IR 05000413/1979002
| ML19261C821 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/07/1979 |
| From: | Conlon T, Crowley B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19261C819 | List: |
| References | |
| 50-413-79-02, 50-413-79-2, 50-414-79-02, 50-414-79-2, NUDOCS 7904100514 | |
| Download: ML19261C821 (7) | |
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UNITED STATES
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101 M ARIETTA STREET, N.W.
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Report Nos.
50-413/79-02 and 50-414/79-02 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 Inspection at:
Lake Wylie, South Carolina 7/7f Inspector:
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B. R. Crowley, Metallurg'ical Engineer
'Date Signed Approved by:
W J _7 y_
T. E. Conlon, Section Chief, RCES Branch ate Signbd SUMMARY Inspection on February 6-9, 1979 Areas Inspected This routine unannounced inspection involved 26 inspector hours onsite in the areas of reactor coolant pressure boundary piping, safety related piping, and general construction activities including housekeeping.
Results Of the three areas inspected, no apparent items of noncompliance or deviations were identified.
7904100514
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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
- S. W. Dressler, Senior Technical Support Engineer
- J. E. Beall, Engineering Specialist-Licensing
- C. L. Ray, Design Engineer
- H. D. Mason, QA Engineer S. W. Hamrick, Technical Support-Welding R. G. Rouse, QA Technician R. P. Ruth, QA Engineer J. C. Shropshire, QA Engineer D. A. Jenkins, QA Technician C. R. Baldwin, QC Technical Supervisor, Welding and NDE R. D. Blackwelder, QA Film Reviewer T. D. Mills, Construction Engineer, Mechanical D. Gadd, Technical Suoport - Welding 2.
Exit Interview The inspection scope and findings were summarized on February 9, 1979 with those persons indicated in Paragraph I above.
The inspection included reactor coolant pressure boundary piping, safety related piping, and general construction activities. The unresolved item of paragraph 9 was discussed.
The licensee agreed to complete a records search to dete rmine if any welders had welded without meeting the qualification maintenance requirements of ASME Section IX.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in paragraph.
-2-5.
Independent Inspection Effort The inspector made a walk-through inspection of Unit I and 2 reactor buildings and Unit 1 auxiliary building and observed housekeeping and general construction activities.
The inspector noted that in general, construction debris had been allowed to accumulate in the Unit I reactor building thus creating poor house-keeping conditions. This was pointed out to the licensee and immediate corrective action was initiated.
Within the areas inspected, no item of noncompliance or deviations were identified.
6.
Reactor Coolant Pressure Boundary Piping (Welding I) - Observation of Work and Work Activities (Unit 1)
The inspector observed field welding of reactor coolant pressure boundary piping at various stages of weld completion. The applicable Code for reactor Coolant pressure boundary piping is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, 1974 Edition with Addenda through the summer of 1974 as implemented by the Duke Power Company (DPC) QA procedure manual and DPC specification CNS-1206.00-2.2,
" Specification for the Procurement of Power Piping Systems, Material and Components".
a.
The inspector examined weld fneints of pipe to pipe / fitting (PPF)
and pipe to component (PC) where welding was beyond the root pass to determine; weld identification proper, use of applicable weld procedure, welder qualified, preheat and inte rpass temperature controlled, use of specified weld material, use of specified purge, physical appearance of weld (e.g.,
starts, stops, undercut and surface imperfections), and evidence of periodic welding variable s
ctecks.
Joint Number Size Isometric System INC24-5 31" CN-INC-24 Reactor Coolant INC24-6 31" CN-INC-24 Reactor Coolant INC164-7 10" CN-INC-164 Safety Injection INC164-8 10" CN-INC-164 Safety Injection b.
Work areas were observed for the presence of uncontrolled weld material and to dete rmine if a sufficient number of QA and QC personnel were present at the work site.
Within the areas inspected, no items of noncompliance or deviations were identifie.
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-3-7.
Reactor Coolant Pressure Boundary Piping - Review of Quality Assurance implementing Procedures (Units 1 and 2)
The inspector reviewed the quality assurance implementing procedures for control of reactor coolant pressure boundary piping to assure that insulation activities are performed according to NRC requirements and SAR commitments.
Within the procedures reviewed, no items of noncompliance or deviations were iientified.
8.
Reactor Coolant Pressure Bouudary Piping (I) - Observation of Work and Work Activities (Unit 1)
The inspector observed non-welding work activities for reactor coolant pressure boundary (RCPB) piping. See paragraph 6 above for the applicable code.
Observation of specific work activities were conducted to determine confo rmance, where applicable, with the following; inspection and/or work procedures, record keeping requirements, and installation speci-fication requirements.
Safety Injection System Activity Component Drawing Alignment During Fitup Part "A" and "B" CN-NI-237 Handling During Fitup Part "A" and "B" CN-NI-237 9.
