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Insp Rept 50-344/85-17 on 850603-07.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp of Reactor Pressure Vessel
	ML20132D448
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/25/1985
From:	Dodds R, Padovan M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	;
Shared Package
ML20132D445	List: ML20132D443; ML20132D448;
References
	50-344-85-17, NUDOCS 8508010028
	Download: ML20132D448 (5)
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U. S. NUCLEAR REGULATORY COMMISSION

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REGION V

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Report No: 50-344/85-17

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. Docket No: 50-344

i License No. NPF-1

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i Licensee: Portland General Electric Company

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121 S. W. Salmon Street

Portland, Oregon 97204

Facility.Name: Trojan

Inspection at: Rainier, Oregon

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!- -Inspection conducted: June 3 - 7, 1985

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Inspector: [

H. L. Pidovan, Regi6hal Inspector

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Date Signed

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R. T. Dodds, Chief, Reactor Projects Section 1

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! Summary:

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Inspection from June 3 - 7, 1985 (Report 50-344/85-17)

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Areas Inspected: Routine. inspection of Inservice. Inspection (ultrasonic

j examination) of the reactor pressure-vessel. .The inspection involved 58

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inspector-hours by-the NRC Regional Inspector.

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Results: - No' violations or deviations were identified.

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DETAILS

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1. Persons Contacted

A.-Wogen, NPE/ISI Engineer

S. Bauer, Licensing

R. Schmitt, Manager,,0perations and Maintenance

A. Cohlmeyer, Engineering Supervisor

M. Snook, Acting QA Supervisor

G. Kent, Plant. Engineer

S. Richards, NRC Senior Resident Inspector

Denotes those attending the exit. interview.

2. Reactor Vessel Inservice-Inspection (ISI)

a. -General-

10 CFR 50.55 a (g) " Inservice Inspection Requirements" specifies

that ISI be performed on the American Society of Mechanical

Engineers (ASME)- Code Class l' reactor pressure vessel in accordance

with Section XI of the ASME Boiler and Pressure Vessel Code, and

applicable addenda, as practical. For the Trojan facility, ISI of

the reactor vessel was to be conducted in accordance with the Summer

1975 addenda to Section XI of the Code. ISI of the reactor vessel

was based upon Portland General Electric (PGE) Topical Report

PGE-1032 " Trojan Nuclear Plant Inservice Inspection Program for the

First 10-Year-Interval" (hereafter referred to as the ISI Program).

Relief from certain ASME Code requirements, granted by the Nuclear

Regulatory Commission (NRC), were described in Section 3.3 of this

document.-

Commencement of the Trojan ISI Program began on the date of

commercial operation, May 20, 1976. The 10-year interval is divided

into.three periods of forty months each, Required reactor vessel

examinations for each forty month interval are specified in the ISI

Program. Examinations which were performed on the reactor vessel

were for the third forty month period ("end of 10 vears" interval),

and included the following:

. longitudinal and circumferential welds in both the core region

and the remainder of the reactor vessel

. closure head segment welds

. Iower head segment welds

, closure head to flange weld

. vessel to flange weld

. inlet nozzle (including safe-end) welds

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. outlet nozzle (including safe-end) welds

. closure head studs and nuts

. vessel flange ligaments

. closure head cladding

. control rod drive housings

The reactor vessel ultrasonic examination was performed by

Westinghouse (H) personnel in accordance with E examination

procedure ISI-154 POR " Inservice Inspection of Reactor Vessels,"

Revision 0, dated April 1, 1985. This document described the

equipment, calibration sequence, examination techniques, and

recording requirements for'ISI of the reactor vessel with a remotely

computer operated inspection tool. Specific calibration and

examination requirements (such.as areas selected for examination,

extent of examination, search unit sizes, search unit angles,

calibration standards,- and water path distances) were defined in'the

" Trojan Reactor Vessel Examination Program Plan, Revision 0, dated

April 1, 1985 (hereafter referred to as the " Program Plan"). The

examinations were performed using pulse-echo and occasional,

supplementary transmit-receive-(pitch and catch) ultrasonic

techniques with immersion water path coupling.

