IR 05000338/1979040
| ML19260D301 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/01/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260D265 | List: |
| References | |
| 50-338-79-40, 50-339-79-53, NUDOCS 8002080283 | |
| Download: ML19260D301 (6) | |
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UNITED STATES g
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ATLANTA. GEORGIA 30303 NC'l - 71979 Report Nos. 50-338/79-40 and 50-339/79-53 Licensee: Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: North Anna Power Station Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and CPPR-78 Inspection at North Anna site near Mineral, Virginia Inspector:
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Ddte S'igned Approved by:
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7f A. R. Herdt, Section Chief, RC&ES Branch Date Signed SUMMARY Inspection on October 9-12, 1979 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours on-site in the areas of inservice inspection (Unit 1), steam generator feedwater line radiography (Unit 1), and inspection of stagnant borated water systems (Unit 1).
Results Of the three areas inspected, no items of noncomplirace or deviations were identified in two areas; one apparent item of noncompliance was found in one (Failure to follow liquid penetrant procedure paragraph 7.d).
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DETAILS 1.
Persons Contacted Licensee Employees
- W. R. Cartwright, Station Manager
- J. W. Martin, Jr., Supervisor, Quality Assurance
- E. W. Harrell, Superintendent of Maintenance
- H. L. Travis, Mechanical Foreman, NDT
- C. B. Swope, Senior QC Inspector
- E.
R. Smith, Jr., Superintendent of Technical Services
- W. R. Madison, NRC Coordinator S. L. Harvey, Operating Supervisor Other licensee employees contacted during this inspection included technicians and security force members.
Other Organizations E. J. Tarby, Site Coordinator (Westinghouse-NSD)
J. W. Bell, Assistant Site Coordinator (Westinghouse-NSD)
NRC Resident Inspector M. S. Kidd
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on October 12, 1979 with those persons indicaced in Paragraph I above.
The noncompliance of para-graph 7.d was discussed in detail.
The licensee had no dissenting comments.
In addition, the status of Bulletins 79-13 and 79-17 were discussed. The inspector stated that revisions are being issued to both Bulletins which will clarify questionable areas.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 338/79-17-02, Permeability Problems-Steam Generator Tube Eddy Current Inspection. Appendix D to the Baseline Eddy Current report discusses the probable cause and effect of the Eddy current per-meability signals and concludes that the problem will not " impair the integrity of the tubing or result in any detrimental effect in service".
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Inservice Inspection-Review of Program (Unit 1)
The inspector reviewed the licensee's Inservice Inspection (ISI) program for the current outage in the areas of: program approval; QA program requirements including organizational structure, audit requirements, general QA requirements (examination reports, control of deviations from established program, quality documentation and identification of components), work and quality inspection procedures, control of processes, corrective action, document control, control of examinations and examination equipment, and quality records; inspection scope; inspection intervals; personnel quali-fication; and NDE records including provisions for storage.
The applicable code for the ISI is the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, with Addenda through the Summer of 1975.
The documents reviewed included:
a.
" Inspection Program Plan for Virginia Electric and Power C ny-North Anna Unit #1-Refueling Outage I-II 1979" b.
Westinghouse Nuclear Services Division (W-NDS) " Quality Assurance Program Plan" WCAP 9245, Revision 4 c.
W-NDS procedure OPS-NSD-101, Revision 5, A m.
03, "Preservice and Inservice Documentation" d.
W-NDS procedure OPR 610-1, Revision 1, " Preparation of Procedures for Field Services" W-NSD procedure OPR 610-3, Revision 1, " Control of Field Services e.
Activities" f.
W-NSD procedure OPR 205-3, Revision 1, " Inspection Verification" g.
W-NSD procedure OPR 210-4, Revision 0, " Control of Nonconformances on NSD Items and Services" h.
W-NSD procedure NSD-ISI-10, Revision 4, Amendaent 01, "Preservice and Inservice Examination Manual Ultrasonic Equipment Qualification" i.
VEPCO " Nuclear Power Station Quality Assurance Manual
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Section 1, Revision 3, " Organization" Section 9, Revision 2, " Control of Special Processes"
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Section 10, Revision 3, " Inspections"
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Section 16, Revision 11, " Corrective Action"
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Section 18, Revision 4, " Audits" g
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VEPC0 " Nondestructive Test Manual" Procedure NDT-1.1, " Responsibility and Authority-Nondestructive
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Test Group" Procedure NDT-4.1, "NDT Written Practice"
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VEPC0 North Anna procedure " Inservice Inspection Program Administration" Within the areas inspected, no items of noncompliance or deviations were identified.
6.
Inservice-Inspection Review of Procedures (Unit 1)
In addition to the procedures listed in paragraph 5 above, the inspector reviewed the ISI procedures indicated below to determine whether the pro-cedures were consistent with regulatory requirements and licensee com-mitments.
See paragraph 5 above for the applicable codes.
ISI-8, Revision 7, Amendment 01, " Visual Inspection Procedure" a.
