IR 05000254/1979019
| ML19253B459 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/04/1979 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19253B455 | List: |
| References | |
| 50-254-79-19, 50-265-79-16, NUDOCS 7910160210 | |
| Download: ML19253B459 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/79-19; 50-265/79-16 Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 L censee:
Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 & 2 Inspection At: Quad-Cities Site, Cordova, Illinois Inspection Conducted: July 25 and August 24, 1979 b
fA 9,/tf,[7f Inspector:
K. D. Ward
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f/M/7f Approved By:
D. H. Danielson, Chief
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Engineering Support Section 2 Inspection Summary Inspection on July 25 and August 24, 1979 (Report No. 50-254/79-19; 50-265/79-16)
Areas Inspected: Torus support modification QA/QC program impleutenting procedures, observation of welding, and review and evaluation of welding and nondestructive examination (NDE) data and reports. This inspection involved 14 onsite inspection hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted Commonwealth Edison Company (CECO)
- N. Kalivianakis, Station Superintendent
- D. Thayer, Senior QA Inspector
- R. Gamperl, QA Inspector
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- T. Warner, QC Inspector
- J. Ford, QC Inspector
- D. Huizenga, QC Inspector
- J. Vahrenwald, Special Projects Group W. Burkamper, QC Supervisor Graver Energy Service Incorporated (GESI)
E. White, Sr. QA Engineer The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview.
Functiona.
.r Program Areas Inspected 1.
Torus Support Modification a.
General The torus support modification is to be designed as a Class MC component support in accordance with the requirements of Subsection NF of the ASME Code,Section III, 1977 Edition, Summer 1977 Addenda. Additionally, the Design Specification requires that the region of attachment of the saddle support to the suppression chamber shell shall meet the requirements of Subsection NE of the ASMF Code,Section III, 1977 Edition, Summer 1977 Addenda.
The suppression chamber support modification consists of the addition of a steel saddle which spans the region under the torus between each of the sixteen pairs of existing suppression chamber columns. The saddle is a welded plate assembly, and attaches to both the columns and to the torus shell. Each saddle assetbly consists of a saddle web, saddle flange, stiffener plates, two base plates with lubricated bearing plates and anchor bolts.
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The design report and specification for suppression chamber support modification was prepared by NUTECH for Commonwealth Edison Company.
The support external modification will provide a substantial increase in ?.he capacity of the torus support system to accept loads generated by LOCA/SRV hydrodynamic behavior in the suppression pool. Modification stated June 1979 and will be completed approximately November 1980 for both units.
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To date Ceco has not received a written approval for the torus modification, CECO submitted a current schedule for implementa-tion of the modificat' ion May 11, 1979, to the Director, Division of Operating Reactors, US NRC, Washington, D. C.
Danlee (Protective Coating Applicators) were contracted to remove the previously applied coatings from the torus support saddle project.
Graver was hired to perform the external modification for both units.
The ANII arrives at the site once a week for surveillance and review of data and rc,.rts.
b.
Observation of Welding Welders are certified to the ASME Section IX, 1977 Edition, Summer 1977 Addenda.
The inspector observed the welder using the butterbead-temper-bead technique on the torus.
Butterbead-temperbead welders are trained ano demonstrate their qualifications on mockups. These mockups simulate the position, accessibility and working conditions (including al'. prote_ctive clothing, masks, etc.) of the actual work.
The mockups were also observed by the inspector.
The mockups are designed to simulate the most restrictive areas of the torus area in the 3G (vertical) or 4G (overhead) positions.
The welders must successfully demonstrate ability to perform the butterbead-teeperbead in both positions in order to be qualified.
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Procedures / Manuals The following procedures and manuals were reviewed:
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(1) Graver Energy Services Incorporated Preparation Guideline for Preparation of Welder Performance Qualification, QC-WPQ-1, Rev. O, February 16, 1979.
General Practice for Shop and Field Welding, Rev. 1, Apr!
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Field Weld Material Control, QC-WMC-1, Rev. 3, May 15, 1979.
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SMAW for Butterbead-temperbead Welding, QC-SMB-TN, Rev. 1, May 25, 1979.
SMAW for Welding Carbon Steel, QC-SMI-1N, Rev. 4, May 18, 1979.