The NRC Inspector's evaluation of the licensee's third forty month

ISI consisted of 1) a rsview of the previously mentioned ISI

programs and procedures, and 2) a partial review of examination data

and records,

b. Inservice Inspection Procedure Review

ISI-154 POR and the Program Plan were reviewed by a certified ASME

Level III nondestructive examination examiner, the Trojan Plant

~ Review Board, and were approved for use by PGE's General Manager.

The personnel requirement section of ISI-154 POR stipulated that

ultrasonic test operators were to be certified ASME Level II or

Level III examiners, in accordance with American Society for

Nondestructive Testing SNT-TC-1A-1968. Consistant with ASME Section

XI Subarticle IWB-2500, the ISI Program specified examination

categories, examination methods for each specified component weld,

and the extent of examination for each subject weld. The inspector

verified that- ISI-154 POR and the Program Plan contained the

following requirements:

. type of apparatus used

. frequency, size, and identification of transducers

. linearity (screen height and amplitude control)

. signal attenuation accuracy

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. beam angles, scanning surface, scanning rate and. direction

. calibration requirements (including calibration block geometry

and material, and location and size of calibration reflectors)

l . verification of penetration ,

l . transducer mount angles

. scanning sensitivity level

l . electronic distance - amplitude correction (DAC) provisions

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. defined reference level for monitoring discontinuities

. specified levels for evaluation and recording of indications

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! . method of recording valid indications

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l . reporting requirements

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The requirements specified in ISI-154 POR and the Program Plan were

determined to be in accordance with Appendix I " Ultrasonic

Examination" of ASME Section XI. Additionally, the inspector

verified that adequate procedural requirements for recordkeeping

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l Technical Specifications and Updated Final Safety Analysis Report

l were found to be properly reflected in the ISI procedures.

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l c. Preliminary Data Review

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l 1he licensee's 'ISI Program specifies that a summary ISI report will

be filed with the NRC 90 days after completion of ISI (final system

pressure tests). Since final system pressure testing was scheduled

to be completed by about June 19, 1985, the report is due to be

submitted by the end of September 1985. This report will contain

the following information:

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. test procedure

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. description of the test systam

. calibration records

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! . ' identification, location and extent of areas examined

. record of all indications recorded

. record of all evaluations of indications

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! . personnel certifications

. dates and times of examinations

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basic calibration block identification

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. surface condition and surfaces from which examinations were

performed

Examination data provided in the summary ISI report will be reviewed

by the inspector, and documented in a routine Trojan NRC Inspection

Report. The licensee has informed the inspector that no valid

indications are present in the reactor vessel at this time (previous

forty month interval ISIS also did not identify any valid

indications). Any indications found which were 20% of DAC or

greater were evaluated by the licensee to determine if the

indication was valid. Indications of 50% of DAC or greater were

required-to be recorded. As no indications of 50% of DAC or greater

were encountered during the ISI, no recordings are available for

review by the NRC. Indications falling between the 20% and 50% DAC

values were dispositioned by the licensee to be invalid indications

(such as scanning noise and spurious noise from electrical sources).

No deviations from program or procedural documents were recorded by

the licensee. The licensee was not able to provide documentation on

reactor coolant system water temperature. Section 7.1.6 of ISI-154

POR specifies that refueling water-temperature be recorded every

two days, to assure that the water temperature is within plus or.

minus 25 degrees F of that used during calibration. However, the

licensee believes that this information was recorded in the ISI

equipment operator's log book, and will be included in the summary

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ISI report. The inspector will review the summary report, once

issued, for inclusion of this information. ~This is an unresolved

item (85-17-01).

No violations or deviations were identified.

3. Unresolved Items

An unresolved item is a matter about which more information is required

in order to ascertain whether it is an acceptable item, an open item, a

deviation, or a violation.

4. Exit

On June 7,1985, an exit meeting was conducted with the licensee's

representatives identified in paragraph 1. The inspector summarized the

scope and findings of the inspection as described in this report.

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ML20132D448

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