IR 05000206/1982014
| ML20053C707 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/10/1982 |
| From: | Eckhardt J, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20053C701 | List: |
| References | |
| 50-206-82-14, NUDOCS 8206020486 | |
| Download: ML20053C707 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-206/82-14 Docket No. 50-206 License No. DPR-13 Safeguards Group Licensee: Southern California Edison Company
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2244 Walnut Grove Avenue Rosemead, California 91770
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Facility Name:
San Onofre Unit 1
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Inspection at: San Clemente, California
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Inspection conducted: April 19-22, 1982 Inspectors:
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ner, Reacto Inspector
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Approved by b(
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J H. Eckhardt, Acting Chief Sat ( Signed eactor Projects Section 1 Summary:
Inspection on April 19-22, 1982 (Report No. 50-206/82-14)
Areas Inspected:
Routine, announced inspection by regional based inspector of construction activities associated with the seismic upgrading of the turbine building, eddy current testing of steam generator tubes, and inservice inspection. The inspection involved 28 onsite inspection hours by one NRC inspector.
Results:
No deviations or items of noncompliance were identified.
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8206020486 020511 PDRADOCK05000g
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DETAILS 1.
Individuals Contacted a.
Southern California Edison Company (SCE)
- W. C. Moody, Deputs/ Station Manager
- G. W. Mcdonald, QA/QC Supervisor
- F. P. Riley, QA Engineer
- B. I. Sanano, QA Engineer
- J. D. Dunn, Project QA Supervisor
- M. J. Speer, Compliance Engineer R. Montroy, QA Engineer A. Menichiello, Nuclear Engineer E. I. Holmes, Nuclear Engineer
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M. P. Short, Supervising Engineer II J. T. Reilly, Engineer I C. C. Warren, QA Engineer b.
Westinghouse Electric Company E. N. Hayden, Senior Quality Engineer
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R. A. Vollmer, Shift Supervisor c.
Bechtel Power Corporation (Bechtel)
J. Sherman, Senior QA Engineer G. Bishop, QA Engineer
- Denotes those attending exit meeting.
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2.
Concrete Placement Activities The concrete placement that was postponed during the previous inspection (Report No. 50-206/82-12), due to a high-water level under the soil foundation, was completed. The~ inspector reviewed the construction inspection data reports'(CIDR's). to verify that the
concrete preplacement and placement activities were performed in
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l accordance with licensee's work plan procedures and quality control
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instructions. The' inspector also_ reviewed NCR No. S01-F-2363, initiated by the licensee prior to the concrete placenent. The NCR, which identifies nonconforming aggregate, was reviewed a'nd approved by qualified civil and quality assurance personnel and appeared to
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be properly dispositioned.
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No items of noncompliance or deviations were identiried.
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3.
Eddy Current Testing (ECT) of Steam Ge'nerator Tubes
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In accordance with License Condition 3.E San Onofre Unit 1 was shutdown to perform ECT in order to monitor the effectiveness of the 1980-1981 steam generator repair program.
a.
ECT Personnel Qualification Records The inspector reviewed the qualifications and certifications of
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one Level I and two. Level II ECT examiners for compliance with the guidelines of SNT-TC-1A. The examiners were qualified and their vision test records up-to-date.
b.
ECT Equipment The ECT equipment used is a Zetec MIZ-12 instrument with a two channel storage display oscilloscope,'two channel strip chart recorders, and Hewlett Packard eight channel eight track tapes. The examination equipment, sensitivity, and calibration were consistent with the approved Westinghouse ECT Procedure No. f1RS 2.4.2 GEN-23 " Multi-frequency Eddy Current Inspection of Heat Exchanger Tubing-Preservice and Inservice" of January 8, 1982.
No items of noncompliance or deviations were identified.
4.
Inservice Inspection a.
Inservice Inspection Program The inspector reviewed the licensee's inservice inspection (ISI)
program for compliance with requirements of the Plant Technical Specification Section 4.2.1 and ASME Section XI, 1974 Edition through Summer 1975 addenda. The ISI plan describes the area
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and extent of examination. Westinghouse is the prime ISI contractor, although the_ majority of examinations' were subcontracted out to Sonic Systems International.
b.
NDE Personnel Qualifications NDE qualification records and certifications were compared with the guidelines of SNT-TC-1A for three individuals involved in NDE activities during this outage No items of noncompliance or deviations were identified.
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-3-e Review and Evaluation
' records for the following components were reviewed:
Pressurizer Spray Line - 3" Sch 160 (2) Reactor Coolant Pipe - 32" & 36" (3) Mainsteam Line - 20" Sch 60 (4)
Feedwater Line - 10" Sch 80 (5) Containment Spray Line - 6" Sch 40 (6) RHR Line - 6" Sch 40 The records reviewed were complete with data sheets, examination equipment data, evaluation data, extent of examination, disposition of findings and evaluation of indications. The records were in compliance with NDE procedures and ASME Section XI requirements.
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The inspector also reviewed the certification of the following NDE items: equipment calibration, UT couplant sulfur and halogen content (Assay Report), transducer, and liquid penetrant chemical analysis.
No items of noncompliance or deviations were identified.
d.
Repairs No repairs have been performed. involving excavation and welding as a result of the inservice inspection examination. However, the following NCR's were written and are currently undergoing disposition for corrective action and may require repair welding; (1) NCR No. 912 - FeedwaterzLine 391-IW-2, (weld separation)
(2) NCR No. 924 - Steam Generator Manway Bolting (damaged threads)
(3) NCR No. 925 - Feedwater Line 320-IW-1 (linear indications)
(4) NCR No. 926 - Feedwater Line 392-IW-6 & 7, and 393 IW-2 (weld separation)
No items of noncompliance or deviations were identified.
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5.
Reactor Vessel Surveillance Program The inspector reviewed the reactor vessel surveillance program for compliance with the requirements of 10 CFR 50 Appendix H, the FSAR and ASTM E-185. The reactor vessel archive (control) material
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was not available for inspection at the site.
However, the inspector reviewed the test data and reports and found them to be consistant with the applicable requirements. The review included data related to the mechanical property changes to the reactor vessel material due to irradiation.
No items of noncompliance or deviations were identified.
6.
Exit Meeting The inspector met with licensee representatives (denoted in paragraph 1)
on April 22, 1982. The scope of the inspection and findings as detailed in this report were discussed.
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