IR 05000344/1982016
| ML20054G818 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/01/1982 |
| From: | Eckhardt J, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20054G811 | List: |
| References | |
| 50-344-82-16, NUDOCS 8206220326 | |
| Download: ML20054G818 (5) | |
Text
.
U. S. IiUCLEAR FICULSTORY COMMISSIO;I h,
REGION V
.
Report No. 50-344/82-16 Docket No. 50-344 License No.
NPF-1 Safeguards Group Iicensee:
Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204
-
~'
Facility Nace: Trojan
.
Inspection at: Rainier, Oregon Inspection conducted:
May 3-7, 1982 Inspectors:
dm1//t -
6-" /~ b1 W. p gner, Rea 6r' Inspector Date Signed Date Signed
=
Date Signed
_ //
[
g ///g7
- - Approved
J.
1. Eckhardt, Acting Chief ta(e Signed actor Projects Section 1 s
Summa ry:
'
Inspection on May 3-7, 1982 (Report No. 50-344/82-16)
Areas Inspected: Routine announced inspection by regional based inspector of inservice inspection activities, and previously identified followup items. The inspection involved 34 inspector hours on site by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
...,)
Q; RV Form 219 (2)
820622O326 820602 PDR ADOCK 05000344
- O PDR j
_.
.-.,.-...m
.
l
-- *
.
.
DETAILS 1.
Individuals Contacted a.
Portland General Electric Company (PGE)
- R. P. Barkhurst, Man ker, Operations and Maintenance
- J. D. Reid, Manager, Plant Services
- J. K. Aldersebaes, Manager, Nuclear Maintenance and Construction
- C. A. Olmstead, Manager, Technical Services
- R. P. Schmitt, Engineering Supervisor
- M. Hoffmann, Site Manager, Nuclear Project Engineering A. O. Wogen, Staff Mechanical Engineer M. R. Snook, Senior QA Inspector E. A. Curtis, QA/QC Inspector
b.
Westinghouse E. J. Tarby, Inservice-Inspection Coordinator R. R. Hilterman, Data Coordinator
'
- Denotes those attending exit meeting.
2.
Licensee Action on Previous Inspection Findings a.
(Closed) Followup Item (50-344/80-28/02)
This item dealt with' licensee inspection in areas excavated for wall modifications. The item remained open pending fulfillment of licensee commitments to include 50.59 analysis in the placement document packages, and to fully implement the PGE as-built inspection procedure REl-1-14. The licensee stated that procedure REI-1-14 was fully implemented and that the 50.59 analysis are included in the placement document packages. These packages are located at the PGE offices in Portland, Oregon.
This item is closed.
b.
(Closed) Followup Item (50-344/80-28/03)
This item dealt with voids discovered at the tops of walls during excavation for modification. This item remained open pending receipt of a report summarizing the results of testing in accordance with Temporary Plant Test TPT-9. This report, PGE No. TEB-7-81M, was received and reviewed by the NRC.
This item is close _-
'
.
-2-3.
Ultrasonic Examination of Steam Generator A Feedwater (FW) Nozzle The A steam generator feedwater nozzle to reducer weld (FW-145) ultrasonic (UT) examination of 1980 was initiated by IE Bulletin 79-13 " Cracking in Feedwater System Piping." FW-145 was reexamined during the 1981 outage. The comparative results of these two examinations are described in NRC Report No. 50-344/81-13.
The UT examination of FW-145 during the 1981 and 1982 outages was initiated by the licensee for engineering information only; that
,
is, to monitor the growth pattern of the indication. Reanalysis of-
'
this data by engineering revealed that the wall thickness at the location of the indication is larger than that used in the original analysis.
Factoring in the corrected thickness resulted in a maximum adjusted depth of the indication for the 1980 outage at 0.11 inch; for the 1981 outage at 0.13 inch; and for the 1982 outage at 0.10 inch. The results from these three data points are within the tolerance range of accuracy for the UT equipment used. The results show that the indication has not undergone any significant growth changes since 1980.
The licensee is planning on reexamining this feedwater nozzle during the 1983 outage to assure that growth of the indication has
,
not occurred. This item will be looked at during the next outane.
4.
