IR 05000413/1980002
| ML19305D900 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/11/1980 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305D898 | List: |
| References | |
| 50-413-80-02, 50-413-80-2, 50-414-80-02, 50-414-80-2, NUDOCS 8004160122 | |
| Download: ML19305D900 (7) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION
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o 101 MARIETTA ST N.W., SUITE 3100 ATLANTA. GEORGIA 30303 o
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MAR 121980 Report Nos. 50-413/80-02 and 50-414/80-02 Licensee: Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242 Facility Name: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117
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Inspection at Lake Wylie, South Carolina Inspector!'
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N. Economos'
pate Signed Accompanying Personnel:
L. D. Zajac (Training)
Approved by:
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A. R. Iferdt, Section Chief, RCES Branch Date Signed
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SUMMARY Inspection on February 12-14, 19,80 Areas Inspected This routine, unannounced inspection involved 33 inspector hours onsite in the areas of reactor coolant pressure boundary piping; safety-related piping; safety-related structures (welding) observation of work and work activities; and vendor pipe welds with rejectable indications.
Results
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Of the four areas inspected, no apparent items of noncompliance or deviations
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were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- D. G. Beam, Project Manager
- D. L. Freeze, Project Engineer
- R. A. Morgan, Senior QA Engineer
- R. G. Rouse, QA Technician
- L. R. Davison, Senior QC Engineer
- H. D. Mason, QAE Civil, Electrical
Other licensee employees contacted included seven construction craftsmen five technicians, and two engineers.
Other Organizations Hartford Steam Boiler Inspection and Insurance Company
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- J. W. Kasko, Authorized Nuclear Inspector (ANI)
NRC Resident Inspector
- G. F. Maxwell
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Richmond Engineering Company (RECO)
J.
R. Palmore, QC Inspector
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- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on February'14,1980, with those persons indicated in Paragraph I above. The inspection included reactor coolant pressure boundary piping, safety-related piping, and safety-related structures. No dissenting comments were received from the licensee.
3.
Licensee Action on Previous Inspection Findings
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Not inspected.
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 noncompliance or
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deviations. New unresolved items identified during this inspection are discussed in Paragraphs 5 and 8.
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5.
Independent Inspection Effort a.
Plant Tour (Units 1 and 2)
The inspector performed a general inspection of Unit I reactor building, auxiliary building and turbine building. Around the work areas the inspector observed certain pipe handling activites including installation and welding, the general state of housekeeping, cleanliness, control of used/ unused weld electrodes around working areas and the proper use of wire brushes on stainless steel material.
b.
Linear indications in SA-312 Stainless Steel Swepco Fabricated Pipe Welds In response to a RII request the inspector reviewed the radiogra'phs of certain field fabricated pipe welds that depicted rejectable rounded and/or linear indications in the vendor (SWEPCO) fabricated longitudinal joints. The welds in question were in 8" schedule 40 stainless steel type-304 material produced to SA-312, ASME Section III, Class 2 (74S74)
and DPCO's specification CNS-1206.00-2.2 Rev. 12.
The welds had been titrasonically (UT) inspected by Swepco per procedure VE-102 Rev. O and ASME Section III, NC-2550. Records of UT test results indicated the welds were satisfactory. The following table identifies the welds and the radiographic indications observed.
Location-Distance from Circumferential Weld No.
System
, Size Indication Weld Fusion Line INS 83-2 Containment Spray 8" sch.40 3/4" linear 5/8-inches INS 82-7 Containment Spray 8" sch.40
\\" linear 5/8-inches 3/16" linear 3/16-inches INS 73-12 Containment Spray 8" sch.40 1-3/8" linear 1/16-inches All the indications appeared to be situated close to the root of the weld. The licensee has issued nonconformance item reports on these welds.
Nondestructive requirements relative to SA-312 epecification were discussed in detail with the licensee's cognizr.nt QA representative whose position was that quality records show the er.cerial met speci-fication requirements, hence repairs and/or additional NDE testing e.g., radiography, would be in excess of code /sper.ification minimum requirements.
The inspector stated that a reexamination of selected welds including the welds in question with the vendor'p' technique would help determine the adequacy of the UT procedure and/or'the ability of UT to detect i
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these type of indications. The QA representative agreed to look further into this matter. During a telephone conversation with the licensee's representative on February 18, 1980, the inspector stated this matter would be identified as an unresolved item pending review of remedial licensee action on this matter. The unresolved item was identified as follows, 50-413/414/80-02, Linear indications in SWEPO fabricated SA-312 stainless pipe.
I 6.
Reactor Coolant Pressure Boundary (RCPB) Piping (Welding) Observation of Work and Work Activities The inspector observed field welding of reactor coolant pressure boundary at various stages of weld completion. The applicable Code for safety-related pipe welding is ASME B&PV Code Section III, 1974 Edition with Summer 1974 Addenda as implemented by Duke ASME QA Manual.
- Observation of field welding activities included, where applicable, the following areas: weld identification and location, joint preparation and alignment, specified weld procedure, welder qualification, specified weld material, specified purge, specified temperature (pre-heat, inte rpass),
welding variables within limits, evidence of QC verification, physical appearance suitable for NDE and specified NDE being performed. Weld repairs were observed and related QC records were reviewed for completeness and accuracy. Following are welds selected for this effort:
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a.
