ML20107L150
| ML20107L150 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/02/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100J378 | List: |
| References | |
| NUDOCS 8411130432 | |
| Download: ML20107L150 (2) | |
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Safety Evaluation Related to Issuance of
- Facility Operating-License DPR-80 Diablo Canyon Nuclear Power Plant, Unit l' Docket No. 50-275
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Introduction This safety evaluation pertains to the issuance of Facility Operating License
'DPR-80'for Unit 1 of the Diablo. Canyon Nuclear Power Plant authorizing facility operation'at 100 percent of rated power.. On_ September 22,:1981 the NRC issued
' Facility Operating License DPR-76 authorizing facility operation not in excess
. of 5 percent of rated power.
Changes were made to the Technical Specificatichs
.and-further' license conditions were added to DPR-7,6 in Amendments.1 through 9 and in an Order to modify the License.
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- The-staff has reviewed all provisions of; license DPR-76, including those conditions previously proposed to be added to the license by an amendment Lauthorizing full. power operation, with respect _to their applicability to the full power licenseLDPR-80.
A number of license conditions previously included in DPR-76 ~nde.r'-Section 2.C have been satisfied and need not be' reinstated or n.
u L%M have been revised because the required-action has been partially lor totally
' completed, or a-regulation'has since'been issued which encompasses the-
!j-(requirements of the license condition.
The inclusion of new license condi.tions p E g and issuance'of. full power Technical Specifications was previously addressed eS ma.1 by the staff in Supplement 27 to the Safety Evaluation Report (SSER-27) dated-Edo JulyL1984.-
-Presented below'islthe staff evaluation for a revision to-a previously proposed a
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i 111 cense condition regarding masonry walls (SSER-27,Section II.4 and IV.4) and g
L the deletion of certain exemptions regarding fracture toughness, previously 1
included in Section 2.0 of DPR-76.'
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. Masonry walls-lIa.a.
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- In SSER-27,-Sections-II.4 and IV.4, the staff indicated that there continued to
,X-be a need for a license condition regarding certain additienal information l
comparing theDlicensee's criteria with staff criteria for evaluation of-P
- masonry walls.: Since that time, the staff has conducted a site visit which included a. number of discussions with the licensee, and review of additional documentation including test results.
This has permitted a more detailed understanding of the. licensee's criteria. As a result, the staff. concludes that there is reasonable assurance that these. walls will r.emain' functional in
- the event of-a _desien earth @uake and that_ agelicable re@ulations are met.
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However, it is still necessary for the licensee.to document'its' analysis of the
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- differences in margins when comparing its criteria to staff criteria even though it isinot likely that structural' change will result from this evaluation.
..The proposed license condition as discussed in SSER-27 has therefore been
. revised accordingly and is included under Section 2.C(10).-
3.-
~ Compliance with Appendices G and H tc 10 CFR Part 50 (Fractur'e Toughness)
-In-Section 2.D~of the low power license DPR-76 exemptions were granted from
.certain' requirements, among others, of Appendices G and H as related to fracture
- toughness.' These' exemptions have been deleted from the full power license DPR-80 as discussed below.
- In previous safety evaluations (Supplement Nos. 9 and 13) the staff determined
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- that exemptic6 to Sections III.C.2 and.IV.A.4 of Appendix G' to 10 CFR 50 and o
-Section II.B of Appendix H to,10 CFR E0 would ha required and were justified.
/Since those evaluatis were published, Appu dices G and H have been revised.
The revised Appendices G and H were published in the Federal Register on May 27, 1983 and became effective on July 26, 1983.- The exemptions to Appendices-
.G and H, which were discussed in our previous safety evaluations, are no longer required, because the Diablo Canyon, Unit 1 materials and surveillance program-complies with the revised Appendices G and H requirements.
A discussion of these requirements follows.
y Section:III.C.2'and IV.A.4 in previou~s versions of Appendix G had specific crequirements for preparation.of reactor.' vessel beltli.ne weld metal test
- specimens and minimum fracture' toughness reouirements-for reactor coolant-pressure boundary ferritic bolting, respectively. -In lieu _of these-specific
- . requirements, the. current provisions of. Appendix G require that' reactor
-vesselybeltline weld metal test. specimens'and reactor coolant pressure boundary ferritic bolting comply with the requirements in ASME Code edition and. addenda 7
, permitted by section 50.55a of-10 CFR 50.-_ In a previous safety evaluation we-e
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determined that the reactor vessel for Diablo Canyon, Unit:1 was fabricated to -
L JASHE Code edition.and' addenda as provided by the requirements of section
.50.55a.
Hence,-the Diablo Canyon,- Unit 1 materials comply with the revised Appendix G requirements and exemptions to Appendix G are no longer required.
i Section II.B in previous versions of Appendix ~H required that the surveillance' L2
= program conducted' prior.to the first capsule withdrawal comply with the 1973 L
(edition'of' ASTM E-185.
The ~ current provision cf Appendix H requires that 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 L~
issue date of'the ASME Code to which the reactor vessel was purchased.
The
.Diablo Canyon, Unit 1 surveillance program complies with these requirements.
Hence,_the Diablo Canyon, Unit 1 surveillance program complies with the L
- revised Appendix H requirements'and an exemption to Appendix H is no longer i
- required.
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