ML16341F095
| ML16341F095 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/23/1989 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341F094 | List: |
| References | |
| 50-275-89-05, 50-275-89-5, 50-323-89-05, 50-323-89-5, NUDOCS 8904170084 | |
| Download: ML16341F095 (4) | |
Text
APPENDIX A NOTICE OF VIOLATION Pacific Gas and Electric Company
.Diablo Canyon Nuclear Power Plant Docket Nos.
50-275 and 50-323 License Nos.
DPR-80 and DPR-82 During an NRC inspection conducted on January 23 through March 4, 1989, a
violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10.
CFR Part 2, Appendix C
( 1988), the violation listed below:
10 CFR 50 Appendix B Criterion III reads, in part, "Design changes including field changes shall be subject to design control measures commensurate with those applied to the original design...."
10 CFR 50 Appendix B Criterion V r'eads, in part, "Activities affectinq quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstance and shall be accomplished in accordance with these instructions, procedures, or dlawings.
The Diablo Canyon Nuclear Power Generation Department Procedure NPAP C-2/NPG-4P and NPAP C-40 establishes and defines detailed steps to be
.taken by responsible individuals at the Diablo Canyon Nuclear Power Plant to identify and process design changes to ensure compliance with the above 10 CFR 50, Appendix B requirements.
These procedures define a
design change as "any modification to plant structures, systems or components as described on approved specifications, drawings or supplier documents."
Contrary to the above requirements on February 13,
- 1989, a split washer, part number 34 on Schuttle 8 Koerting Company draiving 60-XE 143 (No revision) for the Unit 2 auxiliarv feedwater pump overspeed stop valve FCV 152, was modified by craft personnel to increase its inner diameter from 7/8 inch to 15/16 inch.
The change was verbally authorized by a maintenance engineer.
This change had not been processed as a design change in accordance w'ith licensee requirements.
This is a Severity Level IV Violation (Supplement
- 1) applicable to Unit 2.
Pursuant to the provisions of 10 CFR 2.202, Pacific Gas and Electric Company is hereby required to submit a written statement of explanation to the U.S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Senior Resident Inspector, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearlv marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason 8904170084 890323 PDR ADOCK 05000275 8
PNU
1 for the violation if admitted, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further violations,.and (4) the date'when full compliance will be achieved.
If an adequate reply is not ~eceived within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
Consideration may be given to extending the response time for good
" cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION Dated at Walnut Creek, California this, ) 3 day of y,f'y~c+
1989 R.
- immerman, ie Reactor Projects Branch