IR 05000518/1981024
| ML20041A662 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 01/27/1982 |
| From: | Hardin A, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041A656 | List: |
| References | |
| 50-518-81-24, 50-519-81-24, 50-520-81-24, 50-521-81-24, IEB-80-08, IEB-80-8, NUDOCS 8202220390 | |
| Download: ML20041A662 (6) | |
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neeog UNITED STATES
o,i NUCLEAR REEULATORY COMMISSION
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I REGION 11 101 MARlETTA ST., N.W., SUITE 3100 o,%
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ATLANTA, GEORGIA 30303
Report Nos. 50-518/81-24, 50-519/81-24, 50-520/81-24 and 50-521/81-24 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Hartsville Nuclear Plant Docket Nos. 50-518, 50-519, 50-520 and 521 License Nos. CPPR-150, CPPR-151, CPPR-152 and CPPR-153 Inspection at Hartsvi le site near Hartsville, Tennessee b
/ /27/2 E Inspector:
ur w.
J.
. Schipker
Date Signed (!w
//17M Approved by:
e A.
K.' Hardin, Acting Section Chief, Division of Date Signed Resident and Reactor Project Inspection SUMMARY Inspection on December 1-31, 1981 Areas Inspected This routine, unannounced inspection involved 117 inspector-hours on site in the areas of safety-related structures (Unit A-1), previous inspection findings (Units A-1, A-2, B-1 and B-2), installation of safety-related piping (Unit A-1),
placement of structural concrete (Unit A-1), open items, and independent inspection effort (A-1 and A-2).
Results Of the 6 areas inspected, no violations or deviations were identified.
8202220390 920127 PDR ADOCK 05000518 G
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DETAILS 1.
Persons Contacted Licensee Employees-
- R. T. Hathcote, Site Project Manger R. E. Young, Assistant Construction Engineer, PE R. E. McClure, Unit Supervisor, Mechanical QC, STRIDE T. O. Wilkenson, Unit Supervisor, Material Services J. W. Henry, Unit Supervisor, QC Welding T. L. Garden, Assistant Unit Supervisor, QC Welding K. H. Stewart, Assistant Construction Enginecr, Engineer Service H. S. Sheppard, Assistant Construction Engineer, Quality Control F. E. Laurent, Unit Supervisor, STRIDE Mechanical Project Engineering G. A. Gonsalves, QA Unit Supervisor M. U. Rudolphi, Unit Supervisor, Project Engineering, Hangers and Supports J. T. McGhee, Engineering itanagement Assistant A. J. Everitt, Welding Engineer V. L. Ledbetter, Construction Engineering Associate D. H. Mickler, Welding Engineer Other licensee employees contacted included document control personnel, construction craftsmen, QC technicians, and project engineers.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized with the Site Project Manager on December 4, 11, 18, 24 and 30, 1981.
3.
Licensee Action on Previous Inspection Findings (Closed) Violation 518, 519, 520 and 521/81-13-02_ Inadequate Preventive Maintenance procedures for Fire Pump Diesel Engines.
The inspector reviewed the licensee's revised procedure requirements addressed in the RS and Pill Manual TVA I 40124.T9 Section 6BS, Revision 2, Paragraph 19, which incorporates preventive maintenance for the fire pump diesel engines, and verified that preventive maintenance has been imple-mented as stated in the licensee response letter.
(Closed) IFI 518/81-17-01 Radiograph (RT) Procedure Identification on Radiograph Reader Sheets The inspector selected a random sample of radiographs to verify the RT procedure was' addressed on the reader sheets.
The licensee has ordered the preprinted reader sheets with the applicable procedure number applied for future us _-
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4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort The inspector made 5 surveillance tours during which the status of project work was noted, and construction activities were inspected on nuclear safety related structures, systems and facilities.
The inspection included:
a.
Concrete placement pour AIC-9F, west wall of the auxiliary building, elevation +48.3.
The inspector verified preplacement cleanliness, forming and rebar placement were in accordance with applicable drawing and specification requirements.
Placement of the concrete was accomplished in accordance with the licensee's construction engineering procedure CEP 9.02, Revision 5, and TVA construction specification G-2 QCI C-201, Revision 4.
b.
Setting of A-1 and A-2 Diesel Generators (DG) for Temporary Storage.
The inspector observed the DG rigging and placement on the pads of the A-1 and A-2 DG buildings. The applicable procedure for handling of nuclear components is CEP 13.01, Rev. 4.
The DG's were set on timbers for temporary storage with portable metal storage buildings erected around them. The periodic maintenance for the DG's is specified by the licensee's RS and Ptil procedure requirements.
Permanent installation of the DG's is not scheduled at this time.
c.
Open Site Quality Control Items:
The inspector reviewed the licensee's Nonconformance Reports (NCRs),
the significant Quality Control Inspection Reports (QCIR's) and QA Unit audit findings for pertinence to the inspection program and for adequacy of corrective action.
(1) NCR-HNPA-184 Containment based material defects adjacent to vertical weld seam AICS00725, was reviewed in depth to assure corrective action as recommended by the licensee meets the applicable code and specification requirements. The applicable code for the containment vessel is the ASf1E Boller and Pressure Vessel Code,Section III, Subsection NE, Class MC Components and Articles NA-4000 and NA-5000 of Section III, Division 1,1974 Edition, including S74 addenda.
The applicable specification is C. F. Braun and Company, Containment Vessel, Project 4840-P, Specification 300-13, Revision 9.
