IR 05000491/1979012
| ML19275A497 | |
| Person / Time | |
|---|---|
| Site: | Cherokee  |
| Issue date: | 07/31/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19275A482 | List: |
| References | |
| 50-491-79-12, 50-492-79-12, 50-493-79-12, NUDOCS 7910040551 | |
| Download: ML19275A497 (4) | |
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NUCLEAR REGULATORY COMMISSION
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E REGION 11
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101 M ARIETT A sT., N.W., SUITE 3100 ATLANTA, G EoRGI A 30303
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Report Nos. 50-491/79-12, 50-492/79-12, and 50-493/79-12 Licensee:
Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Cherokee rocket Nos. 50-491, 50-492, and 50-493 License Nos. CPPR-167, CPPR-168, and CPPR-169 Inspection at C i
ar Gaffney, South Carolina d
Inspector:
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W K)4 o"ge Dattr'Sigfied
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Approved by:
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A. R. Herdt, Section Chief, RCES Branch Da'te Signed SUMMARY Inspection on July 10-13, 1979 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours onsite in the areas of steel structures and supporta: reactor coolant loop piping and other safety related pipe Welding Procedure Specifications and Quality Assurance Procedures; welding material control; radiographic examination and, safety related pipe welding - observation of work.
Results Of the five areas inspected, no apparent items of noncompliance or deviativns were identified in four areas; one apparent item of noncompliance was found in one area; Weld Procedure Specifications and Quality Assurance Procedures -
Deficiency: Failure to include nonessential variables in GTA Welding Procedure Specifications (Paragraph 7).
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DETAILS 1.
Persons Contacted Licensee Employees C. B. Aycock, Project Eneineer
- T. Reynolds, Technical F.pervisor, Welding
- A. R. Hollins, Senior QC Engineer
- J. W. Willis, Senior QA Engineer Other licensee employees contacted included seven construction craftsmen, five technicianc, and three office personnel.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on July 13, 1979 with those persons indicated in Faragraph 1 above. The inspector identified the areas inspected and discussed in detail the item of ncncompliance. No dissenting comments were received from the licensee.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort The inspector conducted a general inspection of the containment, turbine and auxiliary buildings of Unit 1, piping and metal fabricatica shops, Concrete and NDE Labs, Electrode Issue Station No. 1, Warehouse No. I and The Weld Test Shop to observe construction progress and construction activities such as welding, cv. ting, grinding, radiography, concrete placement and testing, materi 1 inadling and control, t.ousekeeping and storage.
a.
Radiographic Examination The inspector observed radiography of a containment butt weld. The applicable code for containment fabrication, and nondestructive testing is the ASFIE B and PV Code, The 1974 edition including addenda through Summer 1976 Section III Article NE-5000, Subarticle NE-5300 and Section V, as implemented by Duke Power Company (DPC) Specification P81S-1144.10-00-0001 dated November 6,1978 with Revision 1 dated March 12, 1979.
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The inspector witnessed radiographic examination in progress for, and reviewed the radiographs of containment butt weld identified as 1BD01B to determine whether material identified was as specified, surface condition was within specified limits, thickness was within limits, and to determine type of source and equipment, film type and identifica-tion, source to film distance, blocking or masking technique used, film processing requirements, quality of radiographs, film density, use of densitometers, system of radiographic identification, use of location markers, methods of reducing and testing for back-scatter, selection and use of penetrameters, and the epecified NDE being performed with qualified personnel.
b.
Safety Related Piping (Welding) - Observation of Work and Work Activities The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at vr ious states of weld comple-tion. The applicable Code for Undergrc.nd Nuclear Service Water Pipe welding is the ASME B and PV Code Section III the 1974 edition with addenda through Winter 1976, and Section IX the latest at the time of implemented by DPC Specification P81S-1206.00-2.3 qualification, as dated August 30, 1977 with revision 3 dated September 22, 1978.
