IR 05000334/1993008
| ML20036B707 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/28/1993 |
| From: | Gray E, Patnaik P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20036B704 | List: |
| References | |
| 50-334-93-08, 50-334-93-8, NUDOCS 9305270109 | |
| Download: ML20036B707 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
REPORT NO.
50-334/93-08
DOCKET NO.
50-334 LICENSEE:
Duquesne Light Company FACILITY NAME:
Beaver Valley Power Station, Unit 1 INSPECTION AT:
Shippingport, PA INSPECTION CONDUCTED:
April 12-16,1993 i
kM 4'17 93 NRC PERSONNEL:
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Pat Patnaik, Reactor Engineer Date I
Materials Section, EB, DRS i
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h Y!2fb3 APPROVED BY:
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E. H. Gray, Chief, daterials Date
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Section, EB, DRS Areas Insmeted: Observation of nondestructive examination acdvities, review of portions of l
the ISI program, a sample of inspection data on the inservice inspection, and the eddy
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current examination of steam generator tubes during the ninth refueling outage of the Beaver Valley Power Station, Unit 1.
Results: The nondestructive examination activities were performed in accordance with applicable procedures. The inservice inspection program and the eddy current examination program were reviewed for the ninth refueling outage of the Beaver Valley Unit 1. These complied with the applicable code and the regulatory requirements. The inspection data on the above that was sampled for review were satisfactory. The licensee's data evaluation and identification of defective steam generator tubes for plugging was found to be conservative.
9305270109 930520 PDR ADOCK 05000334 O
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DETAILS 1.0 INSERVICE INSPECTION (ISI), INSPECTION PROCEDURE (IP) 73753
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1.1 Scope
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j Inservice inspection by ultrasonic, magnetic particle, liquid penetrant, and visual examinations is performed to ensure integrity of the reactor coolant pressure boundar.'es. An _
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inservice inspection is mandated by the ASME Boiler and Pressure Vessel Code,Section XI, and is essential to promote public health and safety.
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1.2 Program Review
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During the ninth refueling outage starting April 1993 of Beaver Valley Unit 1, Duquesne Light Company (DLC) conducted an inservice inspection in accordance with the ASME
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Code,Section XI,1983 Edition, including the Summer 1983 Addenda. The current
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refueling outage is the second scheduled outage of the second period in the second ten-year
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inspection interval, which started on September 21,1987. As permitted by 10 CFR 50.55 a
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(b)(2)(ii), the selection criteria for Class I piping for examination is based on the ASME
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Code,Section XI,1974 Edition, including the Summer 1975 Addenda. For the examination
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of Class II piping, the licensee applied the provisions of the alternate rules in the Code Case, N-408, in lieu of the examination requirements of Category C-F, in the applicable ASME
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Code,Section XI.
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A sample of welds in the outage plan was reviewed against the requirements of the applicable
ASME Code,Section XI, and no deficiencies were noted.
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The licensee controlled the inspection activities through Beaver Valley Quality Services (QS)
procedures. The inspector reviewed the following sample of procedures to ensure that the j
inservice inspection is controlled effectively.
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Procedure Title Purpose QSP16.1, Rev.1 Initiation of a QS Establishes a system to Deficiency Report document and obtain timely written resolution of non-conforming conditions that are generated following various types of surveillances, inspections, examinations, or audits.
QSP9.4, Rev. O Nondestructive Describes the manner in Examinations (NDE)
which the Quality Services Unit performs and documents NDE and associated activities.
QSP9.5, Rev. O Surveillance of NDE Describes surveillance of Activities NDE activities by the Quality Services Unit to assure that the activities are conducted in accordance with applicable procedures, codes, and specifications.
The inspector was satisfied with the review of the above procedures and had no comment.
1.3 Observation of Work The inspector witnessed in-progress nondestructive examinations, fit up, and welding of safety-related components during a site tour as summarized below.
Ultrasonic examination of pressurizer spray piping welds numbered
RC-98-1-5-06, RC-99-1-E-03, RC-98-1-5-05, and RC-99-1-F-01.
Magnetic particle examination of main steam piping supports identified as
SHP-56-10-5-44, SHP-56-10-5-49, and SHP-56-10-5-16.
- Welding on Recirculation Spray Heat Exchanger 1-WR-87-F-1 A-C,1-WR-88-F-3A-C,1-RS-2-F-4C, and 1-RS-26-F-5AAC.
Weld Fit up Inspection on Feedwater Nozzles
1-WFPD-24-F-13-C,1-WFPD-22-F-12-C,1-WFPD-24-81-F-1B-c, and 1-WFPD-22-83-F-1B-.
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l The inspector observed that proper procedures were being followed for the activities in progress and the operators were knowledgeable of the techniques specified in the procedures.
