IR 05000413/1981022
| ML20039A027 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/26/1981 |
| From: | Bryant J, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20038D148 | List: |
| References | |
| 50-413-81-22, 50-414-81-22, NUDOCS 8112160154 | |
| Download: ML20039A027 (7) | |
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NUCLEAR REGULATORY COMMISSION o
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REGION 11
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101 MARIETTA ST., N.W, SUITE 3100 ATLANTA, GEORGIA 3o3o3 g ***** s Report Nos. 50-413/81-22 and 50-414/81-22 Licensee: Duke Power Company Facility Name: Catawba Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector:
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rfa"nt, Sectf5nf;p'i5f, Division of D&te Signed e dent and Reactor Project Inspection SUMMARY Inspection on August 26 - September 25, 1981 Areas Inspected This routine, announced inspection involved 80 resident inspector-hours on site in the areas of safety-related pipe support and restraint systems (Unit 1);
reactor coolant pressure boundary piping - observation of welding and non-welding activities (Units 1 and 2); safety-related piping (welding) - observation of work and work activities (Units 1 and 2); and followup of licensee (50.55(e)) and NRC identified items (Units 1 and 2).
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Results Of the 4 areas inspected, no-violations or deviations were identified in 2 areas; 3 violations were found in 2 areas (failure to adequately control power cable spacing paragraph 3.d.; failure to follow ASME code inspection requirements for repair welding paragraph 5; failure to follow procedures for control of surface applied materials paragraph 9.b.).
8112160154 811200 PDR ADOCK 05000413 G
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DETAILS 1.
Persons Contacted
- Licensee Employees
- J. C. Rogers, Project !bnager J. R. Wells, Corporate QA thnager
- S. W. Dressler, Senior Construction Engineer
- R. A. Morgan, Project QA Engineer
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J. E. Cavender, Level III Inspector
- J. C. Shropshire, QA Engineer Supervisor
- H. D. Mason, QA Engineer Supervisor M. R. Hemphill, QA Engineer Supervisor H. L. Atkins, QA Engineer J. W. Glenn, QA Engineer D. E. Gadd, Welding Engineer D. H. Llewellyn, Welding Engineer
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Other licensee employees contacted included construction craftsmen, technicians, inspectors, and office personnel.
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Other Organizations
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Hartford Steam Boiler Inspection and Insurance Company J. W. Kosko, Authorized Nuclear Inspector C. F. Toegel, Authorized Nuclear Inspector i
B. Wood, Authorized Nuclear Inspector
- Attended exit interview 2.
Exit Interview L
The inspection. scope and findings were summarized on September 28, 1981 with
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those persons -indicated in paragraph 1 above. The violations and unresolved I
items described in paragraphs 3.d, 5 and 9.b. were discussed in detail.
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3.
Licensee Action on Previous Inspection Findings
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a.
(Closed)
Deficiency (413, 414/80-16-01):
Failure to correctly translate codes and standards into specifications,- drawings, procedures
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or instructions. This. item concerned designation of welding symbols for electrical cable tray supports.
Licensee corrective actions have included correction of the affected drawings and training of appro-priate personnel to prevent recurrence. The inspector verified these
actions.and considers them to be satisfactory.
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b.
(C'osed) Violation (413, 414/81-02-03):
Inadequate procedures. This t
item concerned. inadequate installation of pressurizer relief tanks and containment spray heat exchanger supports. Licensee actions concerning this item have been correction of the affected components, training of appropriate personnel, and establishment of a hold point in QA Procedure M-9 requiring structural inspection prior to equipment setting. The inspector verified these actions and considers them to be sa tisfactory.
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c.
(Closed) Violation (413, 414/81-06-04):
Failure to follow procedure for installation of hangers and to provide appropriate qualitative criteria on a hanger drawing.
Licensee actions concerning this item have been to provide improved instructions in the appropriate procedure (CP-385), implementation of corrective action for the affected hangers, correction of the affected hanger drawing, and training of appropriate personnel. The inspector. verified these actions and considers them to be satisfactory.
d.
