IR 05000361/1982002
| ML20040H399 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/02/1982 |
| From: | Bishop T, Eckhardt J, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20040H396 | List: |
| References | |
| 50-361-82-02, 50-361-82-2, 50-362-82-01, 50-362-82-1, NUDOCS 8202180202 | |
| Download: ML20040H399 (5) | |
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U. S. NUCLEAR REGULATORY C0fNISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
50-361/82-02 R: port flo. 50-362/82-01 Docket flo. 50-361. 50-362 License No. CPPR-97, -9E Safeguards Group Licensee: Southern California Edison Company 2244 Walnut Grove Avenue
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Rosemead. California 91770 Facility Name: San Onofre Units 2 and 3 Inspection at: Construction Site. San Dieoo Countv. California Inspection conducted: Januarv 4-5. 1982 Inspectors W
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' Dr te Signed 1. Eckhardt, Reactor Inspector a
//La ss N
agner, Rea or Inspector
/ Q(te Signed
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I eild Zff!82 Approved by:
T. W. Bishop, Chiet Date Signed Reactor Projects Section 1 Sumary:
Inspection on January 4-5, 1982 (Report Nos. 50-361/82-02 and 50-362/82-01)
Areas Inspected _: Routine, unannounced inspection by regional based inspectors of construction activities involving licensee action on 50.55(e) items, and Unit 3 pipe welding. The inspection involved 22 onsite inspection hours by two NRC inspectors.
Results: No deviations or items of noncompliance were identified.
NYo$?oj@y0361 202 RV Fom 219 (2)
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DETAILS
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1.
Persons Contacted *
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Southern' California Edison' Company (SCE)~
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- D. B. Schone', Project QA Supervisors
- D. C. Stonecipher, Construction-QA" Supervisor V. A., Gow', QA~,Engi neer.. _,.,
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S. S. Dziewit, -QA' Engineer.
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- G. Vaslos, QA Engineer *
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- N. M. Ferris, QA-Engineer
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- J. J. Wambold,1 Construction Manager'
W. E. Kirby, QA Engineer -
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Bechtel Power Corporation (Bebhtel) '
- L. W. Hurst, Project QA Manager
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- J. W. Sheppard, Assistant Project QA Manager
- J. H. Mc Carty, Project QC Manager
- D. T. Lobree, Project Field Engineer F. Cox, Records Control Section Lead S. Wong, Welding QC Engineer R. Shah, Lead QA Engineer R. Koogle, Lead Field Welding Engineer
- Denotes those attending exit meeting.
2.
Licensee Action on 50.55(e) Items The following 10 CFR 50.55(e) items were examined to determine the adequacy of the licensee's corrective action:
a.
Preservice Examination ~ Indications Discovered in Unit 3 Reactor Pressure Vessel (RPV)
During ultrasonic preservice examination of the RPV, gix indicgtions g
were found in the longitudinal weld seams at 90, 210 and 330 neartgebottomoftheintermediateshellgirthweld. The indications at 330 showed some lateral width of less than 3/4 inch; whereas the other indications were all spot size in length. The inspector reviewed Work Notification No. 124-81 which is a traveler generated to remove the indications. Also reviewed were the calibration and weld scan data sheets, and the indication report sheet.
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-2-Prior to implementing of the repair procedure the surface area around the indications was prepared for a confirmatory UT examination.
Preparation involved grinding the surface from a rounded to a flat configuration in order to prevent geometrical reflections, and to provide a more accurate description of the reported indications.
This subsequent examination showed the indications to be acceptable or reportable in accordance with ASME Section XI requirements.
In accordance with the licensee's PSE program plan, these indications will be recorded in the PSE " Summary of Results" making these areas subject to future ISI examinations. The actions taken by the licensee are considered adequate. This item is closed.
b.
HFA Relays The licensee's corrective action specified in their final report of February 5, 1981 was verified. All specified Unit 2 HFA relays (226 total) have been replaced and tested. The inspector observed 48 relays installed in field panels. These included models 12HFA151A6F (12 vdc), 12HFA151A2F (125 vdc), 12HFA154E22H (125 vdc),
and 12HFA151A9H (125 vac).
In addition, the inspector reviewed the testing records for relays in breakers 52-280601 and 52-2B0605.
The tests included resistance and voltage of relay, resistance of circuit, and functional tests. The action taken by the licensee is considered satisfactory. This item is closed, c.
Magnatrol Flood Level' Alarm Switches The co'r_rective action specified in'the licensee's final report of December 2, 1981 was' verified. All specified level switch enclosures in Unit 2 have been replaced with~ watertight NEMA Type 6 enclosures.
Also, conduit fittings'ha~ve been replaced-with those suitable for submersible service.
The inspector examined seven of the newly installed enclosures. The inspector considers the action
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taken by the licensee to be' satisfactory.
This item is closed.
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3.
Reactor Coolant Pressure Boundary Piping (Unit 3)
a.
Observation of Welding Activities
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The inspector observed in-process welding being performed at two locations in the safety injection system. The welds were identified es S3-1204-ML-186 Weld A and 53-1204-ML-184 Weld A.
Both were 2-inch diameter schedule 80 stainless steel pipe to fitting groove welds.
Welding in both cases was beyond the root pass stage.
The inspector verified that the filler material, joint preparation and alignment, base metal, weld identification and weld procedure were in accordance with applicable procedures and ASME Section
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-3-III requirements.
In addition, the inspector observed QC temperature measurement of the welded area for verification of interpass temperature.
No items of noncompliance or deviations were identified.
b.
Welding Materia _1 Control The control, issue, return and storage of weld filler material in Rod Room No. 4 serving Unit 3 was observed by the inspector.
The holding ovens were calibrated and operating within the required temperature range and contained only one electrode classification.
All filler material located in holding ovens and in opened containers were correctly identified.
No items of noncompliance or deviations were identified.
c.
Review of Quality Records The inspector reviewed the records of two field piping welds within the main reactor coolant pressure boundary loop. These welds are identified as follows:
150 No. S3-1201-ML-005 Weld No. C and ISO No. S3-1201-ML-005 Weld No. D.
Both are 30 inch diameter, 3 inch thick pipe, clad with stainless steel.
The following records were selected for each weld and reviewed for compliance with applicable specifications and code requirements:
inspection, weld history, heat treatment, NDE, weld material control, welder qualification (weld and clad) and inspector qualification records.
The inspector found these records to be complete and satisfactory.
The inspector also reviewed four noncompliance reports (NCR's)
relative to the main reactor coolant pipe welding activities.
Identification and description of these NCRs are as follows:
NCR No.
Line No.
Weld No.
Description N-344 1201-ML-009 B
Linear indication in temporary
. attachment area N-358 -
1201-ML-010 B
Linear indication on 0.0. surface N-424
- 1201-ML-006 C
Excessive grinding into weld
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prep area
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N-540'
1201 ML-010'
B-Linear indications in weld metal
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The inspector is satisfied that the NCR's are complete, received adequate' disposition, and were properly reviewed by quality control, welding personnel, and the authorized nuclear inspector.
No items of noncompliance or' deviations were identified.
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4.
. Exit Meeting The inspectors met with licensee representatives (denoted in paragraph 1)
on January 5,.1982. The scope of the inspection and findings as detailed in this report were discussed.
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