IR 05000295/1980015
| ML19343A476 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/05/1980 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19343A470 | List: |
| References | |
| 50-295-80-15, 50-304-80-15, NUDOCS 8009180021 | |
| Download: ML19343A476 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-295/80-15; 50-304/80-15 Docket No. 50-295; 50-304 License Nos. DPR-39; DPR-48 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
Zion Station, Units 1 and 2 Inspection At:
Zion Site, Zion, IL Inspection Conducted: July 22, 1980
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Approved By:
D. H. Dani 1 son, Chief 5/
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Inspection Summary Inspection on July 22, 1980 (Report No. 50-295/80-15; 50-304/80-15)
Areas Inspected: Review of specifications and procedures, observation of work, and review of documentation for installation of spent fuel storage racks; followup on IE Bulletin 80-08 " Examination of Containment Liner Penetration Welds." The inspection involved a total of eight inspector-hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted
.Commonwealta Edison Company (CECO)
- K. L. Graesser, Plant Superintendent
- B. Shannon, ISI Coordinator C. Solich, Assistant ISI Coordinator P. Grazzle, QC Supervisor R. Rostkowski, QA Supervisor D. Waldon, Fuel Handling Foreman K. Kovar, Technical Staff Other personnel were also contacted during the coarse of this inspection.
- Denotes those attending the entrance and exit interview.
Functional or Program Areas Inspected 1.
High Density Spent Fuel Racks The high density spent fuel racks for Zion Units 1 and 2 ordered on Commonwealth Edison purchase order No. 123107 to Nuclear Service Corporation and manufactured by the Lackenby Company and Brooks and Perkins, Inc. have started arriving on site and being installed. The inspector reviewed specifications, observed the installation of two racks, and reviewed manufacturer's documentation as follows:
Specifications Nuclear Service Corporation NSC-3-78-002, Procurement Specification for Spent Fuel Racks for Zion 1 and 2.
Codes and Standards The following codes and standards were used during the manufacture of the racks:
ASME Section II, Material Specification, Part C, Welding Rods, Electrodes, and Filler Material ASME Section III, Nuclear Power Plant Components, Sub-Section NF 3300 ASME Section V, Nondestructive Fxamination, Article 6 ASME Section IX, Welding and Brazing ANSI N45.2.2, Packaging and Shipping-2-
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Materials The following materials were required to be used, by specification, for rack manufacture:
Plate and Sheet - A240 Bar and Shapes - A276 Bolts and Studs - A193 Nuts - A194 Gr. 8 Drawings The following drawings were identified by specification to be used during manufacture:
No. 1000483 Tube Assembly No. 1000484 Tube Cluster Assembly No. 1000485 Base Assembly No. 1000486 Rack Assembly 5' x 7'
No. 1000487 Rack Assembly 5' x 10'
No. 1000488 Rack Assembly 7' x 10'
No. 1000489 Rack Assembly 7' x 11'
No. 1000490 Rack Assembly 10' x 10'
No. 1000491 Rack Assembly 10' x 11'
No. 1000493 Lifting Lug No. 1000494 Lifting Lug No. 1000502 Manufacturing Tube Specification Drawing No. 1000510 Dummy Fuel Assembly
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Spent Fuel Racks The following racks, supplied by the Lackenby Company, were installed in the spent fuel pool during this ir pection:
Rack No. 1, S/N-NSC-1000-490-1/1, 100 cells Rack No. 2, S/N-NSC-1000-490-1/2, 200 cells Rack No. 3, S/N-NSC-1000-491-1/1, 110 cells Rack No. 4, S/N-NSC-1000-491-1/2, 110 cells No items of noncompliance or deviations were identified.
2.