Repair Procedure for Base and Weld Metal Defects, QC-RP-6, Rev. 2, May 14, 1979.
Coating Application Procedure, CA-12, Rev. 1, April 23, 1979.
Nuclear Quality Assurance Manual, 24-A, Rev. O, February 14, 1979, Shop.
Nuclear Quality Assurance Manual, 53-B, Rev. O, February 14, 1979, (Field) Installation.
Manufacturing Procedure for Handling, Storage and Shipping of Carbon Steel Material, SH-II, Rev. 1, April 19, 1979.
Field Receiving, Handling and Storage, QC-SH-1, Rev. O.
Field Installation Procedure and Sequence, QC-FI-1, Rev.
2, May 1, 1979.
Field Pressure Grouting, QC-PC-1, Rev. 1, June 13, 1979.
Visual Examination, VE-15, Rev. 1, April 5, 1979.
Magnetic Particle Examination (yoke) M1E-15, Rev. 1, Ap r:1 5, 1979.
Quals!!catior and Certification of Nondestructive Examination Personnel, Rev. 5, August 1978, 1975 Edition.
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(2) Danlee Removal of Previously Applied Coatings for Torus Support Saddle Project, 328-76, Rev. 2.
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Personnel Certifications The following Graver personnel certifications were reviewed:
Welder Performance Qualification Test
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Name No.
L. Ingram
G. Custer
J. Ojibway
J. Paltgrove
J. Chavez
J. Gordon
NDE Personnel Certification Name Levels Methods E. White RT-VT II D. Sisson PT-VT-MT II W. Dumke RT I
W. Dumke Vf II e.
Material and Equipment Certifications, Calibrations and Storage (1) The inspector reviewed the following material certifications and toured the s... age area of the wing plate assemblies, stiffners and saddle parts.
Magnaflux Corporation Magnetic Particle materials:
- 1 Gray Power Batch # 79C080
- 8A Red Power Batch # 79A019 Liquid Penetrant Developer - batch # 79D008 Penetrant - batch # 79C066 Cleaner - batch # 79B061 Wing plate assemblies
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Wing plate w/o stiffners Torus support saddle parts 1;::
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(2) The following equipment calibrations were reviewed.
Two yokes, type Y6 Six electrode baking ovens Two rod oven thermometers Five portable rod ovens Two AC/DC tong testers f.
Review of Surveillance, Data Reports and Drawings
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The inspector reviewed CECO surveillance reports of the modification and drawings for as-built with changes to reflect modifications, BA 009 Rev. 3, BA 010 Rev. 3 and BA 001 Rev. 2, appreved by Sargent & Lundy, NUTECH and the CECO Station Nuclear Engineer. The following documents were also reviewed:
Visual (VT) reports of the butter /temperbead welds)
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Weld documentation maps
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Electrode receiving inspection reports.
(On site at this time is one size, 1/8" E7018, HT No. 402T4720 lot No. 5520 MIAD)
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Electrode over bake sheets Welding procedure qualification records
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No items of noncompliance or deviations were identified.
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Independent Inspection a.
Small Leaks in Clean-up System, Unit 2 (R079-7/03L)
A visual examination revealed a small leak at the weld edge in the transition weld between valve 2-1201-146B and pipe 2-1205B-4-A, also a pin hole leak in a pipe-to-pipe weld on the clean-up pump discharge pipe 2-1203-4"A.
The defects were ground out until liquid penetrant examinations failed to reveal any additional unacceptable indications. The areas were then welded and a visual, liquid penetrant, and ultrasonic examination were performed on the final welding which was found to be acceptable.
The inspector reviewed the NDE and welding procedures and reports.
b.
Small Leak in a RHR Heat Exchanger, Unit 1 (R079-17/03L)
A spike on the service water effluent recorder revealed a small
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leak between the RHR water and service water side of the A RHR heat exchanger. The cause of the leak was found to be a crack-6-Ubb
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e in the 1" pipe to flange weld of the bellows assembly. After the repair, visual and liquid penetrant examinations were performed and it,d to be acceptable. The inspector reviewed the NDE and welding procedures and reports.
No items of nonecmpliance or deviations were identified.
Exit Interview The inspector met with site representatives at the conclusion of the inspection and summarized the scope and findings of the inspection. The licensee acknowledged the information.
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