(Closed) Unresolved Item (413, 414/81-14-02):
Control of electrical power cable spacing. This item concerned the fact that the specifi-cation which addressed power cable spacing (Specification No.1390.-
01-00-0022) was ambiguous.
The licensee evaluated this requirement and determined that power cable contact should be limited to approximately two feet. The ambiguity of the specification resulted in the NRC inspector and site personnel identifying numerous safety-related power cables where length of contact is more than two feet.
This is in violation of 10 CFR 50, Appendix B, Criterion V which requires that instructions include appropriate quantitative acceptance criteria for determining that important activities have been satisfactorily accom-plished.
This unresolved item has been changed to a violation.
(Violation 50-413,414/81-22-01:
Failure to adequately control power
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cable spacing.)
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(Closed) Violation (414/81-17-01): Failure to conform to drawing requirements for rebar spacing.
Licensee actions concerning this item have included evaluation of the spacing problems and training of the appropriate personnel.
The inspector verified these actions and
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considers them to be adequate.
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(0 pen) Violation (413/81-02-02, 414/81-02-04): Apparent generic items or trends not recognized nor forwarded to management.
This item concerned inadequate documentation and evaluation of problems identified in nonconforming item reports (NCI's).
Details of the inspector's review are discussed in paragraph 5.
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3-4.
Unresolved Items
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Unresolved items are matters about.which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 5.
5.
Nonconforming Item Reports Review The inspector reviewed numerous NCI's to determine if adequate documentation and evaluation had been accomplished. This review included NCI 11385 iden-tified in NRC Report No. 50-413,414/81-11. Action concerning this NCI is adequate.
During this review several items of concern were identified and are described below.
On September 7,1981 the inspector noted that several NCI's had been written concerning missed surface inspections of embedded pipe, it appears that the licensee program requiring surface inspections may have been inadequate, resulting in missed inspections.
Pending further evaluation, this item is
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unresolved.
(Unresolved-Item 50-413, 414/81-22-02:
Control of surface inspections of embedded pipe).
On September 18, 1981, the inspector noted that instructions for weld repair of base metal adjacent to class B weld No. 1FW-22-6 delineated on NCI No.
12454 did not require :iquid-penetrant (PT) inspection of the weld repair.
The applicable code (ASi1E B&PV Code,Section III, paragraph NC-2539.4)
requires PT inspection of base metal weld repairs.
The licensee did specify radiographic inspection of the weld repair and this appears to be an isolated case. This is in violation of-10 CFR 50, Appendix B Criterion V which requires that instructions include appropriate quali-tative acceptance criteria for determining that important activities have been satisfactorily accomplished.
(Violation 50-413,414/81-22-03:
Failure-to follow ASME Code requirements for repair welding).
On September 21, 1981, the inspector noted that a rejectable lack of fusion weld defect in weld No.1 NV-177-8 identified on NCI No.12682. This appears to have been accepted by the licensee welding technical support.
. personnel.
Pending further evaluation, this item is unresolved.
(Unre-solved Item 50-413/81-22-04:
Evaluation of lack of fusion weld defect identified on NCI No. 12682).
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No violations or deviations, except as identified in the paragraph above, were identified.
6.
Independent Inspection Effort (Units 1 and 2)
a.
The inspector conducted general-inspections of site work and work activities and observed equipment protection / storage and housekeeping in the auxiliary building, containment buildings, pipe fabrication shop and storage areas. During this inspection the inspector observed
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welding in progress for class NF weld No. 2WE6-5 for conformance to code and procedure requirements.
b.
The inspector observed grouting of hanger number 1-A-RN 3433, 9156, 9157, 9158, and 9163 for conformance to procedure QAPHS, Rev. 8 requirements.
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The inspector observed installation in progress of Unit 1 control rod guide tube support pins to detennine if work was adequately controlled in the areas of material control, welding control and QA inspections.
No violations or deviations were identified.