Documentation Review The following documentation from Brooks and Perkins (BP) and Lackenby Company, including personnel certifications, procedures, material certification and inspection reports were reviewed by the inspector:
Procedures:
BP-9023, QAP, Liquid Penetrant BP-10033, QAP, Inspection Procedure for Spent Fuel Storage Tubes BP-10032, QAP, Spent Fuel Storage Tube Envelope Inspection Procedure-3-
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6738-P6, Internal Procedures for Customer Supplied B&P Fuel Cell Tubes
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6738-P7, Lifting Rig Load Test Procedure 6738-P8, Interpretation of Minimum Weld Visual Standards 6738-P3, Weld Identification Procedure 1002-6738, Weld Repair Procedure 603.0, Cleaning Procedure, Stainless Steel and Aluminum 6738-P4, Rack Mandrel Test Procedure 606.0, Packaging and Shipping Procedure 6738-P-10, Rack Dimensional Verification Procedure QCP-10
.3, Vidual Identification for Fuel Storage Racks 1001-6738, Weld Material Control Procedure 6738-P-1, Cleaning Procedure 6738-P-9, Cell Cluster Mandrel Test Procedure QCP-9.2, Magnetic Particle Inspection 6738-P-5, Fabrication Procedure Welding Procedures WPS-1034 PQR-1008 WPS-1035 PQR-1009 WFS-1036 PQR-1010 WPS-1029 PQR-1026 WPS-1030 PQR-1003 WPS-1032 PQR-1006 WPS-101 PQR-01-043 WPS-102 PQR-01-043 WPS-111 PQR-00-01-08 WPS-201 PQR-02-027-044-052 WPS-511 PQR-01-05-08
WPS-602 PQR-06-205 Personnel Certifications The following inspection and welder certifications were reviewed by che inspector:
PT MT VT R. Johnson II II II D. Almos II II II E. Chines (BP)
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L. Lillibridge (BP)
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A.J. Schiller (BP)
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H. Harman (BP)
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J. Krzywiecki (BP)
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J. Masters (BP)
III W. Barnes (BP)
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M. Watson (BP)
III H. Stinson (BP)
I N. Brooks (BP)
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W' elder Certifications
W. Dudek Stamp No. V-13 W. Munson
" " V-9 R. Selex
" " V-28 K. Herman
" " V-22 R. McMahon
" " V-36 Material Certifications 304 s/s Sheet, Heat No. F81704 304 s/s Sheet, Heat No. F81685 304 s/s Sheet, Heat No. F81701 304 s/s Sheet, Heat No. F90297 304 s/s Sheet, Heat No. F90263 304 s/s Sheet, Heat No. F90272 Welding Materials Certifications ER-308L, Heat No. 90621C, 1/16" ER-308L, Heat No. 90632C, 1/16" ER-308L, Heat No. 04328, 1/16" 308, Heat No. 94271,.045" 308, Heat No. X1850iC,.045" No items of noncompliance or deviations were identified.
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During this inspection the inspector conducted a follow-up on the licensee's response to the bulletin by reviewing a sampling of radiographs of containment penetration welds which indicated that backing bars say have been used in these welds during construction, rather than cons eable inserts or open butt welds as stated in the response.
Radiographs of all penetration welds reviewed by the inspector utilized a backing bar.
Some repairs were required to remove nonfusion, excessive porosity, and slag inclusions.
The following radiographs of welds were reviewed:
No. P-14, 10", Waste Gas Line 2WG-061-2RC-165-2SA025 No. P-51, 42", Containment Purge Air Inlet No. P-17, 28", RHR-2RH015 No. P7, 50", Main Steam, 2MS003 No. 2P48, 28", Cervice Water to Vent Coolers 2SW010 No. 2P14, 10", Wacte Gas RCSA, A35-5-
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During a phone conversation with the RIII office, the licensee committed to perform a complete rereview of flued head penetrations and submit a report to the RIII office on August 15, 1980. This is an unresolved item pending the licensee's review and report.
(295/80-15-01; 304/80-15-01).
Unresolved Items An unresolved item is a matter about which more information is required in order to ascertain whether it is an acceptable item, an item of noncompliance, or a deviation. An unresolved item disclosed during the inspection is discussed in paragraph 3.
Exit Interview The inspector met with licensee personnel (denoted in Persons Contacted paragraph) at the conclusion of the inspection on July 22, 1980. The inspector summarized the scope and findings of the inspection.
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