IR 05000518/1980025
| ML19351G003 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 12/30/1980 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19351G002 | List: |
| References | |
| 50-518-80-25, 50-520-80-25, NUDOCS 8102200759 | |
| Download: ML19351G003 (5) | |
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'o UNITED STATES I
8 'i 3 NUCLEAR REGULATORY COMMISSION
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- k ' ",,7 REGION 11
' '.. cf 101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGI A 30303 I
Report Nos.
50-518/80-25 and 50-520/80-25
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Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Hartsville Nuclear Plant Doc'et Nos.
50-518 and 50-520
License Nos.
CPPR-150 and CPPR-152 Inspection at Hartsville Site near Hartsville, Tennessee
Inspector:
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d e-,e n > 7 n
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i N. Econo'mos Date Signed
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/2 - 30 - 5" Approved
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A. R He t,4ection Chief, RCES Branch Date Signed i
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SUMMARY Inspection on November 12 - 14, 1980 Areas Inspected l
This routine, unannounced inspection involved 23 inspector-hours on site in the areas of steel structures and supports - welding observation, reactor coolant and safety-related piping - welding procedures specifications and quality assurance procedures.
Results Of the three areas inspected, no violations were identified.
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l DETAILS
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Persons Contacted Licensee Employees
- R. T. Hathcote, Project Manager
- W. T. Ouinn, Construction Engineer
- H. S. Sheppard, Assistant Construction Engineer, QC
- G. A. Gonsalves, Quality Assurance, Construction
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- A. G. Debbage, Quality Assurance, Construction
- T. L. Carden, Assistant Welding Unit Supervisor E. Loop, Second Shift Welding Unit Supervisor C. A. Mansfield, Weld Foreman W. Harper, Weld Foreman
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R. Armstrong, Weld Foreman
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Other licensee suployees contacted included, construction craf tsmen, technicians, and office personnel.
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j NRC Resident Inspector
- W. B. Swan
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on November 14, 1980 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (518, 519, 520, 521/80-12-02).
Bend Specimen Thickness Tolerance. The licensee has revised paragraph 6.4.3 of Process Specification 1.M.2.2(b) to provide for dimensional tolerances
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l as they relate to bend samples in figure QW462 of ASME Section IX.
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Unresolved Items t
Unresolved items were not identified during this inspection.
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Independent Inspection Effort The inspector conducted a general inspection of units Al and A2 auxiliary and reactor buildings to observe work activities in the areas
of piping, welding, storage conditions, material handling and control, housekeeping.
Within these areas no violations or deviations were identified.
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6.
Steel Structures and Supports - Observation of Welding Activities within Containment (Unit A1)
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Welding inside containment at the time of this inspection was centered around the shield wall containment steel structure and on the dry wall vent structure (DVS).
C. F. Braun specification number 300-09, Revision 5, 5/9/78 provides specific requirements relative to fabrication inspection and testing of the DVS.
Codes controlling these activities included ASME sections III, (74,S74)
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l Division 1 NE-5100, NE-5300, Secticn V and IX; AWSD1.1-74. The
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applicable code for containment (CS) welding, as required by Braun
and Company specification 300-13, Revision 7 and TVA " Code of Record" letter dated October 23, 1978, is the ASME Boiler and Pressure Vessel Code,Section III, Division 1, Subsection NE,1974 Edition, Summer 1974 Addenda for the shell and Division 2, l
Subsection CC,1975 Edition for the bottom liner.
Observation of field welding activities included, where
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applicable, the following areas; weld identification and location, joint preparation and alignment, evidence of OC verification, use
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i of specified weld procedure, welder qualification, use of
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specified weld material, use of specified preheat, control of interpass temperature, cleanliness, removal of arc strikes and
weld spatter. The following welds were observed:
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Containment
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l Weld Condition AICS00520 partial A1CS00812 partial Shield Wall PSW00090 (penetration)
partial PSW00089 (penetration)
partial Within the areas inspected, no violations or deviaticos were identified.
7.
