ML20024H110
| ML20024H110 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/29/1991 |
| From: | Richards S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Cross J PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20024H111 | List: |
| References | |
| NUDOCS 9105210443 | |
| Download: ML20024H110 (3) | |
See also: IR 05000344/1991007
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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14fi0 MARIA L ANE,SulTE 210
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WALNUT CRE E K, C AllFORNIA 94t,96
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APR
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Docket No. 50-344
Portland General Electric Company
121 S.W.-Salmon Street, TB-17
-Portland, Oregon 97204
Attention:
Mr. J. E. Cross
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Vice President, Nuclear
Gentlemen:
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Subject:- NRC Inspection of the Trojan Nuclear Plant
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This refers to the inspection conducted by Mr. R. C. Barr and Mr. J. F. Melfi
of this office on February 10 through March 31, 1991 of activities authorized
by NRC License No. NPF-1, and to the discussion of our findings held by Mr.
Barr and Mr. Melfi with Mr. Robinson and other members of your staff
periodically during the inspection.
Areas examined during this inspection are described in the enclosed inspection
report.
Within these areas, the inspection consisted of selective
examinations of procedures and representative records, interviews with
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personnel and observations by the inspectors,
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This inspection identified multiple examples where management awareness of and
participation in facility activities appeared weak, particularly in the areas
of forced outage and refueling outage planning.
For example, at the start of
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the 1991 refueling outage only 63% of the scheduled maintenance request
packages and.20% of the maintenance packages associated with design changes
were prepared and ready for work, although your program intends the packages
to all be available at the start of the outage. -Similarly, plant events such
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-as the reactor trip of February 12,1991, and the pressurizer over-cooling of
March 25, 1991, may have been avoided had Operations-and Maintenance
management independently assessed the potential for problems with regard to
the-activities which led to the events.
Your attention is also' drawn to paragraph 4, which describes maintenance-
activities associated with an auxiliary feedwater valve.
During this
activity, our inspector questioned the craftsman regarding the torque to be
applied to valve components and in so doing, prevented the craftsman from
violating the work instructions.
This occurred-even though maintenance-
supervision was present at the job site.
Based on the results of this inspection, it appears that certain of your
activities were not conducted in full compliance with NRC regulations, as set
forth in the Notice of Violation, enclosed as Appendix A to this letter.
Pursuant to the provisions of 10 CFR 2.201,_you are required to respond as
indicated in the enclosed Notice of Violation.
In accordance with 10 CFR
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2.790 (a), a copy of this letter and the enclosures will be placed in the NRC
Public Document Room.
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9105210443 910429
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ATR 2 91921
The response directed by this letter 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.
Should you have any questions concerning this inspection, we will be glad to
discuss them with you.
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Sincerely,
bY AY
S. A. Richards, Chief
Reactor Projects Branch
Enclosures:
1.
2.
Inspection Report No. 50-344/91-07
cc w/ enclosure:
W. R. Robinson, Plant General Manager
L. A. Girard, Vice President and General Counsel
D. Stewart-Smith, Administrator, Nuclear Safety & Energy facilities
Division, 000E
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Docket File
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B. Faulkenberry
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bec w/o copy of enclosure:
J. Zollicoffer
M. Smith
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