IR 05000413/1981027
| ML20039D229 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/09/1981 |
| From: | Bryant J, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039D221 | List: |
| References | |
| 50-413-81-27, 50-414-81-27, IEB-78-07, IEB-78-7, IEB-79-08, IEB-79-12, IEB-79-26, IEB-79-8, NUDOCS 8112310441 | |
| Download: ML20039D229 (4) | |
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NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST N.W SUITE 3100 o,%.
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ATLANTA, GEORGIA 30303
Report Nos. 50-413/81-27 and 50-414/81-27 Licensee: Duke Power Company 422 South Church Street
- Charlotte, NC 28242 Facility Name: Catawba Docket Nos. 50-413 and 50-414
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License Nos. CPPR-116 and CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector:
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Date Signed Approved by:
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r uza 9. 'Bryalift'ection Chief, Division of Date Signed sident and Reactor Project Inspection SUtit1ARY Inspection on October 26 - November 25, 1981 Areas Inspected This routine, announced insp*ction involved 152 inspector-hours on site in the areas of reactor coolant pressure boundary piping (welding) - observation of work and work activities (Unit 1); safety-related piping - observation of work and work activities (Unit 1); followup of NRC identified items (Units 1 and 2);
followup of IE Circulars and IE Bulletins (Units 1 and 2); and evaluation of operational review (Unit 1).
Resul ts Of the five areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees W. O. Parker, Vice President Steam Production L. C. Dail, Vice President Design Engineering R. L. Dick, Vice President Construction J. C. Rogers, Project Manager J. W. Hampton, Station Manager J. R. Welle, Corporate QA Manager
- S. W. Dressler, Senior Construction Engineer
- R. A. florgan, Project QA Engineer
$1 C, Shropshire, QA Engineer Supervisor
- H. D. Mason, QA Engineer Supervisor J. E. Cavender, Level III Supervisor R. C. Futrell, Director NSRB H. L. Atkins, QA Engineer R. O. Sharpe, Licensing Engineer D. H. Llewellyn, Welding Engineer D. E. Gadd, Welding Engineer Other Organizations Hartford Steam Boiler Inspection and Insurance Company J. W. Koske, Authorized Nuclear Inspector
- C. F. Toegel, Authorized Nuclear Inspector B. Wood, Authorized Nuclear Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 25, 1981, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation (414/81-02-02):
Inadequate evaluation of generic deficiencies for reportability. Licensee actions concerning this item have included clarification of procedures, retraining of appropriate personnel, review of ncnconforming item reports (NCI's) for items reportable per 10 CFR 50.55(e) or 10 CFR 21 and reporting of those items deemed reportable to NRC. The inspector verified these actions
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except retraining.
Verification of training was' previously performed (see NRC report 50-413,414/81-18). This item is closed. However,
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further followup inspection will be perfomed concerning evaluation of NCI's since additional NRC items have been identified in this area (see NRC reports 50-413, 414/81-14 and 81-24).
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(Closed) Violation (413/81-02-02, 414/81-02-04): Apparent generic items or trends not recognized nor forwarded to management. Licensee actions concerning this item have included retraining of personnel, review of previously issued NCI's, evaluation of reportable deficiencies as to their effect on the Duke ficGuire facility, and evaluation / clarification of NCI's as necessary. The inspector verified these actions, except retraining which was verified previously (see NRC report 50-413,414/81-18).
Although this item is closed, further followup inspection will be performed concerning evaluation of NCI's as denoted in paragraph 3.a. above.
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(Closed) Violation (413/81-02-04):
Incomplete QA documentation.
Licensee actions concerning this item have included retraining, review of previously issued NCI's, and clarification of NCI's as necessary.
The inspector verified these actions. Although this item is closed, further followup inspection concerning NCI's will be perfomed as denoted in paragraph 3.a. above.
d.
(Closed) Violation (413, 414/81-08-03):
Failure to control storage and protection of flow sections to prevent deterioraton.
Licensee actions concerning this item have been to upgrade storage requirements for flow sections, evaluate improperly stored flow sections not yet installed, and evaluate installed flow sections. The inspector verified these actions including observation of installed flow section nos.1-RN-FE-
-8600,1-RN-FE-8630,1-RN-FE-8580, and 1-RN-FE-8590 Licensee actions are considered satisfactory.
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(0 pen) Unresolved Item (413, 414/81-24-01):
Verification of appro-priate corrective action for nonconfonning items.
The inspector participated in the followup inspection performed by another NRC:RII inspector (see NRC report 50-413,414/81-26).
No violations or deviations were identified.
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Unresolved Items Unresolved items were not identified during this inspection.
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Independent Inspection Effort (Units 1 and 2)
The inspector conducted general inspections of site work and work activities and observed equipment protection / storage and housekeeping in the auxiliary building, containmnt buildings, pipe fabrication shop and storage areas.
No v1olations or deviations were identifie _ _ _ - _ _ _ _ _ __ ____________ _ _ - ___.
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Safety Evaluation Report (Unit 1)
U The inspector performed an evaluation of the licensee concerning section 13.4, " Operational Review" of the Final Safety Analysis Report (FSAR)..This inspection included discussions with licensee management and detailed review of the FSAR and supporting documentation. Additional documentation of this inspection will be -via the NRC Safety Evaluation Report to be issued later.
No violations or deviations were identified.
7.
Followup of IE Bulletins and Circulars (Units 1 and 2)
The inspector reviewed NRC listed IE Bulletins and Circulars and licensee actions concerning these documents.
The following Bulletins and Circulars will be closed since they are not applicable to the Catawba site:
IE Bulletins:
78-07, 79-08, 79-12, and 79-26 IE Circulars: 78-15, 79-08, 79-21, 80-07, 80-12, and 80-17 8.
Safety-Related Piping - Observation of Work and Work Activities (Unit 1)
The inspector observed a portion of piping system flush no. INV1 fo" conformance to procedure (CD-286) requirement. The inspection observed flushing in progress, in process documentation, water _ sampling and testing of water samples.
No violations or deviations were identified.
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Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities (Unit 1)
The applicable code for installation of reactor. coolant pressure boundary piping is the ASME Boiler and Pressure Vessel Code,Section III, 1974 Edition plus addenda through summer 1975. The inspector observed in process
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weld no.1HI236-10 and reviewed records for conformance te code and procedure requirements in the areas of documentation of pertinent informa-tion and QC signoffs via a weld traveler, availability of pertinent instructions, use of appropriate qualified welding procedure, provisions for weld repair provided, certification of ' filler material, control of welding
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parameters, verification of welder qualification, use of'soecified shielding and purce gas, condition of welding equipment, provisions for voltage and-amperage checks, verification of proper fitup, control of preheat and-interpass temperature, condition of weld and base metal surfaces, and verification that appropriate inspections were being performed.
I No violations or deviations were identified.
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