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Licensee Identified Items - 50.55(e) (Units 1 and 2)
a.
(Closed) (413,414/81-17-08; CDR 81-10) - Piping restraint not installed in accordance with design documents. This item concerned acceptance and installation of a hanger in a direction other than that specified on design documents. The licensee provided a final response on June 15, 1981.
Licensee actions included training of appropriate personnel, review of similar installations to verify that similar problems do not exist, and implementation of program improvements to require additional review of hanger orientation. The inspector verified these actions and considers them to be adequate.
b.
(Closed) (CDR 81-19) - Improper source of control air supplying the diesel generator engine control panel.
The final report was submitted by the licensee on September 11, 1981. Licensee action concerning this item has been to redesign the diesel generator control air line. The inspector verified this action and considers the action to be adequate.
No violations or deviations were identified.
8.
Safety-Related Pipe Support and Restraint Systems (Unit 1)
The applicable code for safety-related support and restraint installation is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF,1974 Edition plus addenda through summer 1975. The inspector observed instal-lation in progress of hanger Nos.1-A-KC-3604,1-A-WL-3219,1-A-WG-8564 and 1-A-NV-8240 for conformance to code and procedure requirements in the areas of use of specified materials, location, documentation, welding and ' anchor bolt installation.
No violations or deviations were identified.
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Safety-Related Piping (Welding) - Observation of Work and Work Activities Units 1 and 2)
a.
The applicable code for installation of safety-related piping is the ASME Boiler and Pressure Vessel Code,Section III,1974 Edition plus
~ ddenda through summer 1975.
The inspector observed in process welds a
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at various stages of completion and reviewed records for conformance to code and procedure requirements in the areas of documentation of pertinent information and QC signoffs via a weld travler, availability of pertinent instructions, use of appropriate qualified welding procedure, provisions for weld repair provided, certification of filler material, control of welding parameters, use of specified shielding and purge gas, condition of welding equipment, provisions for voltage and amperage checks, verification of proper fitup, control of preheat and interpass temperature, condition of weld and base metal surfaces, and verification that appropriate inspections were being performed.
The following welds were observed.
Weld No.
Size (In. Dia.)
Stage of Welding Observed
- 2TE2-1
Fitup 2TE2-2
Fitup 2ND12-13
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Fitup l
Fitup
- First number denotes unit number.
b.
On September 17, 1981, the inspector observed Shufords Shurtape General Purpose Crepe Paper tape applied to stainless steel piping associated
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with weld Nos. 18B52-13 and 1BB52-14. The licensee procedure which controls materials applied to stainless steel surfaces (CP-479, Rev. 4)
does not allow use of the above tape on stainless steel. This is in violation of 10 CFR 50, Appendix B, Criterion V which requires that activities affecting quality be accomplished in accordance with established procedures. This appears to be an isolated case. This is (Violation 50-413/81-22-05:
Failure to follow procedures for control of surface applied materials).
No violations or deviations, except as identified in paragraph 9.b.,
were identified.
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Reactor Coolant pressure Boundary Piping (Welding) - Observations of Work and Work Activities (Unit 2)
The applicable code is delineated in paragraph 9.
The inspector observed weld No. 2NC43-11 at the fitup s' N for conformance to code and procedure requirements in the areas deli's J % paragraph 9.
No violations or deviatic n <. e tantified.
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Reactor Coolant Pressure Buondary Piping - Observation of Work and Work Activities (Units 'I and 2)
The applicable code is delineated in paragraph 9.
The inspector observed
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handling and preparation of piping for fabrication of weld Nos.1NC-190-1
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Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Units 1 and 2)
The applicable code is delineated in paragraph 9.
The inspector observed handling and preparation of piping for fabrication of weld Nos. INC-190-1 and 2N1-55-10 for conformance to procedure and code requirements in the areas of control of tools for grinding, brushing and filing; use of appro-priate handling and rigging equipment; control of cleanliness and control of cold spring whre applicable.
No violations or deviations were identified.