WKM POW-R-Seal Valves The results of an NRC Vendor Inspection Branch investigation revealed that the Babcock'and Wilcox Company (B&W) had purchased forty-eight WKM POW-R-Seal valves with manufacturing defects. B&W subsequently distributed these defective valves to various utilities including Portland General Electric. PGE engineers assured the inspector that no WKM POW-R-Seal valves were purchased or received for use at the l
Trojan plant.
However, ten of these defective valves were received by PGE for use at the B&W Pebble Springs plant. The licensee said that repair work on these valves is completed.
5.
Inservice Inspection (ISI)
l Trojan is in its first inspection interval which covers the ten year j
period since the plant was initially placed into commercial operation (May 1976). The current ISI is in the third plant outage and includes
!
l examination of items necessary to complete the second 40-month period inspection requirements. The licensee's ISI program and activities were reviewed by the inspector for compliance with the requirements of the FSAR and ASME Section XI, 1974 Edition through Summer 1975 Addenda. The prime contractor for the ISI program is Westinghouse; I
the non-reactor vessel examinations are subcontracted by Westinghouse to The Virginia Corporation.
._
_-
-
.
---_-
-_
.
-
.
<
-3-a.
Review of Procedures The following inservice inspection procedures were examined for compliance with technical specifications and code requirements:
(1)
151-153, Revision 1, " Inservice Inspection of Reactor Vessels."
(2)
ISI-205, Revision 2, " Manual Ultrasonic Examination of Full Penetration Circumferential and Longitudinal Butt Welds."
(3)
PET-7-1, Revision 1, " Inservice Inspection."
No items of noncompliance or deviations were identified.
b.
Observation of Work and Work Activities The inspector observed the placement and alignment of the Westinghouse inservice inspection tool onto the reactor pressure vessel.
The ISI tool was used to ultrasonically examine the reactor vessel to flange weld number 1, loop 1 outlet nozzle to vessel weld number 16 and the loop 4 outlet nozzle to vessel weld number 17, No items of noncompliance or deviations were identified, c.
NDE Personnel Qualifications The qualification and certifications of the two Westinghouse NDE Level II individuals who performed the reactor vessel ISI examinations were reviewed by the inspector. Also reviewed were the qualifications of one Level I and two Level II individuals employed by The Virginia Corporation. The records were compared with the guidelines'of SNT-TC-1A.
No items of noncompliance or deviations were identified.
d.
Data Review and Evaluation'
The inspector examined the records of the following ISI examinations:
(1) Loop 1 outlet nozzle to safe-end ald number 1 (DM). Performed manually outside the vessel.
(2) Loop 4 outlet nozzle to safe-end weld number 1 (DM). Performed manually outside the vessel.
These two items are dissimilar metal weld joints requiring both ultrasonic (UT) and liquid penetrant (PT) examinations. The records reviewed were complete with data sheets, examination equipment data, evaluation data, extent of examination, disposition
..
.
-
-
..
_ __ _- _ ____ _
.
'
.
-4-of findings and evaluation of indications.
In addition, the inspector _re' viewed, the ' calibration report of the UT equipment used, certification of compliance for the UT test block, UT.couplant 1 sulfur and halogen content, and the PT penetrant, developer and
.
cleaner chemical. analysis.
+
,
s
--
,
The following listed areas were examined inside the vessel utilizing the: Westinghouse remotely ~ operated reactor vessel ISI tool in
.-
accordance with procedure 151-153.
(3.).. Vessel to flange weld number 1.
'
- (4) L60p 1 out'let nozzle to vessel weld number 17.
(5) Loop 4 outlet nozzle to vessel weld number 16.
(6) Loop 1 outlet nozzle to safe-end weld number 1 (DM).
(7) Loop 4 outlet nozzle to safe-end weld number 1 (DM).
The inspector reviewed the computer printout data sheets of the reactor vessel examinations. The calibrations and evaluations were in accordance with code and Westinghouse procedures. Preliminary results indicate that'no valid indications, either reportable or recordable, were detected.
No items of noncompliance or deviations were identified.
6.
Exit Meeting The inspector met with licensee representatives (denoted in paragraph 1)
on May 7, 1982.
The scope of the inspection and findings as detailed in this report were discussed.