IR 05000413/1979020
| ML19257B808 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/29/1979 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19257B807 | List: |
| References | |
| 50-413-79-20, 50-414-79-20, NUDOCS 8001180401 | |
| Download: ML19257B808 (1) | |
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'o't, UNITED STATES
NUCLEAR REGULATORY COMMISSION
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9E REGION 11
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o 101 MARf ETTA ST., N.W., SUITE 3100 o
ATLAUTA, G EORGIA 30303
Hov 3 o n73 Report Nos. 50-413/79-20 and 50-414/79-20 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Catawba Nuclear Station, Unit I and 2 Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Catawba Site near Lake Wylie, South Carolina Inspector:
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// [24 f79 C. R. McFarland
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Date Signed
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. Bryant,' Section Chip, RCES Branch Date Signed SUMMARY Inspection on October 30 - November 2, 1979 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours onsite for the review of QA procedures, responses to one nonconforming item, one inspector followup item, and two IE Bulletins, and observing work related to the corrective action programs for these items.
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Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
1770 354 80 0118 0 4-C) l
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DETAILS 1.
Persons Contacted Licensee Employees D. L. Freeze, Project Engineer
- S. W. Dressler, Senior Construction Engineer
- L. R. Davison, Senior QC Engineer
- R. A. Morgan, Senior QA Engineer (QAE)
- J, C. Shropshire, QAE Mechanical, Welding
- H.
D. Mason, QAE Civil Electrical E. H. Lecroy, Night Superintendent T. D. Mills, Construction Engineer, Mechanical W. E. Rogers, Welding Superintendnet D. H. Llewellyn, Construction Engineer, Welding
- J. W. Ccx, Licensing and Projects, Operations R. O. Sharpe, Licensing, Steam Production Other licensee employees contacted included various construction craftsmen, technicians, and office personnel.
Other Organizations Hartford Steam Boiler Inspection and Insurance Company J. W. Kosko, Authorized Nuclear Inspector (ANI)
- C. F. Toegel, ANI
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on November 2, 1979, with those persons indicated in Paragraph 1 above. No new items of noncompliance or unresolved items were identified in the areas inspected.
3.
Licensee Action on Previous Inspection Findings (0 pen) Deficiency 413-414/79-12-02, Failure to follow quality assurance (QA) procedure P-1, " Receiving Inspection". Region II has reviewed and is currently evaluating the DPC response letters dated August 6, September 10 and October 1, 1979. DPC has revised Procedure P-1 to correct the deficiency.
4.
Unresolved Items There were no new unresolved items identified during this inspection.
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5.
Independent Inspection a.
Facility Inspection The inspector examined the repaired concrete on the inside of the Unit I containment dome and the crane wall for Unit 2, observed concrete work on the Unit 2 fuel pool, observed steel work on the erection of the steam generator supports in Unit 2, observed the warehouse storage yards, observed the rebar work for the reactor coolant pipe seismic restraints in Unit 1, observed the drying out operations for the Unit I diesel generators, and observed that the Standby Nuclear Service Water Pond is full.
The Unit 2 steam generators are scheduled to be on site in January, 1980. The Unit 2 reactor vessel is on site.
b.
Flow Direction of Valves The inspector reviewed construction procedure (CP) 150 " Flow Direction of Valves" which requires the warehouse to mark the flow direction of the valves that do not have the flow direction identified on the valves by the manufacturer before the valves leave the warehouse.
General and specific guidelines by the design mechanical engineers is provided to the site support group.
Construction QA procedure M-4, Visual inspection and NDE of Welds (ASME III) provides for documenting the fit up of the valve (including the flow direction) according to the isometric drawing of the system. The orientation of the feedwater check valves for the Unit I steam generators B and C was verified by the inspector.
6.
Inspector Followup Items (IFI)
a.
(Open) IFI 413-414/ 79-05-01, Nonconforming item (NCI) system. The inspector reviewed the NCI status log for items reported since the last inspection, NCI's 6431 through 6962, and discussed the current program with the senior QA engineer and the records clerk. The inspec-tor reviewed the trend analysis reports dated August 31, 1979, and December 15, 1978. The August 31, 1979 report presents data from a new data base system, hence no trend analysis report information is reported. There is no apparent correllation between the two reports nor any base of historical data that will be used for trend analysis data prior to 1979. The inspector also reviewed a corporate, level III, audit dated October 22, 1979, that noted as a related potential program weakness that there was no indication that the trend analysis of the NCI's was being used to reduce design changes or to improve the performance of vendors.
None of the trend analysis data, or other information made available, provides a basis for evaluating the status of pending NCI's, and the priority needed to complete the work. Lists of open NCI's are routinely 1770 556
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sent to the persons responsible for closing the NCI's, but no feedback is available to determine that generic problems are being eliminated.
This item remains open pending a further review of the need for more timely action on specific NCI's.
b.
(Closed) IFI 413-414/79-17-03, Failure to include nonessential variables in GTA welding procedure specifications. The inspector reviewed the revisions to welding procedure L-200 for gas tungsten arc (GTA) welding and other welding procedures related to automatic machine welds and noted that requirements for nonessential variables are currently documented.
7.
Licensee Identified Items (LII) 10 CFR 50.55(e) Items a.
(0 pen) 413-414/79-20-01 Modulating control valves. The inspector reviewed the DPC September 10, 1979, report of the significant deficiency and the interim report on the subject dated October 17, 1979. The inspector reviewed a design study of various pumps to add class IE solenoid valves to the instrument air lines immediately upstream of the affected valve operators and downstream of all control grade components to vent the operator on the appropriate signal to allow it
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to fail the valve in the safe position. Similar studies need to be made relative to the main stream and the auxiliary feedwater systems per the corrective action programs in the September 10, 1979 letter.
8.
IE Bulletins (IEB)
a.
(Closed) IEB 413-414/79-BU-15, Deep draf t pump deficiencies. The inspector reviewed the DPC response dated September 7, 1979, and the supporting documentation referenced in the IEB, and discussed the IEB with the construction engineer, mechanical.
The pumps will be utilized as nuclear service water pumps.
The pumps have been installed, but are not yet operational. A detailed maintenance and operation log will be maintained.
b.
(0 pen) IEB 413-414/79-BU-23, Potential failure of emergency diesel generator field exciter transformer. The DPC response to Region II dated November 1, 1979, provides for limiting the flow of circulatory currents. Modifications have beem made by DPC. The full load test is to be completed in January 1980.
9.
QA Procedure Review The inspector reviewed the recent revisions to the QA procedures noted below and discussed the implementation of the revised procedures with the 1770 3157
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QA engineers. None of the revisions cause the QA procedures at Catawba to be deficient.
Procedure No.
Revision Title H-8
Instrument Control L-80
Visual Workmanship
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Standards for Welds M-4
Visual Inspection of and NDE of Welds (ASME III)
M-8
Piping System Installation Inspection M-18
Inspection of Structural Steel Erection M-40
Electric Cable Installation and Inspection M-52
Concrete Expansion Anchor Installation Inspection M-71
Process Control and Inspection of Containment Systems and Liner Plate (ASME III)
P-1
Receiving Inspection R-2
Corrective Action S-4
Requirements for Applying the NA Stamp to Code Systems No items of noncompliance were identified.
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