IR 05000413/1981017
| ML20010J113 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/13/1981 |
| From: | Bryant J, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010J074 | List: |
| References | |
| 50-413-81-17, 50-414-81-17, NUDOCS 8109290603 | |
| Download: ML20010J113 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMlbSION o
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E REGION 11 Q
101 MARIETTA ST N.W., SUITE 3100 e
ATLANTA,r loRGIA 30303
% ***o Report Nos. 50-413/81-17 and 50-414/81-17 Licensee: Duke Power Company P. O. Box 33189 Charlotte, NC 28242 Facility Name: Catawba Docket No. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Cat wba site near Rock Hill, South Carolina 4e m WsL r P l T ff'
inspector:
PfiVa oorV/
jf Date Signed
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Approve [ :
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4wh JF//J/(f J.ftBryantffectionChief,RRPIDivision Date Signed
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SUMARY Inspection on June 26 - July 25,1981 Areas Inspected This routine, unannounced inspection involved 120 inspector-hours on site in the areas of safety related pipe support and restraint systems (Unit 1); electrical cables, observation of work and work activities; containment penetrations-observation of work and work activities (Unit 1); safety related piping (welding) - observati n of work and work activities (Units 1 and 2) and followup of NRC identified items (Units 1 and 2).
Results Of the five areas inspected, no violations or deviations were identified in four areas; one violation was found in one area (Failure to conform to drawing requirements for rebar spacing - paragraph 3.c).
8109290603 810924 PDR ADOCK 05000413 G
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a REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. C. Rogers, Froject fianager
- J. R. Wells, Corporate QA flanager
- S. K. Blakely, Jr., Chief Engineer flechanical Nuclear Division R. B. Priory, Principle Engineer - Project Management Group S. W. Dressler, Senior Construction Engineer W. O. Henry, QA Manager Technical Services
- R. A. Morgan, Project QA Engineer
- R. H. Robertson, Construction Engineer Civil / Welding T. D. Mills, Construction Engineer Mechanical
- J. C. Shropshire, QA Engineer Supervisor
- H. D. Mason, QA Engineer Supervisor D. A. Jenkins QA Engineer J. W. Glenn, QA Engineer H. L. Atkins, QA Engineer J. N. Warren, QC Engineer Civil / Electrical
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l T. A. Barron, QC Engineer Mechanical
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D. H. Llewellyn, Welding Engineer l
W. T. ficClure, QA Technician Other licensee employees contacted in-'uded ten construction craftsmen, three technicians, five inspectors an. three o 'fice personnel.
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- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on July 21, 1981 with those persons indicated in paragraph 1 above. The violation and the unresolved item described in paragraphs 3.c and 9.b, respe-tively, were oiscussed in detail.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction (413, 414/80-05-03) - Failure to require corrective action to prevent repetition of Design Engineering improper identif-ication of safety-related drawings.
Licensee actions concerning this item included procedures changes requiring specification of QA condi-tion on all safety-related drawings, providing an additional check of markings prior to drawing issuance, training of responsible rersonnel and providing a QA audit to assure implementation of adequate correc-tive action. The inspector verified implementation of the above actions and considers them to be satisfactory.
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b.
(Closed) Infraction (413, 414/80-17-01) -Undersize pipe to flange socket welds.
Licensee actions concerning this item included issuance of a new procedure providing additional guidance for weld sizes (CP-427), reinspection of all affected welds and repair of those found to be undersized, and retraining of inspection parsonnel concerning weld sizes.
The inspector verified issuance of CP-427 and verified, on a sample basis, that the additional actions vere completed.
c.
(Closed) Unresolved Item (413, 414/81-08-02) - Spacing of rebar in RCP base blockouts and in pressurizer shield =il area. This item concerned evaluation of embedded rebar spacing in the reactor coolant punp base blockouts and the pressurizer shield wall area.
It has been detennined that the applicable drawings; CN-1051-40, 47 and 49; have been violated and inspection had been performed by the licensee in these areas.
Calculations by the licensee Design Engineering department has shown the spacing to be adequate for the intended load capacity. However, since drawing requirements were not followed this is in violation of 10CFR50, Appendix B, Criterion V which requires that e.ctivities affecting quality be accomplished in accordance with prescribed drawings. The above conditions were identified in Unit 2 only.
This is Violation 414/81-17-01 - Failure to confom to drawing requirements for rebar spacing.
d.
(0 pen) Violation (413/81-02-02, 414/81-02-04) - Apparent generic items or trends not recognized nor forwarded to management.
This ite'n concerned inadequate documentation and evaluation of generic problems.
The inspector reviewed actions concerning nonconforming item reports
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(NCR's) listed in NRC Report No. 50-413, 414/81-11.
Licensee actions are considered satisfactory for NCI Nos. 10917, 11620, 11050, 11324 and 1367.
Action concerning NCI Nos.11325 and 11385 is continuing and will be reviewed at a later date.
