ML20209G470
| ML20209G470 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 03/06/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML082410749 | List:
|
| References | |
| FOIA-86-197 NUDOCS 8704300550 | |
| Download: ML20209G470 (3) | |
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON SITE, UNIT NOS. 1 AND 2 (OL)
DOCKET NUMBERS 50-275/323 SAFETY EVALUATION REPORT SUPPLEMENT J
MATERIALS ENGINEERING BRANCH MATERIALS APPLICATION SECTION Inservice Inspection and Testing Requirements
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i In letter to the Commission dated December 23, 1980, the Pacific Gas and Electric
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Company determined that conformance with certain Edition and Addenda of the ASME Boiler and Pressure Vessel Code was impractical for the Diablo Canyon Site.
Unit Nos.1 and 2, and requested reli&f from the requirement of paragraph 50.55a(g)(4)(i) of 10 CFR Part 50. This paragraph states that the Edition and Addenda of Section XI of the Code in effect for the Inservice Inspection and Testing Program for the initial inspection' interval is the latest Edition and Addenda in effect 12 months prior to the date of issuance of the operating license, subject to certain regulatory limitations.
Pacific Gas and Electric Company submitted the following information in support l
of their determination:
1.) Delay in obtaining an operating license coupled with change in the regulations has resulted in a continual update and revision of the Preservice and Inservice Inspection and Testing Programs, starting in 1975 for Unit No.1 and 1976 for Unit No. 2.
The last revision was on November 1,1979.
2.) The projected schedule for commercial operation is Summer,1981, for Unit No.1 and Spring,1982, for Unit. No. 2.
Since the units will be licensed on different dates, the requirement for the Inservice Inspection and Testing Programs will differ for each unit.
Instead of the requirement of paragraph 50.55a(g)(4)(i) of 10 CFR Part 50, the Pacific Gas and Electric Company proposed that Section XI of the ASME Boiler and Pressure Vessel Code,1977 Edition, including Summer 1978 Addenda, be the applicable 8704300550 870417 EME 197 PDR
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I Code for the initial inspection interval for Unit Nos.1 and 2 at the Diablo Canyon Site. This Edition and Addenda of the Code was in effect on November i
1, 1980. The initial inspection interval will be scheduled to begin when that unit is placed in commercial operation.
1 We have evaluated the request for relief from the requirement of paragraph 50.55a (g)(4)(i) of 10 CFR Part 50, and conclude that the requirement is impractical for Unit Nos.1 and 2 at the Diablo Canyon Site. We conclude that different Inservice Inspection and Testing Programs for the two units and a' continuous updating of the Preservice Program prior to commercial operation imposes a burden upon the Pacific Gas and Electric Company without an increase in plant reliability and safety. We concur with.the licensee in specif91ng Section XI of the ASME Boiler and Pressure Vessel Code,1977 Edition, including Summer 1978 Addenda, as the applicable code for the initial inspection interval for Unit Nos.1 and 2 at the Diablo Canyon Site.
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.a-ATTACHMENT 2
~ PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323
- INSERVICE INSPECTION SECTION,
MATERIALS ENGINEERING BRANCH 5.2 Integrity of the Reactor Pressure Boundary Inservice Inspection Program This evaluation supplements conclusicns in this section of NUREG-0675.
In a letter dated February 22, 1985, the Pacific Gas and Electric Company (PG&E) submitted the Inservice Inspection (ISI) Program Plan for the first ten year inspection interval for Diablo Canyon Unit 2.
This document describes the inservice inspections for the pressure retaining components (including supports) which are classified as ASME Code Class 1, 2, and 3.
The ISI Program also identifies ASME Code requirements that PG&E has determined to be impractical to perform.
The staff is currently reviewing the ISI Program for Unit 2.
Inservice inspections are hot normally conducted until the first refueling outage.
Therefore, the staff has previously determined on other dockets that 1
completion of the review of the ISI Program was not required before full power operation.
The staff will complete the review of the Inservice Inspection Program before the first refueling outage and report the conclusions in a supplement to this SER.
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