Code edition and addenda, which comply with the requirements of ~ paragraph 50.55a.
Hence, Diablo Canyon's materials comply with the revised Appendix G requirements and exemptions to Appendix G are no longer required.
j j Sections II.B and II.C.2 in previous revisions of-Appendix H required that the surveillance program conducted prior.to the first capsule-withdrawal comply with the 1973 edition of ASTM E 185 and the lead 4
{1 factor (ratio of neutron fluence received by the capsule to that l3 received by the vessel inner surface) for the surveillance. capsules
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not exceed three, respectively. The revised Appendix H, requires that i
the surveillance program conducted prior to the first capsule withdrawal comply with the requirements of the edition of ASTM E 185 that is current on the issue date of the ASME Code to which the' reactor vessel was pur-chased. The Diablo Canyon surveillance program complies with these
-I requirements. The revised Appendix H does not have a specific require-ment that lead factor for the surveillance capsules not exceed three.
1 Hence, Diablo Canyon's surveillance program complies with the revised f
l Appendix H requirements and exemptions to Appendix H are no. longer
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required.
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