Joint Fitup Joint Number Isometric System / Size INC 226-1 CN-INC-226 NC (6" Diameter)
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Root Pass Only Joint Number Isometric System / Size INC-46-19 CN-INC-46 NC (3" Diameter)
NC-1506-5 CN-NC-1506 NC (3/4" socket)
Welding Complete and Testing in Progress / Complete c.
Joint Number Isometric System / Size
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INI-162-14 CN-INI-162 NI INC-82-5 CN-INC-82 NC
, (10" Diameter)
(1-1/2" Socket)
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Repairs Joint Number Isometric System / Size
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INC-29-7 CN-INC-29 NC (10" Diameter)
INC-29-4 CN-INC-29 NC (10" Diameter)
INI-162-12 CN-INI-162 NI (6" Diameter)
INI-162-9 CN-INI-162 NI (6" Diameter)
Work areas were observed for the presence of uncontrolled weld consumables
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and the rod issue station was inspected for compliance with procedural requirements. The number of QA/QC inspection personnel assigned to work areas appeared to be commensurate to the amount of work in progress.
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Within the areas inspected no items of noncompliance or deviations were identified.
7.
Safety-Related Piping (Welding) - Observation of Work and Work Activities The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various states of weld completion.
See Paragraph 6 above for the applicable code.
The inspector examined weld joint fitup, prior to welding, to determine whether weld identification / location, joint preparation and alignment, and evidence of QC verification meet applicable procedures. Selected completed welds were inspected to ascertain whether surface conditions were suitable for nondestructive examinations performed. Weld repairs were observed and related QC records were reviewed for completeness and accuracy.
Following are welds selected for this effort:
a.
Joint Fitup Joint Number Isometric System / Size INS-122-2,-4,-6, CN-INS-122 NS (1" Diameter)
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-8,-10,-12.
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Welding Complete and Testing in Progress / Complete Joint Number Isometric System / Size INS-111-1B CN-INS-Ill NS (Containment Spray (Spool No.)
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INI-162-12 CN-INI-162 NI
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(6" Diameter)
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IWL-927-6 to -12 CN-1WL-927 WL (2" Diameter)
IVB-20-1 CN-IVB-20
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Repairs Joint Number Isometric System / Size 2 FD-37-13 CN-2FD-37 FD (3" Diameter)
Within these areas, the inspector noted that the application of liquid penetrant (PT) developer, on the nozzle and nipple socket welds on contain-ment spray header spool INS-1.11-1B, appeared to be extremely thin and nonuniform in some cases. The inspector discussed this observation with DPCO's cognizant NDE personnel who stated that NDE technicians have been instructed to apply a thin and uniform coating of developer on welds under examination. The technician was asked to PT some other similar welds in the same manner and the results were observed by the licensee and the, NRC inspectors.
This time, the developer appeared to be more uniform but still on the thin side.
In view of these circumstances the inspector stated that since these items " thin" and " uniform" are subject to individual interpreta-tions it would be worthwhile to develop acceptance standards that could be used for training and reference purposes on the job. The licensee agreed to look into this matter further and report in a subsequent inspection.
This matter was identified as inspector follow-up item 50-413/80-02-01,
" Liquid Penetrant Developer Application Standards".
Within the areas inspected, no items of noncompliance or deviations were identified.
8.
Safety-Related Structures (Welding I) - Observation of Work and Work Activities (Unit 2)
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The refueling water storage tank (RWST) for Unit 2 is being fabricatd by
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Richmond Engineering Company (RECO) under contract with DPCO. The controlling specification is CNS-1148.00-03 " Specification for Fabricating and Designing, Erecting and Furnishing Water Storage Tanks" while the applicable code is ASME Sections VIII and III, NA, NC (74S75) Class 2.
At the time of this
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inspection work was in progress on the roof and on the vertical and the horizontal welds on the sidewall of the tank. Field weld activiti es observed included weld identification and location with respect to drawing CN-1325-02, D-76-414 Rev. 4; joint preparation and alignments; use of properly qualified weld procedures and welders; use of specified weld material that was properly controlled and its quality verified by appropriate quality records. Welds selected for this work effort were as follows:
Vertical Seams - 11, 12, 27, 28, 29, 31 and 32 Horizontal Seams - 9 and 10
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The tank is being fabricated from materia'l produced in accordance with ASME, SA-240 stainless steel type 304. Shell plates with serial numbers W2250 and W2318 were selected for a review of receipt inspection reports and quality records.
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-6-J Weld consumable storage and issuing facilities were inspected and quality records of material on hand identified by beat numbers 586062, 5/32" diameter R308 and #586062 1/8 diameter R308 were reviewed for compliance with code and procedural requirements. Also radiographs of selected completed welds 9 (horizontal) and 11, 12 (vertical) were reviewed for code compliance.
Within those areas the inspector noted that heavy grinding of the base material in the area of the heat affected zone of vertical weld no.
31 of the 5th ring may have resulted in a violation of a minimum wall requirements and at the same time produced an abrupt weld to base-metal transition with associated stress risers. This condition was discussed in detail with RECO's cognizant QC inspector and DPCO who agreed to measure the thickness of the suspect material and to inspect for abrupt weld to base-metal transi-
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tions. The inspector stated this matter would be identified as unresolved item number 50-414/80-02-01 " Weld and Base-Metal Grinding on RWST".
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