IR 05000206/1981016
| ML20004B949 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/22/1981 |
| From: | Kirsch D, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20004B944 | List: |
| References | |
| 50-206-81-16, NUDOCS 8106010346 | |
| Download: ML20004B949 (4) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50-206/81-16 Report No.
50-206 License No.
DPR-13 Safeguar[s Group Docket No.
Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770
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San Onofre Unit 1 Facility Name:
Camp Pendleton, California Inspection at:
Inspection conducted:
May 12-15,1981 Inspectors:
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agner, Rea r Inspector
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Date Signed f.- 2,7 - 7 /
Approved By:
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DT F. Kirsch, Actiiig Chief, Reactor Projects Section 1 Date signed Reactor Construction Project Branch Summary:
Areas Inspected:
Routine, unannounced inspection of welding activitdes associated with modifications
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made to the auxiliary feedwater system, and repair of circumferential welds on the main steam piping.
Inspection also included review of licensee action on open items from previous inspections.
The inspection involved 23 inspector hours onsite by one flRC inspector.
Results:
No items of noncompliance or deviations were identified.
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RV Form 219 (2)
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DETAILS 1.
Persons Contacted a.
Southern California Edison (SCE)
- J. M. Curran, Plant Manager
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- F. Briggs, Compliance Engineer
- D. E. Nunn, Manager, Quality Assurance
- J. G. Haynes, Manager, Nuclear Operations
- H. E. Morgan, Assistant Plant Manager, Operations
- B. Katz, Supervising Engineer
- G. W. Mcdonald, Quality Assurance /Ouality Control Supervisor
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- J. D. Dunn, Project Quality Assurance Supervisor C. Moran, Construction Engineer F. Krall, Construction Superintendent J. Buckles, Quality Assurance / Quality Control Supervisor
b.
Bechtel Power Corporation (Bechtel)
J. Shennan,-Senior Quality Assurance Engineer W. J. Quiris, Lead Field Welding Engineer J. Hefferon, Field Welding Eng'ineer j
- Denotes attendance at management interview on May 15, 1981.
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In addition, Mr. R. J. Pate, the NRC Sanior Resident Inspector, attended the interview.
2.
Licensee Action on Previous Inspection Findings a.
(Closed) Open Item (50-206/80-11/01) Anchor Bolt Procedure Special Engineering Procedure, SPE-178, Revision 5 did not contain provisions for verification that full anchor bolt expansion had
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been achieved as required by IE Bulletin 79-02. This procedure, titled " Testing of Concrete Anchor Expansion Bolts per IE Bulletin 79-02" had been revised to incorporate the bulletin requirement.
This item is closed.
b.
(Closed) Open Item (50-206/80-11/05)-Pressurizer Safety Valve Test Data The pressurizer safety valve maintenance record for valves 532 and 533 could not be retrieved for the year 1977 (NRC Report 50-T_06/80-11).
The Inspection Planning Data Report, No. SIP-16, had been located for these valves and was available for review
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during this inspection. The inspector reviewed the data report
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for proper inspection instructions and verified that the required OA/QC approvals were in accordance with maintenance procedure
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S-I-1.4.
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This item is closed.
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3.
Weldino Activity Associated with Modifications and Reoairs a.
Auxiliary Feedwater Modifications Modifications made to the Auxiliary Feedwater (AFW) System appear to be completed except for final hydro testing. The following completed weld joints were selected for inspection:
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Manifold valve 381A to pipe; field weld AF251 2.
Block valve 397B to transition piece; field weld AF302 3.
Flow control valve (FCV) 3301 to fitting; field weld AF83 4.
Block valve 381B to pipe; field weld AF108 5.
Block valve 381C to pipe; field weld AF170 The State of California and the ASME consider piping from the main feedwater system to the first block valve of the AFW system to be boiler external piping. This part of the system, including field weld AF170 above, must naet the requirements of ASME Section I, whereas the remainder of the AFW system is fabricated and installed to ANSI B31.1 requirements. Since the AFW piping is unoer 4 inch diameter only visual examination is required.
Although the weld joints were painted for protection against corrosion the inspector was able to determine, by examing the weld profile or contour, that the welds were made using the proper current, voltage and speed.
The weld procedure specification utilized in welding these joints is WPS ?M. P1-AT-Lh, Revision 3.
The inspector examined. this procedure for compliance with ANSI B31.1, and ASME Sections I and IX. The weld procedure appeared to be in accordance with these requirements.
The inspector reviewed the performance qualification records for the five welders involved in welding these joints. All were oualified, on the date the welds were made, in accordance with ASME Section IX for the weld procedure and positions used.
The inspector also examined the Field Weld Checklist for each of the five welds selected for inspection. These checklists (travelers) listed the proper material identification, weld filler metal and weld procedure, and contained the necessary QC ar. ANI approvals as required.
In conjunction with these checklists, the inspector examined the Filler Metal Withdrawal Forms and found them to be compatible with the corresponding Field Weld Checklist.
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No items of noncompliance or deviations were identified.
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b.
Main Steam Line Recair Welds During the 1980 outap; radiographic examination was performed of certain circumferential welds on the 24-inch main steam piping, in response to a serbal request from flRR. The examination results showed reportable indications in five welds. All five welds have subsequently been repaired.
The inspector was not able to visually examine the repair welds; however, the inspector examined the radiographs of the five repair welds for. compliance with ASME B&PV requirements.
Attributes examined included proper placement of penetrameters, radiographic sensitivity, film density in area of interest, film identification, quality, and evidence of discontinuities. The inspector also examined NDE documentation for proper recording of film type, exposure, technique, penetrameter, and completion of the radiographic report. All radiographs reviewed appeared to indicate that the repair welds were acceptable.
The qualification records of the NDE personnel perfoming these radiographic examinations were reviewed and appeared to be satisfactory.
Mobile Inspection Service, Inc. (Mobile) has.been performing the nondestructive examinations including the above repair welds.
In reviewing the Mobile Quality Assurance Progran Manual, the inspector noted two discrepancies regarding Mobile Level I NDE Specialist requirements versus recommended practice SNT-TC-IA.
First, the manual states that the Level I must be able to interpret and evaluate examination results. This is not allowed in SNT-TC-1A. Second, the manual fails to state that the Level I shall perform his examination in accordance with written instructions as required by SNT-TC-IA. Mobile personnel
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stated that the company policy was to not permit Level I NDE Specialists to perform work on nuclear projects and since none appeared to have worked at SONGS-1 the inspector had no immediate concerns. However, the licensee indicated they would discuss this matter with Mobile in order to prevent any future problems.
No items of noncompliance or deviations were identified.
4.
Management Interview The inspector met with the licensee representatives denoted in paragraph I at the conclusion of the inspection on May 15, 1981.
i The inspection scope and findings were discussed.
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