IR 05000369/1979015
| ML19289F788 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/23/1979 |
| From: | Ang W, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19289F770 | List: |
| References | |
| 50-369-79-15, NUDOCS 7906160044 | |
| Download: ML19289F788 (4) | |
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UNITED STATES pm at%q#o,,
NUCLEAR REGULATORY COMMISSION
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Report Nos. 50-369/79-15 and 50-370/79-07 Licensee: Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242 Facility Name: McGuire Units 1 and 2 Docket Nos. 50-369 and 50-370 License Nos. CPPR-83 and CPPR-84 Inspection at McGuire site near Lake Norman, North Carolina Inspector: [ kbm
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Date Signed Approved by:
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3!21/79 J. C. Bryant, Bsetion phief, RC&ES Branch Date Signed SUMMARY Inspection on February 28 - March 2, 1979 Areas Inspected This routine unannounced inspection involved 19 inspector-hours onsite in the areas of main steam (MS) safety valves records (Unit 1); safety related components - work activities and quality records (Unit 2); weld rod control (Unit 2).
Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified in three areas; one apparent item of noncompliance was found in one area (infraction - assembly of MS safety valves without documented instructions paragraph 5).
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DETAILS 1.
Persons Contacted Licensee Employees J. C. Rogers, Project Manager
- G. W. Grier, Project Engineer
- E. B. Miller, Senior QA Engineer
- W. N. McCollough, Mechanical Maintenance - Steam Production M. Sample, Steam Production Technical Services Engineer
- G. B. Robinson, QA Engineer - Mechanical C. Ward. Jr., Mechanical QC Inspector J. Waters, Technical Support - Mechanical Other Organizations
- W. D. Tillman - Hartford Insurance Company 8' Attended Exit Interview 2.
Exit Interview The inspection scope and findings were summarized on March 2, 1979, with those persons indicated in Paragraph I above. The licensee acknowledged the inspector's findings.
3.
Licensee Action on Previous Inspection Findings (Closed) Infraction 50-370/78-18-01 - Failure to follow weld rod control procedures. An inspection of Unit 2 containment and auxiliary buildings was performed. Weld rod control appeared to be in accordance with DPC QAP H-3 Rev.9 and QAM Section H-9.
Su-veillance checklist M-10-1-79 on welding material control was reviewed and it also indicated that weld rod control was in accordance with the above noted procedures. The inspector has no further questions regarding this matter. This item is closed.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. A new unresolved item identified during this inspection is discussed in paragraph 7.
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Independent Inspection Effort Main Steam (MS) safety valves had been assembled on site by DPC construc-tion. During testing of the safety valves DPC Steam Production identified several problems with the MS safety valves. Two valve bonnets had been interchanged. ASME Code valve data reports identifies the respective serial number of bonnets and bodies for each valve. Frozen nozzle rings on three valves and binding internals on another valve were also identified by DPC Steam Production.
Form M-12A, valve disassembly and assembly inspection records for the main steam safety valves were reviewed. The M-12A records referenced the valve drawings but did not reference an assembly procedure.
The M-12A form and the valve drawings did not contain sufficient information to properly assemble and set the valves.
The engineer and QC inspector involved were interviewed to determine what procedure was used for the valve assembly. Although both could recall having an assembly procedure, neither one could identify the specific procedure nor could they locate a copy for review by the NRC inspector. The licensee could not find a copy of the procedure. The licensee could find no record of the procedure ever being in their document control system. The apparent lack of documented instructions for the assembly of the MS safety valves appears to be in noncompliance with 10 CFR 50 Appendix "B" Criterion V and DPC Topical Report " Duke 1-A" Section 17, paragraph 17.1.5 and shall be identified as an infraction, 50-369/79-15-01.
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Safety Related Components II - Observation of Work and Work Activities (Unit II)
The pressurizer was selected as a representative safety related component.
The pressurizer was inspected for compliance with NRC requirements and licensee PSAR commitments regarding storage, handling, storage protection, and installation. The applicable portions of the following procedures and drawings were used for the inspection:
Installation of Pressurizer a.
C. P. 199, Rev.2
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Shimming of Equipment with Grouted Base b.
C. P. 42, Rev.6
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Bolt and Stud Torque Procedure c.
C. P. 61, Rev.6
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Mechanical Equipment Installation d.
QAP H-9, Rev.10
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Inspection Pressurizer Lower Support, Plan e.
DPC Drawing MC 1070-6
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General Arrangement - Containment and f.
DPC Drawing MC 1041-14
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Reactor Building - EL738+3 2228 060
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DPC Drawing MC 1041-16
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Reactor Building - EL 778+10 No items of noncompliance or deviations were noted.
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Safety Related Components II - Review of Quality Records - (Unit II)
Pertinent quality related work and inspection records relative to the pressurizer were reviewed to ascertain conformance with applicable requirements for storage inspection, installation inspection, material and fabrication certifications, test records, and nonconformance reports.
The following pressurizer records were reviewed:
Receiving Inspectic.n Information Sheet, PI-A a.
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Westinghouse Quality Release Supplement, QR-25261 c.
Westinghouse Manufacturer's Data Report d.
DPC Form M9B - Equipment Release Document for the Installation of Rotating and Non-Rotating Equipment DPC Form M10A - Process Control and Inspection of Torque to Bolts e.
and Studs f.
DPC Form P3A - Equipment Special Storage and Mainteance Inspection -
Se::ial Number M-122,Rev. I and Original g.
- !cnconforming Item Report 7072 The two most recent QA surveillances associated with safety related components (Dated January 31, 1979 and December 27, 1978) were reviewed to ascertain that they were of the required scope and frequency, that deficiencies identified were corrected, and that QA personnel performing the surveillance were qualified for the work performed. Qualifications for the two QA personnel and the reviewing QA supervisor were not available on-site for inspection. Pending the availability of the qualification recorde and subsequent NRC review, this item shall be identified as Unresolved Item 50-370/79-7-1.
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