IR 05000413/1981001
| ML20008E709 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/06/1981 |
| From: | Bryant J, Matt Thomas, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20008E707 | List: |
| References | |
| 50-413-81-01, 50-413-81-1, 50-414-81-01, 50-414-81-1, NUDOCS 8103090503 | |
| Download: ML20008E709 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
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E REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 p
ATLANTA, GEORGIA 30303
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Report Nos. 50-413/81-01 and 50-414/81-01 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Catawba Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Ca+ wba si a near Rock Hill, South Carolina Inspectors:
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M. Th'omas
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Approved b -
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J. C Bryant, ection Chi /f, RCES Branch Date S'igned SUMMARY Inspection on January 12-16, 1981 Areas Inspected This routine, unannounced inspection involved 62 inspector-hours on site in the areas of reactor coolant pressure boundary piping - csbservation of welding and non-welding activities (Unit 2); safety related piping observation of welding (Unit 2); safety related pipe support and restraint systems - review of work procedures (Units 1 and 2); and followup of IE Bulletin 80-21 (Units 1 and 2).
Results d
Of the four areas inspected, no violations or deviations were identified.
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DETAILS
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Persons Contacted
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Licensee Employees
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- D. G. Beam, Project Manager
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- D. L. Freeze, Project Engineer
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- S. W. Dressler, Senior Construction Engineer
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L. R. Barnes, Hangar Manager -
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R. A. Morgan, Senior QA Engineer L
L. R. Davison, Senior QC Engineer
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- J. C. Shropshire, QA Engineer
- H. D. Mason, QA Engineer l
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"M. R. Hemphill, QA Engineer
H. E. Edwards, Design Engineer
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R. G. Rouse, QA Technician - Welding
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Other licensee employees contacted included 10 construction craftsmen, two
inspectors, and three office personnel.
Other Organizations Hartford Steam Boiler Inspection and Insurance Company J. W. Kosko, Authorized Nv: lear Inspector
- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on January 16, 1981 with those persons indicated in Paragraph 1 above.
The unresolved items
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described in paragraphs 9 and 10 were discussed in detail.
During this
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Freeze was transferring to a new position off-site and his position of Catawba Project l
Engineer is being eliminated.
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Licensee Action on Previous Inspection Findings
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Not inspected.
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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.
New unresolved items identified during this inspection are discussed in paragraphs 9 and 10.
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Independent Inspection Effort (Units 1 and 2)
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The inspectors performed an inspection of the reactor buildings, auxiliary building, outside storage areas, weld material issue station, and the pipe fab shop for conformance to code and procedure requirements in the areas of housekeeping, safety related pipe storage, material hancling and control, nondestructive examinations (NDE), and verification of inspector qualifi-cation.
Liquid penetrant (PT) tests were observed for welds 2NI119-2, 2NI119-3, 2NI119-8, and 2NI121-6. The inspector observed handling of safety related pipe for welds 2KF97-14, 2KF97-15, and 2KF97-16.
No violations or deviations were identified.
6.
IE Bulletin No. 80-21 - Valve Yokes Supplied by Malcolm Foundry Company, Inc. (Units 1 and 2)
Duke submitted the subject bulletin response for Catawba on January 5,1981.
This response indicates that no safety related valves planned to be used for the Catawba site contain parts supplied by Malcolm Foundry Company, Inc.
Duke informed the inspector that their determination was made by contacting all vendors supplying safety related valves for Catawba.
This action is considered satistactory and this bulletin is closed.
No violations or deviations were identified.
7.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities (Unit 2)
The applicable code for installation of reactor coolant pressure boundary and other safety related piping is ASME Section III (74S75). The inspector observed in process welds and reviewed records for conformance to procedure requirements in the areas of documentation of pertinent information and QC signoffs via a weld traveler, availability of pertinent instructions, weld identification / location, use of qualified welding procedures, provisions for weld repair provided, certification of filler material, control of welding parameters, verification of welder qualification, use of specified shielding and purge gas, control of preheat and interpass temperature, condition of weld and base metal surfaces, and verification of fitup.
The following welds were observed:
Weld No.
Size Class Stage of Welding Observed d
2NC9-1 29"
Intermediate 2ND67-2 12"
Fitup 2ND67-8 12"
Fitup 2NI55-2 6"
Intermediate No violations or deviations were iden'tified.
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Safety Related 'iping (Welding) - Observation of Work and Work Activities (Unit 2)
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The applicable code is identified in paragraph 7.
The inspector observed in process welds and reviewed records for conformance to code and procedure requirements in the areas of documentation of pertinent information and QC signoffs via a weld traveler, availability of pertinent instructions, weld identification / location, use of appropriate qualified welding proceduras, provisions for weld repair provided, certification of filler material, control of welding parameters, verification of welder qualification, use of specified shielding and purge gas as applicable, control of preheat and interpass temperature, condition of weld and base metal surfaces, and verification of fitup. The following welds were observed:
Weld No.
