IR 05000400/1982006
| ML20053B269 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/26/1982 |
| From: | Coley J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053B249 | List: |
| References | |
| 50-400-82-06, 50-400-82-6, 50-401-82-06, 50-401-82-6, NUDOCS 8205280237 | |
| Download: ML20053B269 (8) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
E REGION 11
o, 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
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Report Nos. 50-400/82-06 and 50-401/82-06 Licensee:
Carolina Power and Lighs Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name:
Shearon Harris Docket Nos. 50-400 and 50-401 License Nos. CPPR-158 and CPPR-159 Inspection at Shearon Harris site near Raleigh, North Carolina Inspector: \\.M 3 - O[- kk
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J. L>h Date Signed Approved by:
M (;
V A.
. Herdt, Section Chief Date Signed Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on February 23-26, 1982 Areas Inspected
This routine, unannounced inspection involved 26 inspector-hours on site in the j
areas of reactor coolant loop piping (Unit 1), safety related piping (Unit 1),
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followup on regional request (Units 1 & 2), and previous inspection findings (
(Unit 1).
I Results l
Of the four areas inspected, no violations or deviations were identified in three areas; one violation was found in one area (Violation - Failure to follow visual procedure (NDEP-601) for examination of pipe welds, paragraph 9).
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I REPORT DETAILS 1.
Persons Contacted
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d Licensee Employees
- R. M. Parsons, Site Manager
- S. Smith, Vice President Nuclear Construction f
- N. J. Chiangi, Manager Engineering and Construction QA/QC
- C. R. Osman, Principal QA/QC Specialist
- D. C. Whitehead, QA Supervisor
- E. M. Harris, Jr., Principal Mechanical Engineer
- G. White, Project Engineer
- E. E. Willett, Resident Engineer Mechanical
- B. Seyler, Principal Engineer Civil
- G. M. Simpson, Principal Construction Specialist
- W. Mercer, Welding QA/QC Specialist
- G. Daniel, Mechanical-QA/QC Specialist NRC Resident Inspector
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G. F. Maxwell
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 26, 1982, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding listed below.
No dissenting comments were received from the licensee.
(0 pen) Violation 400,401/82-06-01:
Failure to Follow Visual Procedure (NDEP-601) for Visual Examination of Pipe Welds, paragraph 9.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Unresolved Item 400/81-22-03: " Drawing Inconsistencies." An
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NRC inspector had noted that drawing SK-A-G-0165 Rev. 2, the weld map
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for the fuel pool liner plates, did not appear to correctly depict the location and orientation of welds. This drawing was used only as an aid for joint identification and not for construction. The inspector reviewed the licensee's corrective action and found that the licensee had identified this problem and had revised drawing SK-A-G-0165 several days prior to the inspector reporting this finding.
However, copies of the revised drawing had not been distributed to the craft. The inspector reviewed the revised drawing and found that the wr.lds i
were correctly depicted on the revision. This matter is cons'dered resolved.
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b.
(Closed) Unresolved Item 400/81-22-05: " Improper Specified Fillet Weld Size." Weld Data Reports (Traveler) for chilled water system socket weld joints 1-CH-92-FW-250 through FW-225, with 0.179 " wall thickness, specified 3/16" (0.1875") fillet leg size.
This is contrary to ASME Section III which requires 0.195" minimum fillet leg size for 0.179" wall socket weld joints. At the tirre of the inspection, it could not be determined whether any undersized socket weld joints had been accepted as a result of the incorrectly specified fillet weld leg size.
The licensee had the above welds reinspected and the minimum reading for all the welds were above the 0.195" minimum required. In addition weld data reports for the above welds were revised to reflect the correct leg sizes and other weld data reports were reviewed to deter-mine their correctness. This matter is considered closed.
c.
(0 pen) Violation 400/81-15-02:
" Failure to Follow Procedure for Inspection of Fuel Pool Liner Welding." Paragraphs 6.3.5 and 6.3.8 of Carolina Power and Light Company Procedure CQC-19 " Weld Control,"
required that fitup inspection be performed on all full penetration seismic category I welds and that all seismic category I welds be inspected on monitoring basis and the monitoring inspection recorded on a weld inspection checklist. This violation was identified because for fuel pool liner welding, classified as seismic category I by the PSAR, fitup inspections were not being performed and monitoring inspections were not being recorded on weld inspection checklists.
