IR 05000413/1979004
| ML19276F785 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 03/21/1979 |
| From: | Conlon T, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19276F752 | List: |
| References | |
| 50-413-79-04, 50-413-79-4, 50-414-79-04, 50-414-79-4, NUDOCS 7904120102 | |
| Download: ML19276F785 (6) | |
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UNITED STATES ga arou
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NUCLEAR REGULATORY COMMISSION REGION 11
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M 101 MARIETTA STREET, N.W.
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ATLANTA, GEORGI A 30303
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Report Nos.
50-413/79-04 and 50-414/79-04 Licensee: Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242 Facility Name:
Catawba, Units 1 and 2 Docket Nos.
50-413/79-04 and 50-414/79-04 License Nos.
CPPR-116 and CPPR-117 Inspection at Catawba Nuclear Station near Lake Wylie, South Carolina Inspector:
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VanDoofh Date Signed Approved by:
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9/h'//7 f T. E. Conlon, Section Chief, RC&ES Branch Oate' Signed SUmiARY Inspection on February 27 - March 2, 1979 Areas Inspected This routine unannounced inspection involved 25 inspector-hours onsite in the areas of reactor coolant pressure boundary pipe welding, handling, storage, and associated procedures; safety related pipe welding, storage and associated procedures; and liquid penetrant testing of spent fuel pool liner welds (Activities reviewed were for Unit 1, procedures apply to Units 1 and 2).
Results Of the three areas inspected, no apparent items of noncompliance or devia-tions were identified in two areas; two apparent items of noncompliance were found in one area (Deficiency - Signoff of misnumbered welds paragraph 5; Infraction - Inadequate corrective action concerning storage of safety-related piping paragraph 5).
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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
- L. R. Davison, Senior QC Engineer
- J. C. Shropshire, QA Engineer R. G. Rouse, QA Staff R. D. Blackwelder, QA Staff Other licensee employees contacted included 20 construction craftsmen and 2 inspectors.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 2, 1979, with those persons indicated in Paragraph I above.
The two noncompliances described in paragraph 5 were discussed in detail.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effog (Units 1 and 2) The inspector conducted a general inspection of the a.
Unit I containment, the auxiliary building, and prefabricated piping storage areas to observe construction progress and construc-tion activities such as velding, material handling and control, housekeeping and storage.
b.
(Unit 1) The inspector observed liquid penetrant inspection of spent fuel pool liner welds p9,16R and 96L for conformance to code and procedure requirements. The applicable Code for fabrication of the liner plate is the ASME Boiler and pressure vessel code,Section III, 1974 Edition plus addenda through the winter of 1974.
The PT inspection disclosed rejectable defects which were marked for repair and documented.
During this inspection the inspector
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-2-noted that extensive repair welding had been performed in two The licensee indicated that defective carbon steel angle areas.
used for backup between plates may have attributed to this problem.
The licensee also indicated that a different welding technique was being evaluated for the Unit 2 liner plate. This method would consist of placing the plates closer together providing for butt welds in lieu of stainless steel to carbon steel fillet welds.
(Unit 1) The inspector observed field welding of safety-related c.
(class B and C) and reactor coolant pressure boundary (class A)
piping at various stages of weld completion. The applicable Code for pipe welding is the ASME Boiler and Pressure Vessel Code,Section III, 1974 edition plus addenda through the summer of 1974.
(1) The inspector examined weld joint fitup, prior to welding, to determine whether weld identification / location, joint prepara-tion and alignment, evidence of QC verification meet applicable procedures. The following weld joints were examined.
Joint Number Isometric Class System
CN-1KC-553 B
Component Cooling
CN-1RN-407 C
Nuclear Service Water (2) The inspector examined a weld joint where the root pass (only)
has been completed to determine; weld / welder identification, qualified welder / weld procedure, physical appearance of weld and evidence of QC verification.
The following weld joint was examined.
Joint Number Isometric Class System
CN-1RN-407 C
Nuclear Service Water (3) The inspector examined weld joints of pipe to pipe / fitting (PPF) and pipe to components (PC) where welding was beyond the root pass to determine; weld / welder identification, qualified welder / weld procedure, use of specified weld material, proper interpass temperature and physical appearance of weld (e.g.,
starts, stops, undercut and surface imperfections).
Joint Class /
Number Size Tygg Isometric System I 7-4 A,1/2" PPF CNI-11?
Incore Instrumen-tation I 11-4 A,1/2" PPF CNI-Ill Incore Instrumen-tation
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b-3-I 12-4 A,1/2" PPF CNI-Ill Incore Instrumen-tation I 24-4 A,1/2" PPF CNI-Ill Incore Instrumen-tation I 31-4 A,1/2:
PPF CNI-Ill Incore Instrumen-tation I 40-4 A,1/2" PPF CNI-Ill Incore Instrumen-tation
B,3" PPF CN-1NV-312 CVCS
C,18" PPF CN-1RN-221 Nuclear Service Water d.