Radiograph AICS00725 was reviewed to ascertain the extent and type of base material defects present adjacent to the weld.
From this review the inspector observed the defects were of laminar oriented non metallics inclusion (slag, mill scale) of light density which
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are a common type defect for rolled plate and not considered detrimental for its intended use.
In addition, the inspector reviewed the applicable AST!! Standard (SA516-70), and the licensee's purchase order (Bristol Steel),
Contract F0109A (X17) 75K61-86227-2) to assure the material inclusions meet the required material specification requirements and any supplementary requirement imposed by the purchase order.
In the areas inspected no violations or deviations were identified.
6.
Licensee Identified 50.55(e) Items Iterim reports were received from the licensee on two previously identified items.
The inspector reviewed these reports and found that none contained information which would permit closure.
Follow on reports are scheduled at later dates.
(0 pen) 518,519, 520, 521/80-15-1 Hartsville and Phipps Bend, Rosemount Model 1152 and 1151 Pressure Transmitter Defect dated December 17, 1981. Next report scheduled June 22, 1982.
(0 pen) 518,519, 520, 521/CDR 81-008 Failure by ITT Grinnell to Use Proper Testing Methods. Next scheduled report June 22, 1982.
7.
Safety-Related Structures a.
Observation of Welding Activities The inspector observed welding preparation and repair weld to Unit A-2 biological shield weld seam identified A-2 PSW 00029 and A-2 PSW 00058, located in the iron workers' shop A.
Weld Procedure Specification SM-U-1 Revision 4 was utilized.
This procedure is prequalified (PQR)
as specified in AUS D1.1 Structural Welding Code. The welder's qualification certification was verified to the referenced weld procedure specification.
b.
Drywell Wall Embedment Frames (Unit A-1).
The drywell wall embedment frames in Plant A-1 are in process of removal and repair of welding defects.
The inspector is monitoring these repairs and subsequent nondestructive examinations. flagnetic particle examination of excavated defective welds and completed weld repairs are observed by the inspector. The following is a tabulation of obser-vations made to date:
Frame #
Weld #
Excavation MT Weld Repair Final HT
43AB Acceptable Incomplete
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364T Incomplete
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7 3738 Acceptable Incomplete
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409D Acceptable Incomplete
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468D Incomplete
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125F Acceptable Complete Acceptable
138G Acceptable Incomplete
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14C Acceptable Incomplete
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138N Acceptable Incomplete
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179H Acceptable Complete Acceptable The following repair welds were monitored in process:
Frame #
Weld #
Welder WPS
125F IAEE SilVIB Rev. 6
138G IABG Si1VIB Rev. 6
138N IAIV SfiUIB Rev. 6
43AB IAFA SMUIB Rev. 6 The inspector also verified material issue, temperature control, segregation, cleanliness, container integrity, and handling of returned materials at the weld rod crib to be in compliance with TVA Process Specification CEP-803, Revision 12. Weld material handling by the representive welders was verified for adequate segregation, cleanli-ness, temperature control, issue records for proper sign offs, identify material and withdrawer, dates of withdrawal and amount withdrawn.
8.
Safety Related Piping (Unit A-1)
a.
Observation of Welding Activities The inspector observed welding activities for safety-related piping outside of the reactor coolant pressure boundary as described below to detennine whether applicable code and procedure requirements were being met.
The applicable code for safety-related piping is the ASf1E B&PV Code,Section III, Subsection NC and ND,1974 Edition, with addenda through stimmer 1974.
The welds listed below were examined in process to determine: whether work was conducted in accordance with travelers; welder identificatian and location; welding procedure; welding techniques and sequence; materials identification; weld geometry; fit-up; preheat; electrical characteristics; shielding gas; welding equipment conditon; interpass temperature; interpass cleaning; qualification of welders; qualification of inspection personnel; and weld history records.
Held #
Code Welder AIFFC0031R05 III-3 FAFH AIARH0721R01 III-2 FABQ AIFFC2210002 III-3 FAftA AIARH0211001 III-2 FADK
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b.
Observations of Nondestructive Examination (NDE)
The inspector observed NDE on the following weld seams outside of containment as described below to determine whether applicable codes and procedure requirements were being met.
Weld #
Code NDE Method AIARH0211001 RS III-2 Liquid Penetrant AIFBFPCC204-2 III-3 Visual AFFCC0031R05 III-3 Visual / Liquid Penetrant AIARH0070005 R-1 III-2 Visual / Liquid Penetrant
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AIARH0090005 III-2 Radiography AIARH0420004 III-2 Radiography Applicable NDE procedure fc'r visual is QCI-N-501, Revision 6 Liquid penetrant Examination QCI-h'-101, Revision 7 Radiography QCI-N-301, Revision 3.
Within the areas inspected no violations or deviations were identified.
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9; Open Bulletins, IEB 80-08 Examination of Containment Liner Penetration Welds.
The inspector reviewed applicable drawings for configuation of welds for installation of the flued head penetrations and verified radiography is specified for the welds concerned in the bulletin. The welds completed by the vendor (Ametek) were verified to have been radiographed by review of as-builts and quality documentation which included the radiograph reader sheets.
(Radiographs have not yet been turned over to the licensee.) The following penetration QA documentation was reviewed.
Part Number 7-050157-1, Penetration 9SCD, S/N 971; S/N 1182; 10 SCD, S/N 971; 11SCD, S/N 970; and 12SCD, S/N 972.
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