IR 05000361/1979015

IE Insp Rept 50-361/79-15 & 50-362/79-15 on 790529-0601.No Noncompliance Noted.Major Areas Inspected:Const Activities Involving License Actions on Previous Insp Findings, Preservice Insp,Instrumentation & safety-related Pipe Welds

ML13309A730
Person / Time
Site:	San Onofre
Issue date:	06/25/1979
From:	Dodds R, Eckhardt J, Haist D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML13309A728	List: IR 05000361/1979015 ML13309A727
References
50-361-79-15, 50-362-79-15, NUDOCS 7908150251
Download: ML13309A730 (6)

Text

U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION V

50-361/79-15

"Report No. 50-362/79-15 Docket N, 50-362 License No. CPPR-97, CPPR-93 Safeguards Group Licensee:. Southern California Edison Company P. 0. Box 800, 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:

San Onofre Units 2 and 3 Inspection at:

Construction Site, San Diego County, California Inspection conducted:

May 29 -

June 1, 1979 Inspectors:

______________

H. Ec hardt, Reactor Inspector Dat6 Signe D.h aiReco Iseco/

i?~~~~1 5179_________

DP./as Reactor Inspector Dafe Signed 0. Ein, Reactor Inspector Date Signed Approved By:

__

V_

_

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R. T. Dodds, Chief Reactor EngineeringDte Signed ReactDat Signedrin Support Section Summary:

Inspection on May 29 -

June 1, 1979 (Report Nos. 50-361/79-15 and 50-362/79-15)

Areas Inspected: Routine unannounced inspection by regional based inspectors of construction activities involving licensee's actions on previous inspection findings, preservice inspection, instrumentation, containment post tensioning system, and safety related pipe welding. The inspection.involved 60 inspector-hours onsite by three NRC inspector Results: Of the five areas inspected, no items of noncompliance were identifie II RV Form 219(2)

79081506k

DETAILS 1. Individuals Contacted a. Southern California.Edison Company (SCE)

• D. E. Nunn, Manager, Quality Assurance

• P. A. Croy, Site QA/QC Supervisor

• R. R. Hart, Construction Superintendent

• P. R. King, QAEngineer J. Huey, QA Engineer S. Dziewit, QA Engineer F. Pimentel, QA Engineer D. Schone, Engineering Site Representative -

Civil L. Tipton, Nuclear Enginee J. J. Panteleo, QA Engineer b. Bechtel Power Corporation (Bechtel)

• C. A. Blum, Quality Control Manager

• W. D. Nichols, Assistant Project Field Engineer

• L. W. Hurst

• A. L. Erickson, Project Field QC Engineer N. Sanderfur, Field Engineer

• Denotes those attending exit intervie c. Zetec C. J..Denton - President E. J. Hako -

Level IIA Eddy Current Examiner W. D. Chevalier -

Level I Eddy Current Examiner d. VSL C. A. Grosvenor, Field Inspector J. V. Bond, Superintendent e. State of California J. Westphal, Authorized Nuclear Inspector 2. Licensee Action on Previous Inspection Findings (Closed) Follow-up item (50-361/79-11-02):. Inspector questioned the need for written inservice inspection supervisor qualification requirements based upon the responsibilities of the inservice inspection supervisor specified in Combustion Engineering Procedure No. 9976-NLE-056, Program Controls Procedure for Inservice Inspecto The licensee stated and confirmed with Combustion Engineering, that the Supervisor, Inservice Inspection acts as a supervisor and administrator and as such can determine the qualification of technicians responsible for the operability of remote examination equipment. Personnel operating remote handling equipment during data taking.operations must be certified to at least Level I as defined in ASNT-TC-l This item is close.

Bulletins and CircularsBulletin 79-02 - Pipe Support Base Plate Designs using Concrete Expansion Anchor Bolt The inspector interviewed licensee and Bechtel site personnel to determine the action being taken to respond to IEB 79-0 The licensee stated that Bechtel is preparing a response to IEB 79-02 that will show conservative calculational methods result in no base plate flexibility.. The licensee feels that the required safety factors can be shown and has specified the use of rock bolt anchors for piping over 2 1/2 inches. The licensee feels that adequate QC documentation is available to preclude a special testing program. The inspector reviewed the IE bulletin position with the licensee with the understanding that the licensee's formal response will be submitted within the allowed time perio. Preservice Inspection - Zetec Corporation a.. Review of Quality Assurance Implementing Procedures The inspector reviewed the Zetec Quality Assurance Manual for conformance to 10 CFR 50, Appendix B requirements. The inspector also reviewed the following Zetec procedures for conformance to ASME Section XI and Regulatory Guide 1.83 requirements:

(1) Procedure N Z-QA.-101, Personnel Qualification (2) Procedure No. Z-QA-201, Equipment Certification (3) Procedure No. Z-QA-301., Eddy Current Inspection of Steam Generator Tubes The eddy current examinations are being performed in accordance with the requirements of ASME Section XI, 1977 Edition through Summer, 1978 addenda which has not yet received formal endorsement from NRC Office of Standards Developmen Approval of this edition and addenda is expected shortly by reference in 10 CFR 50.55(a).