Safety Related Piping (Welding >- Review of Quality Records (Unit 1)
The inspector reviewed the quality records described below relative to safety related pipe welding to determine whether these records reflected work accomplishment consistent with NRC requirements and SAR commitments.
The applicable code for this welding is the ASME Boiler and Pressure Vessel Code,Section III, Subsections NC and ND, 1974 Edition with Addenda through the summer of 1974 as implemented by the DPC QA procedure manual and DPC specification CNS-1206.00-2.2.
a.
The following completed weld records were reviewed in the areas of; visual and dimensional inspections, weld history, preheat and interpass temperature, stress relief, NDE, weld repair, welder qualification, and inspector qualification, es applicable to each weld:
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L-4-Weld Number ISO /Dwg. Number System INC2-1 CN-INC-2 Reactor Coolant INC4-1 CN-INC-4 Reactor Coolant INV71-1 CN-INV-71 Chemical Volume & Control INV71-5 CN-INV-71 Chemical Volume & Control INS 27-1 CN-INS-27 Containment Spray INS 27-11 CN-INS-27 Containment Spray IKC12-1 CN-IKC-12 Component Cooling IKC12-13 CN-IKC-12 Component Cooling IFW14-7 CN-1FW-14 Refueling Water 1FW14-10 CN-1FW-14 Refueling Water b.
The following welding material records relative to; receipt inspection, weld material certification and issue and storage control, were reviewed:
(1)
P-1A,
" Receiving Inspection Information Report" forms for welding material used to weld above listed welds.
(2) Available H-3B, " Weld naterial Issue Slip" forms for material used fcc above welds.
(Note - The H-3B form is not kept as a
.ecord after the information is transferred to the pe rmanent
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M-4A form. )
(3) A sample of H-3C, " Oven Temperature Verification" forms dated 9/1/77 - 12/31/77 and 5/1/78 - 8/3/78.
c.
During review of the above weld records, the following problems were noted.
(1) Review of welder qualification maintenance records (Weld History Computer Printout) for weld INC4-1, drawing CN-INC-4, revealed that welder H-39 had been updated on the SMA process 4 times since his employment had terminated on 10/20/77.
Further investigation revealed that he was automa;ically updated.f rom M-19A forms (weld record for containment plate and tank erection) for welds which he had started prior to his te rmina t ion. The revision of M-19A in effect at the time did not provide an actual weld date.
The date used for updating the welder was the date the final weld was inspected. Where a weld is finished months after the start date (in this case 8 months), this practice could allow a welder's qualification to lapse by the rules of Section IX to the ASME Code and yet maintenance records show his qualification to be valid. This situation cannot occur presently as a new revision to M-19A is in effect which provides the actual date the welder welded.
However, there was a period of time when the old revision of
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-5-M-19A was in effect that a welder's qualification could have lapsed and the welder still be allowed to weld.
For the records reviewed during this inspection, there was no case where a welder's qualification had lapsed because of this problem. The licensee initiated a records search to determine if any welder had been allowed to weld without meeting the maintenance qualification rules of Section IX to the ASME Code.
This item is considered unresolved pending the outcome of the licensee's record search and is identified as item number 413/414/79-02-01.
(2) During review of radiographic (RT) film, the inspector noted a questionable indication in view 1-2 of joint IFW14-7, drawing CN-lFW-14. The licensee decided to re-radiograph the indication for further evaluation.
The additional radiograph indicated that the indication was marginally acceptable. lioweve r, due to the marginally acceptable condition, the licensee decided to repair the indication.
Within the areas inspected, no items of noncompliante or deviations were identified.
10.
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 9. above for the applicable code.
a.
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. The following weld joints were e'xamined:
Joint Number Isometric System 1RN27-1 CN-lRN-27 Service Water b.
The inspector examined weld wints where the root pass (only) has been completed to determine; w rld identification, use of specified procedures, qualified welder, physical appearance of weld and evidence of QC verification.
The following weld joints were examined:
Joint Number Isometric System IRN27-1 CN-lRN-27 Service Water
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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 identification, qualified welder, use of specified 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 Isometric System IFV30-3 PPF CN-1FW-30 Refueling Water d.
Work areas were examined for the presence of uncontrolled welding material.
Within the areas inspected, no items of noncompliance or deviations were identified.
11.
Safety Related Piping - Observation of Work and Work Activities The inspector observed non-welding work activities for safety related (SR) piping. See paragraph 9. above for the applicable code.
Observation of specific work activities were conducted to determine conformance, where applicable, with the following; inspection and/or work procedures, recordkeeping, installation specifications or plans, and qualified inspection personnel.
Activity System or Component Drawing Handling During Fitup Part "C" CN-l?,N-324 Cutting Weld Prep Part "A" CN-lRN-147 Within the areas examined, there were no items of noncompliance or deviations identified.