ML20137Q546

Forwards Insp Rept 50-344/85-33 on 851202-13.Attention Must Be Devoted to Mgt Sys Which Ensures Reliable Performance of Installed safety-related Equipment.Areas Inspected & Results Listed

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: IR 05000344/1985033 ML20137Q546
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 ~

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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Portland General Electric Company -2- USN 1 7 1933

Areas Inspected and Results

A. Operator Recovery Actions

The area of Operator Recovery Actions was examined and it was determined j

that the level of operator knowledge and understanding of the emergency i

procedures associated with operator recovery actions for the ' Loss of l

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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Portland General Electric Company -3- JAN 17 ggg

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 {

temporary modification program was examined to assess the adequacy of the l

licensee's program for controlling lif ted electrical leads and jumpers. l

It was concluded, except for minor deficiencies, the program was meeting

NRC requirements.

F. Modifications i

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The plant modification program was inspected to determine whether j

controls and procedures were established and implemented for changes to '

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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Portland General Electric Company -4- 1I I33$

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 t

. 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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