ML20137Q546
| ML20137Q546 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/17/1986 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20137Q550 | List: |
| References | |
| NUDOCS 8602060300 | |
| Download: ML20137Q546 (4) | |
See also: IR 05000344/1985033
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N 1 Y 1995
Docket No. 50-344
Portland General Electric Company
121 S. W. Salmon Street
Portland, Oregon 97204
Attention:
Mr. Bart D. Withers
Vice President, Nuclear
Gentlemen:
Subject: NRC Inspection of the Trojan Nuclear Plant
This refers to the special team inspection conducted by Mr. W. Albert and
other members of our staff on December 2-13, 1985, of activities authorized by
NRC License No. NPF-1, and to the discussion of our findings held by
Mr. Albert with you and other members of your staff at the conclusion of 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
personnel, and observations by the inspectors.
This inspection focused its effort upon your programs and controls associated
with the Auxiliary Feedwater System, the emergency Diesel Generators, and the
125 VDC Power System and the implementation and adherence of those programs
and controls in the following areas: Operator Recovery Actions; Motor-operated
Valve Programs; Technical Specification Surveillance Program; Maintenance
Programs; Plant Modifications; Offsite Safety Committee Activities; and Health
Physics Programs.
Overall Conclusions
In general, the team concluded that serious attention must be devoted to those
management systems which ensure reliable performance of installed
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safety-related equipment. This need is demonstrated by the findings of the
team with~ regard to quality control inspections of maintenance activities and
the control of temporary modifications. We are particularly concerned with
the findings in the quality control area, as these findings again reflect a
historical lack and appreciation by the management of the utility for a strong
quality control program in support of nuclear plant operations. We are
similarly concerned that quality control presence may be missing in other
areas and in need of management attention.
Please advise us of your plans to
assess this question and your anticipated corrective actions.
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Areas Inspected and Results
A.
Operator Recovery Actions
The area of Operator Recovery Actions was examined and it was determined
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that the level of operator knowledge and understanding of the emergency
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procedures associated with operator recovery actions for the ' Loss of
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Secondary Coolant' and ' Loss of All AC Power' procedures was extensive.
However, three items of concern were identified in the procedures which
addressed recovery actions.
B.
Motor Operated Valves
The scope of this inspection included the components that make up the
interface between the Auxiliary Feedwater System (AFS) and the Service
Water System (SWS) with emphasis on the motor-operated valves between
these systems. Maintenance and testing of motor-operated valves in
general was also reviewed. No problems or concerns were identified.
C.
Surveillance Program
The surveillance program for implementing technical specification
requirements which apply to the Auxiliary Feedwater System, Station IE
125-volt Batteries and Emergency Diesel Generators was examined and found
to be adequate. The results of the examination revealed that there were
minor weaknesses in the station battery and the auxiliary feedwater
system diesel's starting battery surveillance procedures. The licensee's
station management connitted to revise these procedures.
An examination of approximately 500 surveillance records for the three
systems examined found that quality control inspection was not being
performed during the performance of the surveillances. This lack of a
quality control function was evident from the lack of quality control
hold points or inspection points in any of the procedures examined. The
absence of the quality control function in the technical specification
surveillance program, which also implements a major portion of the
preventive maintenance program for the plant's safety-related equipment,
is perceived as a major weakness in the licensee's overall quality
assurance program and is discussed under " Maintenance" below.
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D.
Maintenance
The maintenance program was examined for conformance with regulatory
requirements, Technical Specifications, and licensee commitments. The
inspectors interviewed approximately 30 PGE staff members, reviewed 35
PGE procedures and examined approximately 500 Maintenance Requests and
Procedural Test Data sheets. Three areas of concern were identified in
the Preventive and Corrective maintenance program as follows:
1) failure
to systematically analyze performance data, 2) use of post-maintenance
testing and 3) methods by which maintenance requests are classified as
safety or non-safety related. None of these items were severe enough to
warrant a violation or deviation. However, it was found that there was a
definite lack of independent quality control verification in maintenance
work. This matter is considered to be a violation of NRC requirements.
E.
Procedural Control
Procedural controls were examined to determine whether ar not procedures
were being revised to reflect plant modifications. Auditionally, the
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temporary modification program was examined to assess the adequacy of the
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licensee's program for controlling lif ted electrical leads and jumpers.
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It was concluded, except for minor deficiencies, the program was meeting
NRC requirements.
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Modifications
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The plant modification program was inspected to determine whether
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controls and procedures were established and implemented for changes to
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plant design. The inspectors concluded that overall the program was
functioning according to requirements, however, the deficiencies found in
the installation of one of the changes appear to constitute a violation
of requirements.
G.
Offsite Review Committee
Although team effort in this area was limited, the procedures governing
the Trojan Nuclear Operations Board (TNOB), (the offsite safety review
committee), were reviewed and the quarterly meeting held on December 10,
1985 was attended.
It was concluded that the TNOB was meeting the
requirements of the Technical Specifications and the commitments in the
FSAR.
H.
Radiation Protection, Plant Chemistry and Radwaste
The inspection in this area included radiation protection and the
chemistry organization and management, training and qualification and
liquid and gaseous waste disposal, information notices and the licensee's
response to a Generic Letter. No violations of NRC requirements were
identified in this area.
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In accordance with 10 CFR'2.790(a), a copy of this letter and the enclo.sure
will.be placed in the NRC Public Document Room.
Should;you have-any questions concerning this inspection, we will be glad to
discuss them with you~.
Enforcement action by the NRC relating to this inspection will be the subject
of separate correspondence.
R Pote
For - D. F. Kirsch, -Deputy Director
Division of Reactor Safety and Projects
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. Enclosure:
Inspection Report
No. 50-344/85-33
cc:
W. S. Orser, PGE
J.~ W. Durham, Esq
W. Dixon, DOE
J. Partlow, IE
W. Russell, NRR/AD/DHFS.
bec:
RSB/ Document. Control Desk (RIDS)
Mr. J. Martin
Mr. B. Faulkenberry
.G. Cook
Resident Inspector
Project Inspector
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