Size Class Stage of Welding Observed 2KF53-1 10"
Intermediate
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2KF53-2 10"
Intermediate 2KF5a-10 10"
Intermediate 2KF53-11 10"
Intermediate 2NB57-5 6"
Intermediate 2ND28-15 8"
Fitup No violations or deviations were identified.
9.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities a.
The inspector observed non welding work activities for reactor coolant pressure boundary (RCPB) piping. The applicable code is identified in paragraph 7.
The inspector observed handling of piping for fitup of weld no. 2ND67-2 and weld no. 2ND67-8 for conformance to applicable procedures and instructions.
b.
On January 12, 1981, during observation of fitup of Class A Weld no.
2ND67-8 in the fabrication shop the inspectors noted that handling had caused gouges in the pipe outer surface. Craftsman indicated that the gouges would "probably be cleaned up" when the welds were ground.
It appears that site procedures are no+ scovided to control this type of grinding in the fabrication shop to assure proper inspections are performed. Until the extent and severity of this problem is determined
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this will be Unresolved Item 50-413, 414/81-01-01 Control of Grinding
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on Piping Base Material.
No violations or deviations were identified.
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Safety Related Pipe Support and Restraint Systems (Units 1 and 2)
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The applicable code for safety related support and restraint install-ation is the ASME Boiler and Pressure Vessel Code,Section III,
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Subsection NF, 1974 Edition plus addenda through summer 1975.
The inspector reviewed procedures to determine whether they were tech-nically adequate, approved by authorized personnel and meet applicable code and NRC requirements. Areas considered in the review included
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controls to assure type and classification of pipe support and
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restraint systems comply with approved. drawings and specifications; control of ' cutting and forming operations; measures to assure that
bolts, nuts and washers are tight, secured as required and of the
proper type and size.
Inspection of dynamic supports for freeze-up; control cf installation tolerances; control of support / restraint
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modifications; materials control; installation inspections; control and inspection of welding and in process documentation control.
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following procedures were reviewed:
Specification No. CN5-1206.00-04-0003, Rev. 6 - Procedure Requirements for Fabrication and Erection of-Hangers, Supports and Seismic Supports.
i Construction QA Procedure L-80, Rev. 7 - Visual Workmanship Stand,rds for welds.
Construction QA Procedure M-15, Rev. 11 - Installed Pipe Support Inspection Construction QA Procedure M-51, Rev. 3 - Component Supports.
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Support Inspection Instruction CN-1, Rev. 5 - Erection Inspection l
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Support Inspection Instruction CN-2, Rev.
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Supplementary Instructions for Shock Suppressors, Sway Struts, and Variable and Constant Support Spring Hangers.
Support Inspection Instruction CN-3, Rev. 0 - Cold Load Setting Inspection.
Support Inspection Instruction CN-4, Rev. 2 - Final Walk Thru.
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l Support Inspection Instruction CN-5, Rev. 1 - Reactor Vessel Head
Lifting Rig and CRDM Seismic Support Platform.
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i Support Inspection Instruction CN-6, Rev.
0 - Reactor Building Supports / Restraints by Civil Design.
Construction Procedure (CP) - 309, Rev. 13 - Marking Requirements for
Hangar Material.
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l CP-313, Rev. 9 - Administrative Control of Hangar Packages.
i CP-353, Rev.
8 - Adjustment, Installation and Modification of
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Pre-Engineered Hanger Components.
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CP-385, Rev. 6 - Support / Restraint Erection Tolerances.
CP-432, Rev. 5 - Welding of Hangers, Supports and Seismic Controls.
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CP-475, Rev.
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Administrative Control of Packages for Supports / Restraints to be Handled by the Civil Tech Support Group.
CP-488, Rev. 0 - Hanger Documentation Control of Design Engineering Sketches.
b.
On January 15, 1981 it appeared that procedure controls were not specified for thermal cutting and material forming of support materials requiring impact testing. These controls are required by ASME,Section III, subsection NF, paragraphs NF-4211 and NF-4212. The extent /effect of this problem was not determined during this inspection and therefore, until further inspection can be performed, this is Unresolved Item 50-413, 414/81-01-02 - Control of Cutting and Forming for NF Supports and Restraints.
c.
On January 15, 1981 it appeared that butt weld reinforcement require-ments of ASME,Section III, Subsection NF, paragraph NF-4426 were not specified in the applicable Duke visual inspection procedure ( L-80, Rev. 7).
The extent /effect of this problem was not determined during this inspection and therefore this is Unresolved Item 50-413, 414/81-01-03 - Specification of Weld Reinforcement Requirements for NF Supports and Restraints.
No violations or deviations were identified.
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