The licensee stated that, paragraphs 6.3.5 and 6.3.8 t - procedure CQC-19, were not intended to apply to the fuel pool liner welds. These welds, while designated as seismic category I, are not structural welds.
Inspection requirements for the fuel pool liner welds are provided in Ebascc Specification CAR-SH-AS-17 " Pool Liners".
These requirements, whit n include visual inspection, liquid penetrant exam-ination and vacuum box testing of completed weld surfaces, are to ensure the leak tightness rather than structural integrity.
The licensee's investigation of the violation revealed that monitoring of fitup had been conducted on a random basis, but that the assigned inspector did not document this monitoring because procedure CQC-19 did not address monitoring of the fuel pool liner welding.
The inspector found that the licensee had revised CQC-19, to Revision 2 to clarify the scope of paragraphs 6.3.5 and 6.3.8, and to add the inspection requirements for fuel pool liner welds as specified in Ebasco Specification CAR-SH-AS-17.
The procedure revision also includes requirements for monitoring fuel pool liner welding activi-ties, such as fitup, preheat and interpass temperature, in accordance with procedure CQA-22, " Welding Activity Monitoring." The inspector was informed that monitoring of these activities on a routine basis was initiated immediately following NRC inspection 400/81-15.
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3 The inspector reviewed the monitoring checklist and Revision 2 of Procedure CQC-19.
During this review the inspector noted that the
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procedure did not specify how the fuel pool liner plate welding inspections would be documented.
This item will remain open until CQC-19 is revised to address documentation of fuel pool liner plate welding and inspections.
Within the areas examined no violations or deviations were observed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspector Followup Items (Unit 1)
(Closed) Inspector Followuo Item 400/82-01-05: " Inspection of Pipe Welds."
This item was opened to track a Region II concern for the NRC inspector to reinspect a larger sample of non-ASME pipe welds to determine whether a licensee inspector was signing off pipe weld joint records without actually examining the welds.
A larger sample was reinspected during this inspection and this followup item was closed and elevated to a violation.
This item is discussed in greater detail in paragraph 9 of this report.
6.
Independent Inspection Effort (Units 1 & 2)
i The inspector conducted a general inspection of the reactor building, auxiliary building, fuel handling building and storage yards to observe i
construction progress and construction activities such as welding, material control, housekeeping, material handling and' storage. The following speci-f fic items were examined:
j a.
Fuel Handling Crane Weld Defects - Yard Storage The licensee has identified welding defects in its fuel handling crane
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and has reported its preliminary findings to Region II as a potential construction deficiency.
Numerous weld defects of various kinds were identified. The inspector observed that the type of defect which had been identified was primarily undersized welds.
The licensee is presently evaluating these weld discrepancies to determine their severity and whether this item will be reportable in accordance with 10 CFR 50.55(e).
b.
Spool Pieces - Yard Storage Pipe welding and preservation were examined on ASME Class 1,2 & 3 spool
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pieces located in yard storage l
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Within the areas inspected, no violations or deviations were identified.
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7.
Reactor Coolant Pressure Boundary Piping (Unit 1)
a.
Observation of Welding Activities The inspector observed work performance and work in process to deter-mined whether field welding activities associated with reactor coolant pressure boundary piping are controlled and performed in accordance with applicable code and specifications. The applicable code for this work is the ASME Boiler and Pressure Vessel Code,Section III, Subsec-tion NB,1974 edition including addenda through winter 1976.
The following weld joints were inspected during inprocess inspection:
WELD JOINT #
SYSTEM SIZE 1-RC-2-FW-8 Reactor Coolant 31" X 2.48" 1-RC-3-FW-4 Reactor Coolant Repair (external)
1-RC-3-FW-3 Reactor Coolant Repair (internal)
18-FW-6 Incore Instrumentation 1" X.200" nozzle weld The welding was examined to determine whether:
(1) Work is conducted in accordance with a document which coordinates and sequences operations, references procedures, establishes hold points, and provides for production and inspection approval.
(2) Weld identification and location are as specified.
(3) Procedures, drawings, and other instructions are at the work station and readily available.
(4) WPS assignment is in accordance with applicable code requirements.
(5) Welding techniques and sequences are specified and adhered to.
(6) Welding filler materials are the specified type and traceable to certification.
(7) Alignment of parts is as specified.
(8) Preheat and interpass temperatures are in accordance with proce-dures.
(9) Electrodes are used in positions and with electrical character-istics specified.