This procedure was reviewed in the areas of procedure approval and qualification of personnel.
b.
ISI-11, Revision 9, Amendment 09, " Liquid Penetrant Examination Procedure" This procedure was reviewed in the areas of procedure approval, per-sonnel qualification requirements, compilation of required records, and procedure technical content relative to:
method consistent with ASME code, specification of brand names of penetrant materials, speci-fication of limits for sulfur and total halogens for penetrant materials, pre-examination surface preparation, minimum drying time following surface cleaning, penetrant application and penetration time, temper-ature requirements, penetrant removal, method of surface drying, type of developer and method of application, examination technique, technique for evaluation, and acceptance standards.
c.
ISI-47, Revision 2, Amendment 06, " Manual Ultrasonic Examination of Circumferential and Longitudinal Butt Welds in Ferritic Vessels of 2'2 Inches Thick and Greater" This procedure was reviewed in the areas of procedure approval and qualification of personnel.
d.
ISI-205, Revision 2, Amendment 03, " Manual Ultrasonic Examination of Full Penetration Circumferential and Longitudinal Welds" This procedure was reviewed in areas of procedure approval, personnel qualification requirements, compilation of required records, and i94J 127
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procedure technical content relative to: type of apparatus, extent of coverage including beam angle and scanning techniques, calibration requirements, search units, DAC curves, reference level for menitoring discontinuities, method of demonstrating penetration, levels for evaluation and recording indications, and acceptance criteria.
e.
ISI-70, Revision 0, " Magnetic Particle Examinations" This procedure was reviewed in the areas of procedure approval and qualification of personnel.
Within the areas inspected, no items of noncompliance or deviations were identified.
7.
Inservice Inspection-Observation of Work and Work Activities The inspector observed the ISI activities described below to determine whether these activities were being performed in accordance with regulatory requirements and licensee procedures.
See paragraphs 6 and 7 above for the applicable codes and procedures.
Personnel qualification records for one level I, two level II and one a.
level III (VEPCO) examiners were reviewed b.
In process angle beam ultrasonic (UT) examination (weld and base material) including the calibration process was observed for welds 1 and 2 on ISO VRA-1-4102.
c.
Visual examination of support weld WS-2 on ISO VRA-1-4102 was observed.
d.
In process liquid penetrant (PT) examination was observed on welds 4, 5, 6, 7, 8, 9 and 10 on ISO VRA-1-4109. During observation of the PT, the inspector noted that for welds 5, 7, 8, 9 and 10, excess penetrant was not adequately removed as required by paragraph 3.3 of W-NSD procedure IIS-11, resulting in a surface too pink for proper evalua-tion. The level II examiner evaluated the test as if it was a valid test. Upon request by the inspector, the VEPCO Mechanical Foreman-NDT (qualified level II in PT) and the W-NSD site coordinator observed the test results and agreed that the welds should be retested. This failure to follow procedure is considered to be noncompliance with Criterion V of Appendix B to 10 CFR 50 as implemented by section 5 of VEPCO Nuclear Fower Station Quality Assurance Manual and is identified as item 338/79-40-01, " Failure to Follow PT Procedure".
Within the areas inspected, no items of noncompliance, except as noted in paragraph 7.d, or deviations were identified, i94]
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IE Bulletins (IEB)
(Open) IEB 79-13, Cracking in Feedwater System Piping, Unit 1.
The inspec-tor performed a followup inspection of radiography which was performed to meet Bulletin requirements. The radiography was performed in accordance with Field Quality Control Procedure (FQCP) QC-14.6, " Radiographic Examina-tion of Welds" except that evaluation was to the 1977 Edition, including addenda through the Summer of 1979 of ASME, section III, Subsection NC, paragraph NC-5000 to the 2T quality level. The inspector reviewed film for the following welds:
Loop "A" Weld 29 (Nozzle Weld)
Weld 10 Weld 7 Weld 21 Weld 11 Loop "B" Weld 24 (Nozzle Weld)
Weld 4 Weld 8 Weld 15 Weld 17 Loop "C" Weld 20 (Nozzle Weld)
Weld 15 Weld 16 Weld 4 Weld 8 At the time of the inspection, all radiography required by the Bulletin had been completed except that the site had interpreted the Bulletin to allow surface examination for the feedwater line base material downstream of the auxiliary feedwater connection.
The inspector pointed out that the intent was for a volumetric inspection of this area.
The licensee agreed to volumetrically examine the area and initiated radiography inspection while the inspector was on site.
(0 pen) IEB 79-17, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants (Unit 1).
The inspector discussed the Bulletin with responsible licensee personnel.
The licensee has identified the affected systems, responded to part 1 of the Bulletin, and is in the process of establishing a sampling plan for part of the inspections required by part 2 of the Bulletin.
VEPCO has requested an extension for the time allowed to perform the inspections required by paragraph 2 of the Bulletin.
Within the areas inspected, no items of noncompliance or deviations were identified.
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