IR 05000413/1979023
| ML19305B951 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/17/1980 |
| From: | Herdt A, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305B934 | List: |
| References | |
| 50-413-79-23, 50-414-79-23, NUDOCS 8003250388 | |
| Download: ML19305B951 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W., SUITE 3100 V
ATLANTA, GEORGIA 30303 o
JAN 181980 Report Nos. 50-413/79-23 and 50-414/79-23 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Catawba Nuclear Station Docket Ls. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Catawba Site near Lake Wylie, South Carolina
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p W. P. Kleinsorg,e Date Signed p
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/ /7 [70 A. R.'Herdt, Section Chief, RCES Branch
' Date Signed SUMMARY Inspection on December 17-19, 1979 Areas Inspected
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This routine, unannounced inspection involved 20 inspector-hours onsite in the area of Prerervice Ivispection - Review of program & review of procedures, Material Handling and Welding filler material.
Results e
Of the four areas inspected, no items of noncompliance or deviations were identified in three areas; one item or noncompliance was found in one area. (Infraction -
Failure to establish adegr.te measures f or handling and storage of equipment &
materials - paragraph Sb.)
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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 Construction Engineer J. C. Shropshire, QA Engineer (QAE) Mechanical, Welding
- L. R. Davison, Senior QC Engineer
- H. D. Mason, QAE Civil, Electrical Other licensee employees contacted included ' canstruction craftsmen, 5 tech-nicians, and 2 engineers.
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Other Organizations Hartford Steam Boiler Inspection and Insurance Company J. W. Kaska, Authorized Nuclear Inspector (ANI)
C. F. Toegel, ANI i
Bcbcock and Wilcox Company, NPGD
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C. R. Meredith, Asst. Group Leader F. C. Nichols, Level II Tech
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 19, 1979, with those persons indicated in Paragraph 1 above. The inspector identified the areas inspected and discussed the item of noncompliance. No dissenting comments were received from the licensee.
3.
Licensee Action on Previous I. spection 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 Sc.
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Independent Inspection Effort
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Construction Progress (Units 1 and 2) The inspector conducted a general inspection of the Unit.1 and 2 containments, au dliary building, piping fat rication shop and fuel buildings. to' obsene construction progress and construction activities such as weldir.g, fitting material handling and control, housekeeping and storage, b.
Material Handling and St9 rage
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The inspector, on December 19, 1979, observed two separate piping assemblies (10" & 14" diameter, stainless steel) in the reactor coolant system supported from two cable tray supports on both sides of third loop steam generator in unit I containment. In addition the inspector
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i noted that the 14" assembly was suspended by carbon steel chain with multiple raps in direct contact with the assembly.
The inspector further noted that there was damaged pipe cap on a 10" diameter pipe j
leading to the third loop cold leg. The licensee stated that there i
were no procedures established to prohibit rigging from installed i
equipme'nt and materials.
Failure to establish adequate measures to control handling and storage of equipment and materials is in noncompliance with 10 CFR 50, Appendix
"B" Criterion XIII. This is an infraction and is assigned item no.
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50-413/79-23-01: " Failure to establish adequate measures for handling and storage of Equipment and Materials."
c.
Welding Filler Material Control
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The inspector, on December 18, 1979 observed welding on new fuel i
storage racks. Inspection of the electrodes used for the above welding
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indicated that the electrodes had been reconditioned in a high tempera-ture oven at 725 125F. The inspector noted that the oven was not included in the DPC calibration - program, and further that the DPC calibration program did ' not address measurement accuracy tolerance requirements - for instruments as a criterion for inclusion of that instrument into the calibration program. The licensee indicated that they would:look further into the matter. The inspector stated that above would be an unresolved item and identified as 50-413/79-23-02, 50-414/79-23-01: "High Temperature Oven Calibration".
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6.
Preservice Inspection - Review of Program (Unit 1)
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The applicable Code for preservice and in-service inspection is the ASME B.
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and PV Code Section XI 1974 Edition through summer 1975 Addenda as implemented
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by DPC QA Program. The inspector reviewed the below listed documents to ascertain whether the Preservice Inspection (PSI) Program had been approved J
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by the. licensee and whether adequate QA plans and procedures had been established (written, reviewed, approved and issued) to assure that, organ-ization structure and QA personnel, audits, general QA requirements, work and quality inspection procedures, control of processes, corrective action, document control, examination control and control of examination equipment, quality records, and qualification of personnel were controlled and accom-plished. The following documents were examined:
-a.