The inspector also attended a training session at tha licensee corporate headquarters concerning generic evaluation of NCI's for reportability to NRC.
No violations or deviations were identified.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-
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tions. One unresolved item identified during this inspection is discussed in paragraph 9.b.
5.
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 housekeemng in the auxiliary building, containment buildings, pipe fabrication shop ano storage areas.
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b.
(Closed) Insnector Followup Item (413, 414/80-20-01) - Internal pressure electrical penetrations. This item concerned the fact that documents specifying the internal nitrogen pressure to be maintained in stored electrical penetrations were inconsistent. Penetrations were found which exceeded the maximum allowed by one document. A specific pressure range based on manufacturer's recommendations has been estab-lished and specified in all applicable documents. The pressures found in previously identified penetrations fell within the recommended range. These actions are considered satisfactory.
c.
(Closed) Inspector Followup Item (413, 414/80-28-02) - Seismic support of f1DV junction boxes mounted on electray. The inspector verified that seismic calculations were performed to determine that the junction box supports were adequate.
This action is considered satisfactory.
No violations or deviations were identified.
6.
Containment (Penetrations) - Observation of Work Activities (Unit 1)
The inspector observed n 'callation of 12-inch Type G electrical penetration S/N 9321E for conformance to requirements in the areas of installation in accordance with applicable drawings and procedures, protection from con-struction activities and performance of required inspection activities by qualified personnel.
No violations or deviations were identified.
7.
Safety Related Pipe Support and Restraint Systems (Unit 1)
The applicable code for safety-related pipe support and restraint systems installation is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NF,1974 Edition plus addenda through summer 1975. The inspector observed prefabrication in progress for hanger No.1-A-KC-3348 for confor-mance to requirements in the areas of use of specified base materials, conformance to drawings, in process documentation and control of welding.
No violations or deviations were identified.
8.
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 ASf1E Boiler and Pressure Vessel Code,Section III,1974 Edition plus addenda through summer 1975. The inspector observed in process welds 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, verification of welder quali-fication, use of specified shielding and purge gas, condition of
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welding equipment, provisions of voltage and amperage checks, verifi-cation 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.)
Stages of Welding Observed 1FW10-15
Final plus liquid penetrant inspection 1FW10-16
Final plus liquid penetrant inspection 1FW10-17
Final plus liquid penetrar.t inspection 2NS39-17
Fitup 2NV30-P
Fitup
- First aumber denotes unit number.
No violations or deviations were identified.
9.
Electrical (Cables) - Observation of Work and Work Activities (Unit 1)
a.
The inspector obsened installation in progress of cables IN1747 and 1E'iF743 for conformance to procedure and specification requirements.
Areas reviewed included identification of cable, control of pulling tension, bending radius, protection from damage, routing, supports and in process inspections.
b.
During observation of pulling for cable IN1747 on June 26, 1981 the inspector noted that the angle of pull varied during the pulling operation. This pull through conduit required control of tension using a dynomometer.
It did not appear that the change in angle and it's subsequent effect on pulling tension was being accounted for in the fleid.
In addition, the guidance for calculating pull tension provided in Specification No. CNS-1390.01-00-0070 appears confusing, e.g. the sample calculation does not calculate the value needed in the field, which is the maximum allowed value on the dynomometer. Until further review can be conducted concerning these questions, this will be Unresolved Item 413, 414/81-17-02 - Control cf electrical cable pulling tension.
No violations or deviations were identified.
10. Licensee Identified Items (50.55(e)) (Units 1 and 2)
This paragraph is provided to assign item numbers to Licensee Identified Items for NRC tracking purposes.
Specific followup inspection was not performed for these items.
Items numbers are assigned as follows:
Misapplication of 3000-pound fillings (DPC 413/81-17-01
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No. 81-06)
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Failure of pressurizer power operated relief 413, 414/81-17-03
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(PORV) and block valves during prototype testing (DPC No. 79-07)
Diesel generator turbocharger bearing lubrication 413,414/81-17-04
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system (DPC No. 81-01)
Inadequate evaluation of nonconforming materials 413,414/81-17-05
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to determine reportability to NRC (DPC NO. 81-07)
Inadequate evaluation of nonconforming materials 413,414/81-17-06
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to determine reportability to NRC (DPC No. 81-08)
Fillet welds incorrectly specified (DPC No. 81-09)
413, 414/81-17-07
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Piping restraint r.ot installed in accordance with 413, 414/81-17-08
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design documents (DPC No. 81-10)
Failure of components cooling syrtem motor operated
413, 414/81-17-09
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gate valve during dry cycling (DPC No. 81-11)
Radiographic film for control rod drive violates 413, 414/81-17-10
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code (DPC No. 81-12)
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Piping material defect violated minimum wall (DPC 413,414/81-17-11
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No. 81-13)
No violations or deviations were identified.
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