1.4 Procedure and Personnel Certification Review
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The inspector reviewed the applicable nondestructive examination procedures governing the above-mentioned work activities as stated below:
Procedure Iltle UT-303, Rev. I1 Ultrasonic Examination of piping welds 0.2 inch to 6 inches thick and vessels less than or equal to 2 inches wall thickness.
MT-201, Rev.10 Magnetic Particle Examination.
I The certifications of contractor's personnel who performed nondestructive examinations at Beaver Valley Unit I during the outage were reviewed. There were no deficiencies noted in the review of procedures and personnel certifications.
1.5 Data Review The licensee conducted the inservice inspection prior to the outage of systems that were accessible during plant operations and hence, the data on the following welds were available for inspector's review:
QS-1-3B-L-201, CH-FL-4HB-C-2, SI-133-5-5-03, CH-FL-AB-N-3, CH-FL-4B-C-1, and SI-29-5-F-05.
There were no recordable indications in excess of 50 percent DAC in the above welds.
A liquid penetrant examination of the socket weld between the disc pressurization line and the loop isolation valve revealed a linear indication 1.25 inches long. The licensee documented the indication in Deficiency Report No.107 for resolution. However, a similar indication was also found in the corresponding weld of Unit 2 during the third refueling outage, which was repaired and, subsequently reanalyzed by Engineering. From discussions with appropriate personnel, the inspector was assured that the indication in Unit I will be repaired and the line would be modified in the same way as Unit.
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1.6 Conclusion Based on the review of the outage plan, examination records, procedures, and interviews with personnel, the inservice inspection program and its application at Beaver Valley Unit 1 l
for the areas inspected was found to meet the requirements of the applicable code and the
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NRC regulations.
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2.0 STEAM GENERATOR EDDY CURRENT EXAMINATION (IP73753)
2.1 Scope The steam generator eddy current examination is performed to ensure integrity of steam
generator tubes, and hence, the reactor coolant pressure boundary. This examination was
performed during the ninth refueling outage to comply with the requirements of the Technical Specification.
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2.2 Finding The licensee performed a full-length bobbin coil examination from the cold leg, on one
hundred percent of inservice tubes in each steam generator (S/G). In addition, the following i
exploratory examinations were also performed.
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Bobbin coil eddy current examination for rows 1 through 3 in hot leg up to the e
seventh support in the hot leg.
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MRPC (Motorized Rotating Pancake Coil) examination of B&W plugs.
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MRPC examination of explosively expanded tube region (Wextex).
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MRPC examination Of rows 1 and 2 U-bends.
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MRPC examination of distorted support plate indications (DSI) found during the i
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eighth refueling.
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MRPC examination of DSIs found during ninth refueling, j
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e MRPC examination of special interest.
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During this inspection, the examination of A and B steam generators (SGs) were completed.
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The results of the examination revealed a total of 221 tubes in the A SG and 197 tubes in the B SG were found defective, and were required to be plugged. For 40 tubes in the A SG (out of 221) and 15 tubes in the B SG (out of 197), the indications that exceeded the plugging
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limit of forty percent through wall could not be confirmed by MRPC. The licensee conservatively identified these tubes for pluggmg.
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The inspector reviewed the data analysis guideline for eddy current examination using a bobbin coil probe and an MRPC probe and found no deficiency. All certifications for contractor's personnel involved in the examination were available and were found to meet the requirements of SNT-TC-1A.
The inspector witnessed portions of data acquisition and subsequent plugging of tubes during this inspection.
2.3 Conclusion For those areas inspected, the eddy current examination and the plugging of defective tubes met the requirements of the Technical Specification. The licensee's data evaluation and identification of defective tubes for plugging was noted to be conservative.
3.0 ENTRANCE AND EXIT MEETINGS Members of the licensee's management were informed of the scope and the purpose of this inspection at the entra.ce meeting that took place on April 12, 1993. The findings of the inspection wae presented to and discussed with members of the licensee's management at the conclusion of the inspection on April 16, 1993. The licensee did not take issue with the findings discussed at the exit meeting. A list of attendees at the exit meeting is appended to this report as Attachment.
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A'ITACHMENT I i
LIST OF A*ITENDEES Ducuesne Light Comoany John Baumler, Director Quality Services J. J. Giocondi, NDE Supervisor K. Grada, Mgr, Quality Services Unit G. Kammerdeiner, Director, Materials Engineering F. Lipchick, Sr. Licensing Supervisor T. Noonan, General Manager, Nuclear Engineering and Safety M. A. Pergar, Director, Quality Services B. Sepelak, Licensing W. Sikorski, Director, ISI D. E. Spoerry, Vice President, Nuclear Operations G. S. Thomas, Vice President, Nuclear Services N. R. Tonet, Manager, NSD U.S. Nuclear Regulatory Commission L. Rossbach, Senior Resident Inspector