ML16342B262
| ML16342B262 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/12/1987 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8701210482 | |
| Download: ML16342B262 (4) | |
Text
JP,N 12 P.S7 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 941b6 Attention:
Mr. James D. Shiffer, Vice President Nuclear Power Generation
SUBJECT:
EQUALITY ASSURANCE PROGRAM DESCRIPTION FOR DIABLO CANYON On November 26, 1986, you submitted proposed changes to Chapter 17 of the Diablo Canyon Power Plant FSAR for our review and approval.
As a result of our review, we are providing you with the following coltments addressing each of the proposed changes submitted:
a ~
Use of ASME Code Case N-356 Code Case N-356 is not currently listed in any of the applicable Regulatory Guides as suitable for use by the Commission staff.
Therefore, your request to make use of this code case cannot be approved by Region V.
- However, use of this code case has been approved on a case-by-case basis as in the authorization for use at the Clinton Power Station Unit 1.
Your request for approval to use Code Case N-356 should be made to the Licensing Branch of NRR in accordance with 10 CFR 50.55a, footnote 6.
b.
Use of SNT-TC-1A 1980 C ~
Your proposed request to use the 1980 Edition of SNT-TC-1A is authorized provided you make the requirements of this document mandatory rather than guidance.
This would make your ISI program in compliance with the intent of ASME Section XI that "shall" is to be inserted in place of "should" in SNT-TC-1A 1980.
Use of NCIG-01 and NCIG-03 The NCIG-01 document for reinspection of structural welds was developed under two important premises.
First, that it doesn' apply to fatigue loaded structures, and second, that the assumed design margins in fact are available at the adopting site.
- Also, NCIG-Ol is not applicable to ASME structures or any work performed to your ASME Section XI Inservice Inspection Program.
Therefore, we are requesting you provide us with additional information on your intended use of these NCIG documents; and what measures will be initiated (implementing instructions) to ensure that the NCIG documents are not misapplied to areas with fatigue loading considerations or areas with insufficient design margins.
8701210482 870112 PDR ADOCK 05000275 P
f
O V
James D. Shiffer JAN >P. ~-B>
Please reply by March 1, 1987 as to what positions you plan on taking in regards to the above comments.
If you have any questions regarding this
- matter, please contact W. J.
Wagner of my staff at (415) 943-3731.
CC:
H. E. Schierling, NRR W. L. Belke, QAB P.
P. Narbut, RY Section Chiefs Branch Chief Document Control Desk 1st Dennis F. Kirsch, Director Division of Reactor Safety and Projects RV/jk USE TO PDR ]
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