(1) The inspector examined a weld joint where the root pass only had been completed to determine: weld / welder ider.tification, qualified welder / weld procedure, physical appearance of.he weld and evidence of QC verification. The following weld joint was examined:
Joint Number Size System 2RN11-2 36" x 0.406" Underground Nuclear Service Water (2) The inspector examined a weld joint of pipe to pipe / fitting (PPF)
where welding was beyond the re pass to determine: weld / welder identification, qualified wel(.. er i procedure, periodic checks of welding variables, use of lied weld material, proper interpass temperature and whe ricable pre-heat and post-weld heat treatment and physical a,je.cance of the weld (e.g.
starts, stop undercut and surface imperfections). The following joint was examined:
Joint !! umber Size System 3RN13-2 36" x 0.406" Underground Nuclear Service Water (3) The inspector observed activities at weld material issue stations to determine adequacy of; weld material storage / segregation, oven temperatures, issue records and return of unused weld material.
Also observed work areas for uncontrolled weld material.
Within the areas examined, there were no items of noncompliance or deviations identified.
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Steel Structures and Supports - Welding Procedure Specifications and Quality Assurance Procedures Requirements, control, preparation, qualification, approval / certification distribution and revision of welding procedure specifications (WPS) are established through (DPC) " Quality Assurance Manual for ASME Code Work" Section L "Special Processess" and DPC " Construction Department Quality Assurance Program" Chapters L-100 " Welding Program" and G-1 " Document Control".
Section III of the ASME Code 1974 edition, including addenda through Summer 1976, incorporating Code Cases 1714 and 1777 and Section IX the latest in effect at the time of qualification, control the qualification of WPS applicable to steel structures and supports for the containment.
The following randomly selected shielded metal are welding (SMAW) WPS was selected for review:
WPS Process 304 Rev. 10 SMAW The above WPS and its supporting Procedure Qualification Record (PQR) were reviewed to ascertain whether essential, supplementary and/or nonessential variables including thermal treatment were concistent with code requirements; whether the WPS was properly qualified and its supporting PQRs was accurate and retrievable; whether all required mechanical tests had been performed and the results met the minimum requirements; whether the PQRs had been reviewed and certified by appropriate personnel and, whether any revisions and/or changes to nonessential variables were noted.
Within the areas examined no items of noncompliance or deviations were identified.
Welding 7.
Reactor Coolant Loop Piping and Other Safety Related Piping
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Procedure Specifications and Quality Assurance Procedures The control requiremec'- are the same as paragraph 6 above.Section III of the ASME Code 1977 s ition, including addenda through Summer 1977 and Section IX, the latest in effect at the time of qualification control the qualification of WPS applicable to reactor coolant loop piping and other safety related piping.
Six randomly selected WPSs involving GTAW, SMAW and GMAW, were selected for review.
These were identified as follows:
WPS Process 202 Rev. 10 GTAW 232 Rev. 2 GTAW l098 253
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303 Rev. 9 SMAW 350 Rev. 12 SMAW 507 Rev. 2 GMAW 558 Rev. 1 GMAW Within the areas examined the inspector noted on July 11, 1979 that for the GTAW WPS and their supporting PQR, the nonessential variables " width, frequency, or dwell time of oscillation", and " peening" QW-410.7 and 410.26 respectively of the ASME Code Section IX were not addressed as required by Paragraph QW-201.1 of ASME Code Section IX. The licensee's representative agreed to take appropriate corrective action in this matter.
Failure to include all pertinent information in the welding procedure specification is in noncompliance with 10 CFR 50 Appendix B Criterion IX. This is a deficiency and was assigned item number 491-492-493/79-12-01.
8.
Steel Structures and Supports, Reactor Coolant Loop Piping, and Other Safety-Related Piping-Welding Material Control The applicable code is as specified in paragraphs 6 and 7 above.
Requirements control, purchase, receiving, storing, distribution and bandling, identification, environmental control including baking temperatures, and limitation of moisture pick-up for welding materials are established through and controlled by the following: DPC " Quality Assurance Manual for ASME Code Work" Sections E-3 " Field Procurement of Materials and Construction Services," and E-4 " Purchase of Code Items" and DPC " Construction Department Quality Assurance Program", Procedures P-1 " Receiving Inspection," P-3 Mechanical Equipment Storage Maintenance Inspection," and H-3 " Identification and Control of Welding Material" The inspector observed activities at several work areas where welding was in progress and in Electrode Issue Station No. I to determine whether identification was acceptable and whether distributior; maintenance, storage, and moisture control were in accordance with applicable procedures Within the areas inspected, no items of noncompliance or deviations were identified.
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