No items of noncompliance or deviations were identifie b. Observation of Work and Work Activities The inspector visually observed the calibration and eddy current examination of Unit #2 steam generator 088 (North) data which was being recorded on magnetic tape reel No. 3, Side 1. The inspector visually observed a typical data evaluation operation from magnetic tape reel No. 32, Side 1 representing eddy current examinations on steam generator no. 089 (South) quadrants 1 to 4 (hot leg to cold leg).

The inspector reviewed certifications for the Level I examiner, and the Level II A data evaluator. Also examined were calibration certifications and material certifications for the following equipment and calibration standards:

(1) Vector analyzer S/N 047 (2) Brush recorder No. 11483 S/N 11306 (3) Ocilloscope S/N B116019 (4) EM3300 S/N 422 (5) MIZ-7 S/N 385 (6) Tape recorder S/N 51 (7) Teac tape recorder S/N 49 (8) Calibration standard No. 49, Heat No. 6586 (9) Calibration standard No. 48, Heat No. 6586 It was found that examination were performed by certified examiners in accordance with the Zetec Quality Assurance Manual.and procedure No items of noncompliance or deviations were identifie.

Instrumentation (Review of Ex-Core Neutron Monitoring System and Protective Functions)

The Ex-core Nuetron Monitoring System and its protective functions were reviewed and compaired to the FSAR description. At the time of the inspection the detector thimbles and preamplifier cabinets had been installed along with the protective system cabinets. The cables from the preamplifiers to the protective cabinets (2L-91 & 3L-91) had not been pulled, and the detectors and their associated cables were not on sit The Combustion Engineering specification for location and installation of ex-core neutron detectors and preamplifiers (SCE #S023-941-16-0) and the specification for testing and calibration of ex-core neutron detectors (SCE #S023-941-3-0) were reviewed. Bechtel design drawings for the installation of ex-core neutron detectors were reviewed and compaired to the Combustion Engineering requirements. Several deviations from the Combustion Engineering requirements, caused by the use of steel construction aids or steel reactor vessel insulation canning, were noted but they had been reviewed and endorsed by Combustion Engineering in a letter to Bechte The actual installation of source range, safety and control channel.thimnbles was observed in Unit 3 and compaired to Bechtel design drawin Installation records for both Unit 2 and Unit 3 were examine No items of noncompliance or deviation were observe. Containment Post Tensioning System (Unit 3)

The inspector observed installation of Unit 3 containment horizontal tendon number 24 from buttress 3 to buttress 2. In addition, greasing records (sheathing filler material) for previously installed and tensioned vertical tendons75-167, 79-163,81-161, 93-149, and 91-151 were reviewe No deviations or items of noncompliance were identifie. Safety Related Pipe Installation and Welding The inspector visually examined a total of fifteen pipe welds in eight safety related systems to ascertain cbmpliance with appropriate ASME code requirements. The welding was in various stages of completion from prepping through completion and included both socket and butt weld Welds examined and their status was as follows:

System Drawing N Weld N Status Unit 2 VC S2-1208-ML-014 Third pass in progres DA S2-2420-ML-042 H (C)

Complete except for M DA S2-2420-ML-055 BB Complete except for M DA S2-2420-ML-051 SS Complet SI S2-1204-ML-002 ED Final pass in progres SI S2-1204-ML-033 B (R-1)

Grind out for repai FS S2-1219-ML-068 B

Final pass in progres CC S2-1203-ML-021 SS (C)

Tack welde FW S2-1305-ML-185 B

Complete except for R Unit 3 BM S3-1218-ML-068 SMH Complete except for P BM S3-1218-ML-068 SMM Complete except for P Both Units CH SA-1513-ML-087 SR(C)

Complet CH SA-1513-ML-087 SF Prepped onl CH SA-1513-ML-087 SJ(C)

Complet CH SA-1513-ML-087 SQ(C)

Complete In addition, quality records (Field Welding Check List and Filler Metal Withdrawal forms) associated with the above welds were reviewed. Also, welder qualification records for. welders performing the welds were reviewed and compared with the actual welding procedures use No deviations or items of noncompliance were identifie. Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

at the conclusion of the inspection on June 1, 1979 and summarized the scope and findings of the inspection as stated in this report. This exit interview was held in conjunction with the NRC Resident Inspector's regularly scheduled weekly meetin.