ML20132D448
| 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: |
| References | |
| 50-344-85-17, NUDOCS 8508010028 | |
| Download: ML20132D448 (5) | |
See also: IR 05000344/1985017
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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
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License No. NPF-1
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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
Inspector:
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H. L. Pidovan, Regi6hal Inspector
Date Signed
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R. T. Dodds, Chief, Reactor Projects Section 1
Ddte 7igned
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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
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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
1.
Persons Contacted
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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
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and the remainder of the reactor vessel
closure head segment welds
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Iower head segment welds
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inlet nozzle (including safe-end) welds
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outlet nozzle (including safe-end) welds
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closure head studs and nuts
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vessel flange ligaments
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closure head cladding
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control rod drive housings
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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
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frequency, size, and identification of transducers
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linearity (screen height and amplitude control)
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signal attenuation accuracy
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beam angles, scanning surface, scanning rate and. direction
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calibration requirements (including calibration block geometry
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and material, and location and size of calibration reflectors)
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verification of penetration
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transducer mount angles
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scanning sensitivity level
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electronic distance - amplitude correction (DAC) provisions
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defined reference level for monitoring discontinuities
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specified levels for evaluation and recording of indications
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method of recording valid indications
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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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were established, and licensee commitments described in the Trojan
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Technical Specifications and Updated Final Safety Analysis Report
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were found to be properly reflected in the ISI procedures.
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c.
Preliminary Data Review
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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
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calibration records
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' dentification, location and extent of areas examined
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record of all indications recorded
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record of all evaluations of indications
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personnel certifications
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dates and times of examinations
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basic calibration block identification
couplant
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surface condition and surfaces from which examinations were
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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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