The Babcock & Wilcox Co., Nuclear Power Generation Division (B&W - NPGD)
" Quality Assurance Manual For Inservice Inspection" including the following Quality Assurance Policies and Quality Control Procedures:
(1) 9-QA-201
" Quality Assurance Program" Rev 3 dtd 6/6/75 (2) 9-(1-202
" Organization" Rev 6 dtd 6/9/75 (3) 9-QA-204
" Instructions, Procedures and Drawings" Rev 1 dtd 7/29/74 (4) 9-QA-205
" Document Control" Rev 3 dtd 6/9/75 (5) 9-QA-208
" Control of Special Processes" Rev 2 dtd 6/9/75 (6) 9-QA-209
" Inspection" Rev 4, dtd 6/9/75 (7) 9-QA-210
" Control of Measuring and Test Equipment"
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Rev 1, dtd 6/10/75
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(8) 9-QA-211
" Inspection, Test and Operating Status" Rev 1, dtd 6/10/75 (9) 9-QA-212
" Nonconforming Items" Rev 2, dtd 10/30/74 (10) 9-QA-213
" Corrective Action" Rev 2, dtd 10/17/74 (11) 9-QA-214
" Quality Assurance Records" Rev 1, dtd 6/11/75 (12) 9-QA-215
" Audits" Rev 2, dtd 6/10/75 i
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(13) QCP-9A-153
" Quality Assurance Audits" Rev 2, dtd 6/10/75 (14) QCP-9A-154
" Qualification of Audit Personnel" Rev 1, dtd 6/10/75 b.
"Preoperational Inspection Manual For Catawba Station Units #1 & 2" including Volume I and the following Inservice Inspection Procedures of Volume III:
(1)
ISI-61 Rev 9
" Administrative Procedure for Control of dtd 4/23/79 Manuals and Reports" (2) ISI-62 Rev 0
" Administrative Procedure for Control of dtd 8/29/74 Documents" (3) ISI-63 Rev 3
" Administrative Procedure for Approval of Manuals and Reports for Base-Line and Inservice Inspection Programs" (4) ISI-64 Rev 11
" Administrative Procedure for Handling dtd 3/27/78 Nondestructive Examination Data for Preoperational or Inservice Exam-inations" (5)
ISI-65 Rev 5
" Administrative Procedure for Use of the dtd 3/22/78 Data Base Line System" In the areas inspected no items of noncompliance or deviations were identified.
7.
Perservice Inspection - Review of Procedures (Unit 1)
The inspector reviewed the preservice inspection procedures indicate. in the following paragraphs to determine whether the procedures were consistent with regulatory requirements and licensee commitments.
See paragraph 6
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above for the applicable code.
B&W procedure No. ISI-270 Rev 4 with field changes 599-1151-03-01-0005 a.
to 0007 inclusive " Wet and Dry Methods of Magnetic Particle Examination of Welcs, Studs, Nuts, Bolts, Washers and Pump Motor Flywheels" was reviewed for technical content in the areas of examinations done by continuous method, particle color contrast, particles suppended in suitable liquid, viewing conditions for fluorescent examination, xamination with sufficient overlap prod spacing, magnetizing current for prod method, current and technique for coil or direct contact, yoke spacing and acceptance criteria.
b.
Duke Power Company (DPC) procedure NDE-10, Rev 4, " General Radiography Procedure" was reviewed for technical content in the areas of material type radiographed, thickness range, type of radiation source, film type, source to film distance, blocking or masking technique, type and
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The below listed procedures were reviewed in conjunction with the B&W c.
and DPC QA Manual as applicable to determine if compilation of records were specified.
(1) B&W ISI-119, Rev. 2
" Ultrasonic Examination of Stainless Steel and Nickel Base Alloy Weld Scams" ISI-120, Rev. 7
" Ultrasonic Examination of Class 1 and 2 Piping Welds Joining Similar and Dissimilar
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Materials" i
ISI-240, Rev. -
" Penetrant Examination of Weld and Base Materials including Studs, Nuts and Washers" ISI-270, Rev. 4
" Wet or Dry Methods of Magnetic Particle Examination of Welds, Studs, Nuts, Bolts, Washers and Pump Motor Flywheels" (2) DPC
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NDE-10 Rev 4
" General Radiography Procedure" In the areas inspected, no items of noncompliance or deviations were identi-fled.
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