(10) Shielding gas is in accordance with the welding procedures.
(11) Welding equipment is in good conditio m
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(12)
Interpass cleaning is in accordance with applicable procedures.
(13) Temporary attachments are removed in accordance with applicable procedures.
(14) Welding personnel are qualified.
(15) Weld history records are adequate.
b.
Welder Qualification The inspector reviewed the welder qualification records for the welds listed in a. above.
Within the areas examined, no violations or deviations were observed.
8.
Safety-Related Piping (Unit 1)
The inspector observed work activities for safety-related piping as described below to determine whether applicable code and procedure require-ments were being met. The applica'le code for safety-related piping is the ASME B&PV Code,Section III, Subsections NC and ND, 1974 edition with addenda through winter 1976. The inspector observed activities as described below to determine whether applicable code and procedure requirements were being met for the following components:
ITEM INSPECTED ASME CLASS ACTIVITIES OBSERVED 1-CX-61-3 (spool piece)
Installation of Spool Pcs.
1-CX-61-4 (spool piece)
Installation of Spool Pcs.
1-MS-70-1 (spool piece)
Handling, Cleanliness & Protection 1-FW-31-4 (spool piece)
Handling, Cleanliness & Protection The inspector observed the activities reported above to determine whether:
a.
Activities were in conformance with inspection (QC) and work perform-ance procedures b.
Activities were in conformance with record keeping requirements c.
Activities were in conformance with construction / installation speci-fication d.
Issuance and use of material as specified e.
Performance of prescribed inspections f.
Utilization of qualified inspection personnel Within the area examined, no violations or deviations were observe s
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9.
Followup On Regional Request (Units 1 & 2)
As part of an ongoing investigation (see report 50-400,401/82-01), it was requested that non-ASME pipe welds inspected by a certain licensee welding inspector from June 1981 thru September 1981 be reviewed by Region II welding inspectors.
The safety significance of this non-ASME pipe is established by section 1.8 of the Harris FSAR, which commits to Regulatory Guide 1.143. The Guide identified the radioactive waste management systems as an activity important to safety and requires inspection in accordance with ANSI B31.1.
CP&L procedure NDEP-601, Revision 0, conforms with the requirements of ANSI B31.1 and is the procedure used by CP&L for visual inspection of the Waste Processing System.
The following non-ASME welds were re-examined by the inspector.
WELD JOINT NO.
SYSTEM DATED INSPECTED
- 1-WL-641-FW-2353 Waste Processing 9-09-81
- 1-WL-642-FW-2368 Waste Processing 7-18-81 1-WL-364-FW-1857 Waste Processing 6-27-81 1-WL-324-FW-1856 Waste Processing 6-27-81 1-WL-365-FW-1846 Waste Processing
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1-WL-365-FW-1848 Waste Processing 6-27-31 1-WL-608-FW-2305 Waste Processing 8-11-81 1-WL-646-FW-2364 Waste Processing 7-21-81 1-WL-644-FW-2370 Waste Processing 8-11-81 1-2-WL-142-FW-1319 Waste Processing 8-18-81
- 1-2-WL-142-FW-1318 Waste Processing Inspection Sticker had been removed 1-WL-717-FW-4016 Waste Processing 7-28-81 1-WL-717-FW-4017 Waste Processing 7-23-81 1-WL-679-FW-4051 Waste Processing 7-22-81 1-WL-717-FW-4015 Waste Processing 7-22-81 1-2-WL-143-FW-1316 Waste Processing 8-24-81
- NOTE: This joint was unacceptable Discrepancies noted as a result of NRC reinspection were as follows:
(a) Butt weld joint #'s 1-WL-641-FW-2353 and 1-WL-642-FW-2358 had insuf-ficient weld metal deposited on the external surface of the weld prep resulting in areas of external weld concavity.
(b) Weld joint #1-2-WL-142-FW-1318 had two arc strikes. One of the arc strikes resulted in a pit in the base metal which had not been grcund or liquid penetrant inspected.
The discrepancies noted above were reported as a violation of 10 CFR 50 Appendix B, Criterion V and assigned number 50-400, 401/82-06-01, " Failure to Follow Visual Procedure (NDEP-601) for Visual Examination of Pipe Welds."
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As a result of the above reinspections by Region II, the licensee committed to reinspect all non-ASME pipe weld joints inspected by the welding inspec-tor in question and submit a list of their findings to NRC.
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