Safety-Related Piping, Observation of Welding Activities (Unit A-1)
Welding activities of safety-related piping were observed in order to detemine whether they were consistent with applicable code and proce-dural requirements. The code of record for this activity is ASME Sections III and IX 1974 Edition and addenda through summer 1974.
Field welds in various stages of fabrications were selected at random for observation and record review to ascertain whether work was being perfomed in accordance with the appropriate traveler and welding procedure.
In addition the inspector observed workmanship, weld / welder
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identification, cleanliness and reviewed welder qualifications.
The following welds were observed / inspected.
Weld Size (diameter)
System inches
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A1FRH0511002R1 10b Residual Heat Removal l
A1 ARC 0060004 6h Reactor Coolant A1 ARC 0010007
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A1AES0060001 10b Essential Services A1FFC0942005
Fuel pool cooling Within the areas inspected, no violations or deviations were
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identified.
8.
Reactor Coolant Loop Piping - Welding Procedure Specifications and Quality Assurance Procedures The licensee's QA Manual _and referenced documents were reviewed to ascertain whether adequate QA plans and procedures have been established to assure that welding activities are controlled and accomplished within applicable code and QA program requirements.
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Specific areas selected for review included quality requirements, procurement, documentation and deviation disposition, test result documentation / certification, control and component identification; work
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and quality inspection procedure review, approval and availability at i
work areas; material control including identification, traceability, handling, storage and certification; control of special processes, test and control of test equipment QA plans and/or procedures which impact these activities.
The procedures reviewed were as follows:
i Nuclear Components QA Manual Section 3.1 Rev. 9, Control of Purchase Requisitions
Section 2.1 Rev. 12, Design Control Section 9.1 Rev. 12, Records Section 9.2 Rev. 10, Code Symbols and Data Reports Section 4.1 Rev.13, Manufacturing and Installation Section 4.3 Rev. 3, Process Control at HNP Section 5.1 Rev. 13, Welding Control Section 2.3 Rev. 7, Preparation Review and Approval of Process, Specifications and Assignments of Welding and NDE Procedures Section 3.7 Rev. 8, Material Control and Identification Section 3.6 Rev. 9, Receiving Inspection, Storage Preservation and Issuing of Code Items Section 10.2 Rev. 15, Nonconforming Items Section 7.1 Rev.13, Calibration of and Test Equipment
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Construction Engineering Procedures (CEP)
CEP 8.01, Rev. 3, Identification and Marking of Material, Parts and Components CEP 8.02, Rev. 5, Materials, Parts and Components CEP 6.02, Rev. 7, Control and Distribution of CEP's, QCI's, RI's and PM's CEP 12.01, Rev. 6, Control of Measuring and Test Equipment CEP 10.01, Rev. O, Inspection The applicable code for reactor coola~nt piping work is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, 1974 Edition with
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Addenda through the Summer of 1974.
Welding on safety related structures / piping is controlled by ASME Section IX (74S74) implemented
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by the General Construction Specification G-29M.
General Walding Procedure Specification 1.M.1,P(b) as it applies to HNP and the following detail weld procedures with corresponding procedure qualification reports (PQRs) were reviewed for conformance with
applicable code requirements.
Detail Weld Procedure (WPS)
7 Gas Tungstan Arc (GTA)
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GT11A Rev. 6 GT11-0-1
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GT11-0-2 GT11-0-2 GTA/ Shielded Metal Arc
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GTSM88-0-1B GTSM88-0-1 GTSM88-0-2 GTSM11-0-3B GTSM11-0-3
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For these WPSs, areas of specific interest included identification of-essential and nonessential variables, availability and accuracy of corresponding PQRs, certification, documentation of revisions.
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Within the areas inspected, no violations or deviations were identified.
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Other Safety-Related Piping Welding Procedure Specifications and Quality Assurance Procedures
The procedural review and inspection results of paragraph 8 above also l
apply to safety-related piping in that this piping is being installed under the same control procedures as for reactor coolant pressure
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boundary piping.
The applicable code is the same as that referenced in paragraph 8 except that subsections NC and ND apply in lieu of NB.
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