IR 05000397/1985014
| ML17277B746 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/25/1985 |
| From: | Casella F, Johnson P, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17277B745 | List: |
| References | |
| 50-397-85-14, NUDOCS 8505220296 | |
| Download: ML17277B746 (8) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION REGION'
Report No. 50-397/85-14 Docket No. 50-397 License No. NPF-21 Licensee:
Washington Public Power Supply System P. 0.
Box 968 Richland, Washington 99352 Facility Name:
WNP;2 Inspection at:
Benton County, Washington Inspection Conducted:
April
Inspector:
F. A.
C sel a
e to ctor Date Signed Approved by:
T.
ng, Jr., Chief, Engi e i g ction Date Signed P.
H.
o nson, Chief Reacto Projects Section
Date Signed
~Summar:
Ins ection on A ril 1-5 1985 (Re ort No. 50-397 85-14)
review of the program, records and procedures pertaining to the WNP-2 Inservice Inspection for pressure boundary piping welds and supports, along with a review of (}uality Assurance records that pertained to Inservice Inspection.
The inspection involved a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> onsite by one NRC inspector.
Results:
In the areas inspected, there were no violations of NRC requirements.
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DETAILS Persons Contacted-J. Martin, Plant Manager
"-C. Powers, Assistant Plant Manager
-"D. Feldman, Plant (}A Manager-D. Porter',
Manager Support Engineering
"-D. Ramey, XSI Engineer
<W. Fitch, Executive Secretary, Washington State Energy Facility Site Evaluation Council
"-T.. Hoyle, Supervisor, Code Programs-W. Aeschliman, Iicensing Engineer
>"J. Brent, Authorized Nuclear Inspector, Lumberman Mutual Insurance D. Kidder, Technical Staff Supervisor M. Reis, ISI Program Leader K. Hannah, Manager ISI/NDE D. Welsh, Site Ievel III
"Denotes those attending the exit interview on April 5, 1985.
Preservice Ins ection Results The inspector reviewed the Preservice Inspection (PSI)
Summary Report for pressure retaining Class 1,
2 and 3 components and supports inspected during the period November 1976 through March 1983.
The report was approved and signed by the Authorized Nuclear Inspector (ANI) on April 27, 1983.
CFR 50.55a(g)
requires this plant to comply with the requirements of ASME Boiler and Pressure Vessel Code Section KI 1971 Edition through the Winter 1971 Addenda.
WNP-2 voluntarily complied with the 1974 Edition through Winter of 1975 Addenda and the Appendix III Winter 1975 Addenda in order to smooth the transition to the Xnservice Inspection (ISI)
Program.
This was a conservative approach and complied with NRC requirements.
In addition to this basic upgrade, the licensee had 9 exceptions to the Code commitments.
These were substantially upgrades to the 1977 Edition through Summer of 1978 Addenda.
These exemptions were reviewed by the inspector with no discrepancies noted.
The licensee also performed a number of examinations in excess of Code requirements.
There is an Augmented XSI series on 213 welds in high energy Class 1 pipes which penetrate containment for which there are unacceptable effects of postulated ruptures.
Seventy of these welds do not fall under any Code jurisdiction, yet have been fully inspected.
Class 2 pipes greater than
~g inch NPS and all Class 1 pipes are PT inspected as well as UT inspected.
All angle beam examination results are recorded on strip charts for future comparison.
The Reactor Pressure Vessel feedwater nozzle inner radii are inspected utilizing a 70O angle beam IGSCC technique qualified on a full sized mock-up in the NDE la I
The inspector also reviewed Tables summarizing recordable pressure vessel indications, pressure vessel geometric indications, and Balance of Plant significant indications.
There were no discrepancies noted.
Pressure Vessel Re air Welds The Chicago Bridge and Iron (CBI) Fabrication Report on the WNP-2 reactor pressure vessel was reviewed for indications of repairs to base metal.
Major Repair Procedure 1, dated 5/10/73, describes a large rejectable lamination in the Number 2 Ring Shell Segment (Piece Mark 22-1-4).
The defect was excavated and a repair weld was performed.
This ring shell segment is within the core beltline zone of the vessel.