(Unit 1) On February 28, 1979, the inspector noted that weld stencil numbers placed adjacent to the welds for weld numbers 1RN 407-15 and 1RN 407-16 were reversed. Fitup inspection had been signed off on February 26, 1979. DPC procedure M-4, dated 10/30/78, paragraph 4.2 requires verification of weld stencil numbers to the applicable drawing to be included in fitup inspection.
This is in noncompliance with 10 CFR 50, Appendix B, Criterion V as implemented by the PSAR paragraph 17.1.5, which requires activities affecting quality to be accomplished in accordance with established procedures.
Since Code and NDE requirements were being met and further inspection of these weld numbers is required at the time of installing the succeeding weld this item is a deficiency in lieu of an infraction.
This is item 413/79-04-01 - Signoff of misnumbered welds.
(Unit 1) On March 1, 1979, a review of the prefabricated piping e.
subassembly laydown area disclosed numerous assemblies with end caps missing and/or lying on the ground and several assemblies partially buried.
Construction QA procedure P3, dated 11/12/75; construction procedure CP-116, Rev. 5; and construction procedure CP-170, Rev. 2 require storage of pipe subassemblies upon which welding has taken place to be above ground and with end caps in place and require inspection of the storage areas.
Housekeeping inspection records for September, October and November of 1978 and February of 1979 had identified that piping was improperly stored. A total of 24 corrective action notices had been issued in calendar years 1977 and 1978 identifying improper piping storage.
Although corrective action had been performed to correct each specific storage problem, the corrective action taken was not adequate to preclude improper piping storage. This is in noncom-pliance with 10 CFR 50, Appendix B, Criterion XVI, as implemented by the PSAR paragraph 17.1.16, which requires corrective action to preclude repetition of significant conditions adverse to quality.
This is an infraction and is item 413/79-04-02 - Inadequate correc-tive action concerning storage of safety related piping.
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-4-No items of noncompliance or deviations, except as identified in paragraphs 5 d and 5 e, were identified.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of 6.
Work and Work Activities (Unit 1)
The inspector observed field welding of reactor coolant pressure boundary piping at various stages of weld completion and procedures relative to this area of inspection. The applicable Code for reactor Coolant pressure boundary piping is identified in paragraph 5.c. and is implemented by Specification No. CNS-1206.02-1.0.
The inspector examined weld joint fitup prior to welding, to determine a.
whether weld identification / location, joint preparation and alignment, evidence of QC verification meet applicable procedures.
The following weld joint was examined.
Joint Number Isometric System Pipe Size
CN-INI-164 Safety Injection 10" The inspector examined a weld joint where the root pass (only) had b.
been completed to determine; weld / welder identification, qualified welder / weld procedure, physical appearance of weld and evidence of QC verification. The following weld joint was examined.
Joint Number Isometric System Pipe Size
CN-1NI-152 Safety Injection 10" The inspector examined weld joints of pipe to pipe / fitting (PPF)
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and pipe to component (PC) where welding was beyond the root pass to determine; weld / welder identification; qualified welder / weld procedure, periodic checks of welding variables, use of specified weld material, proper interpass temperature and where applicable pre-heat and post-weld heat treatment and physical appearance of weld (e.g., starts, stops, undercut and surface imperfections).
Joint Number Type Size Isometric System
PPF 31" CN-INC25 Reactor Coolant
PC 31" CN-INC25 Reactor Coolant
PPF 6"
CN-INC30 Reactor Coolant
PFF 6"
CN-INC30 Reactor Coolant
PPF 6"
CN-INC31 Reactor Coolant
PPF 6"
CN-1NC31 Reactor Coolant x
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-5-d.
The inspector observed activities at weld material issue stations to determine adequacy of; weld material storage / segregation, over temperaturec, issue records and return of unused weld material.
Also observed were work areas for uncontrolled weld material.
Within the areas examined, there were no items of noncompliance or deviations identified.
7.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Unit 1)
The inspector observed non-welding work activities and associated proce-dures for reactor coolant pressure boundary (RCPB) piping. The applicable code for installation of RCPB piping is identified in paragraph 5.c.
Observation of specific work activities were conducted to determine conformance, where applicable, with the following; inspection and/or work procedures, record keeping requirements, installation specification requirements, specified materials and qualified inspection personnel.
Specifically, the inspector reviewed handling and installation of piping associated with the various welds identified in paragraph 6; handling and preparations for grinding of weld bevel on pipe IND-38-AA for weld 1, and storage of pipe subassemblies INI-31-AA,1NI-240-AA and AC, no.
and 1NI-32-AA.
No items of noncompliance or deviations were identified.
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