ML20248B232
| ML20248B232 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/24/1989 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20248B238 | List: |
| References | |
| NUDOCS 8906080295 | |
| Download: ML20248B232 (2) | |
See also: IR 05000344/1989013
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Docket Nob 50-344
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Portland General Elu.tric Company
121 S.W. Salmon Street, TB-17
. Portland,~ Oregon 97204
. Attention: Mr. David W. Cockfield
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~Vice President, Nuclear
Gentlemen:
Subject: NRC Inspection of the Trojan Nuclear Plant
This refers'to the special inspection of the. Residual Heat Removal. System
(RHRS) suction isolation valve failure to operate per design conducted by Mr.
R. C. Barr and Mr. G. Y. Suh of this office from April 9,71989 through April
29, 1989. . The inspection was related to activities authorized by NRC License
No. NPF-1, and concluded with discussion of our findings with members of your
staff on April 28, 1989.
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- Areas examined during this inspection are described in.the enclosed inspection
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report. Within-these areas, the inspection consisted of selective
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. examinations of procedures and representative records, interviews with
personnel and observations by the inspectors.
Based on.the results of this inspection, it appears that one of your
activities was not c'onducted in full compliance with NRC requirements, as set.
forth in the Notice of Violation, enclosed herewith as Appendix A.
Your response
.. , : r
.to this Noticetis' to- be submitted in accordance with the provisions of 10 CFR 2.201.
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as stated in Appendix A, Notice of Violation.
In accordance with 10 CFR-2.790(a),
a copy of this lette.r and the enclosure will be placed in the NRC Public
Document Room.
-The inspection determined inadequate post modification testing during the-1988
Refueling Outage resulted in the failure to identify a wiring error that
rendered inoperable the' interlock and permissive features of Residual Heat
Removal System suction isolation valve, M0-8702.
Furthermore, the technical
review'and oversight of the post modification testing by your Engineering,
Quality Assurance and Plant Review Board organizations, was not of sufficient
depth to detect ~these. testing deficiencies.
The response directed by this letter and the attached Notice is not subject
- to the clearance procedures of the Office of Management and Budget as required
by:the Paperwork Reduction Act of 1980, PL.96-511.-
In accordance.with 10 CFR 2.790(a),'a copy of this letter and the enclosure
will,be placed in the NRC Public Document Room.
I
8906000295 890524
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Should you have any questions concerning this inspection, we will be glad to
discuss them with you.
Sincerely,
,
[
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R. P. Zi.
rman, Acting Director
Division of Reactor Safety and
Projects
' Enclosure:
Inspection Report No. 50-344/89-13
cc w/ enclosure:
- T.. D. Walt, General Manager, Technical Functions
C. P. Yundt, General Manager:
- L.. A. Girard, Vice President and General Counsel
W. Dixon, ODOE
bec w/ copy of enclosure:
Docket File
Project Inspector
Resident Inspector
G. Cook
B. Faulkenberry
J. Martin
R. Nease, NRR
State of Oregon
bec w/o enclosure: g
M. Smith
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