The inspector compared the locational and dimensional information for this weld repair in the CBI report to that called out in the PSI and ISI program documents and was satisfied with the correspondence.
The ISI program complies with the Code requirement that this repair weld be inspected during the first 10 year interval.
Another repair was performed under Major Repair Procedure 4 dated 11/6/73.
Number 1 Shell Ring Plate (Piece Mark 21-1-3)
had four discrete pockets of inclusions and delaminations surrounding the 120'et pump nozzle (N2).
As a result, metal was excavated from a strip 270'round the penetration, about 7" wide and 5q" deep, in what would become the heat effected zone outside the centerline of seam KA.
A repair weld was completed and MT, RT and UT acceptance tests were performed.
This repair was below the beltline region and is not required to be reinspected during the ISI program.
The licensee has however committed to performing volumetric examinations specifically in the repair area whenever local weld inspections are called out.
The only other two repairs to base material were a surface defect in a main steam nozzle and a safe end weld butter defect in a jet pump nozzle.
Neither of these had any bearing on ISX requirements.
Inservice Ins ection Pro ram The inspector reviewed the ISI Program, Revision 0, which has not been issued.
The Program was found to be in accordance with 10 CFR 50.55a(g)(4)(i),
generally committed to the ASME Boiler and Pressure Vessel Code Section XI 1980 Edition through the Winter of 1980 Addenda.
There were additional upgrades and commitments and a number of exemptions which were reviewed and found to be in compliance with NRC requirements.
The licensee has structured the ISI program around Plan B of Subsection 1WA-2420, requiring 10 year intervals divided into 3 40 month periods.
There were no violations of NRC requirements identified.
Procedure Reviews Management of the ISI Program is controlled by Nuclear Operations Standard-33 (NOS-33), "Inservice Inspection".
The inspector reviewed Revision 1 of this document, dated 11/18/84, and found that it adequately establishes the requirements and delineates responsibility for ISI activitie ~
N I
The inspector also reviewed the technical adequacy of five nondestructive evaluation (NDE) procedur'es written to control ISI activities.
These were UTP-10) Revision 1, dated 3/1/79, "Ultrasonic Examination of Nuclear Coolant System Piping"; UTP-14, Revision 1, dated 1/20/81,
"Beam Spread Measurement";
UTP 32'evision 1, dated 12/9/81
UTP-30, Revision 2, dated 9/18/81
"UT of RPV Butt Welds and Adjacent Base Metal"; and SLT 303.0, Revision 0, dated 9/1/82 "Visual Examination of Component Supports".
There were no deficiencies noted.
Incor oration of Plant Modifications The licensee has sufficient administrative controls in effect to assure that pertinent plant modifications are incorporated into the XSI program.
Technology Directorate Procedure TDP-4.4, "Preparation of ISI Program Plans" establishes responsibilities and provides guidelines for preparing and changing the program plan.
Xt also provides for a specific input and review circuit for isometric drawings and weld and support list changes.
In addition, there are 2 procedures that control ASME Pressure Boundary repair and replacement requirements and the preparation of design change packages.
These are NOS-21 and TI2.1 respectively.
These procedures assure ISI accessibility review prior to fabrication and inclusion of modifications into the ISI program whenever necessary.
Data Review and Evaluation The inspector reviewed a sample of 8 data sheets.
These were RIU-006, HPU-055, 1210-33, 1210-28, RHP-062, RHP-151 and MSU-514.
The data sheets were inspected for evidence of procedural compliance, accuracy of calibration and description of findings.
All reports reviewed were complete and complied with Code and procedural requirements.
Control of Contractors The inspector reviewed a binder of Technical Surveillance Daily Log Sheets.
These log sheets were evidence of close daily monitoring of contracted inspectors by licensee staff NDE personnel.
In addition, thirteen QA Department Surveillances and 2 QA Audits were reviewed.
These were completed between 12/76 and 4/80, and dealt with a variety of specific procedural and technical aspects of preservice inspection.
It appears that contracted inspection work was adequately controlled by the licensee.
'here were no violations of NRC requirements noted.
Mana ement Meetin The inspector met with licensee management personnel denoted in paragraph 1 at the conclusion of the inspection on April 5, 1985.
The scope, observations and findings of the inspections were discusse r A