IR 05000329/1978009
| ML20058A196 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 09/21/1978 |
| From: | Danielson D, Eric Lee NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20058A189 | List: |
| References | |
| 050-330-78-09, 50-329-78-09, 50-329-78-9, 50-330-78-9, NUDOCS 7811130350 | |
| Download: ML20058A196 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-329/78-09; 50-330/78-09 Docket No. 50-329; 50-330 License No. CPPR-81; CPPR-82
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Licensee: Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At: Midland Site, Midland, MI
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Inspection Conducted: August 29-31, 1978 t
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Inspector:
E. W. K. Lee I'/.h Z[
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Approved By:
D. H. Danielson, Chief M(
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Engineering Support Section 2
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Inspection Summary Inspection on August 29-31, 1978 (Report No. 50-329/78-09; 50-330/78-09)
Areas Inspected: Reactor Coolant Pressure Boundary and Safety Related Piping and Welding quality assurance manual, procedures and work activ-ities. The inspection involved 20 inspector-hours onsite by one NRC inspector.
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Results: Of the seven areas incpected, no apparent items of noncom-pliance or oeviations were identified in siv areas; one apparent item of noncompliance was identified in one area 'b fraction - failure to follow procedure - Paragraph 5.a).
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I DETAILS
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Persons Contacted Principal Licensee Employees I
- T. C. Cook, Project Superintendent l
- J. L. Corley, Section Head, Inspection Evaluation and Test Verification
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W. Dickson, QA Engineer
- D. R. Keating, QA Engineer R. L. Southam, QA Engineer Other Personnel J. Barbee, Lead Welding Engineer, Bechtel Power Corporation
- W. L. Barclay, Project Field Quality Control Engineer, Bechtel Power Corporation
- L. A. Dreisbach, Project Quality Assurance Engineer, Bechtel Power Corporation
- J. F. Newgen, Project Superintendent, Bechtel Power Corporation R. Ward, Lead Mechanical Engineer. Bechtel Power Corporation
- R. Shope, Quality Control Supervisor, Babcock and Wilcox Construction Company
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- Denotes those present at the exit interview.
Other personnel of the licensee and his contractor were contacted during the course of the inspection.
Functional or Program Areas Inspected 1.
Reactor Coolant Pressure Boundary and Safety Related Piping -
Review of QA Procedures (Units 1 and 2)
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The inspector reviewed three Bechtel Power Corporation (Bechtel)
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Technical Specifications, eleven procedures and fifteen Babcock and Wilcox Construction Company (B&WCC) procedures relative to Reactor Coolant Pressure Boundary and Safety Related Piping work activities. The procedures reviewed included procurement documents; requirements and control; receiving inspection; identification; handling; storage; shipping and preservation; cleanliness control; erection and installation; hydrostatic testing; cold spring; gener-ation and record keeping. The inspector determined that the pro-cedures met the PSAR commitments, QA Manual,10 CFR 50, Appendix B and the applicable code requirements.
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No items of noncompliance or deviations were identified.
2.
Reactor Coolant Pressure Beundary and Safety Related Piping (Welding) - Review of QA Procedures (Units 1 and 2)
The inspector reviewed twelve Bechtel procedures and eighteen B&WCC procedures related to welding of Reactor Coolant Pressure Boundary and Safety Related Piping. The procedures reviewed included control of weld data sheets including hold points; qualification of welding procedures, welders, NDE and inspection personnel; calibration of equipment; control of preheat and interpass temperatures, post weld heat treating; repair of defects and control of welding materials. The inspector determined that the procedures met PSAR commitments, QA manual,10 CFR 50, Appendix B and the applicable code requirements.
No items of noncompliance or deviations were identified.
3.
Reactor Coolant Pressure Boundary (Welding) - Observation of Work (
and Work Activities (Unit 2)
The inspector observed fit-up of Unit 2 Decay Heat Removal System Line No. 2CCA-21, weld No. 19.
It was determined that the joint alignment met the applicable code requirements and QC had verified
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the alignment prior to welding.
No items of noncompliance or deviations were identified.
4.
Safety Related Piping - Observation of Work and Work Activities (Units 1 and 2)
The inspect.or observed the following safety related piping work activities:
a.
Weld end preparation of Unit 2 Decay Heat Removal System welds No. 12 and No. 13 on drawing No. M611, sheet 7.
b.
Rigging of Unit 1 Decay Heat Remcval System spool No.
1FCB-22-610-7-ll.
The inspector determined that work activities were performed in accordance with the applicable procedures except the support of the "come-along" for lifting item b above. The inspector noted that item b was lifted by a "come-along" supported from spool No.
OHBC-50-5-617.7.3.
Upon questioning the licensee relative to
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the criteria of lif ting a pipe spool sup' ported from another, the
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inspector was informed that there was none. However, the licensee has the same concern and a nonconformance report has been initiated for a similar situation. The inspector stated that this matter is considered unresolved pending a review of the resolution of the nonconformance report during a subsequent inspection.
(50-329/
78-09-01; 50-330/78-09-01)
No items of noncompliance or deviations were identified.
5.
Safety Related Piping (Wciding) - Observation of Work and Work Activities (Units 1 and 2)
a.
Welding of Root Pass The inspector observed welding of root paks-bf Unit 2 Fuel Pool Cooling System Weld No. 16 on drawing No. M617, sheet 11
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and Unit 2 Decay Heat Removal System Weld No. 38 on drawing l
No. M611, sheet 5.
It was determined that:
(1) proper welding procedures were used, (2) welders were currently qualified. (3) physical appearances were acceptable and (4)
backing gas used in welding root pass of tield No. 38 on j
drawing No. M611, sheet 5 was 45 CFH instead of 10-15 CFH
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as required by welding procedure No. P8-AT-Ag, Rev. 1.
Item 4 is an item of noncompliance identified in Appendix A.
(50-330/78-09-02)
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Welding Beyond Root Pass
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The inspector observed welding of Unit 1 Reactor Building
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Spray System Weld No. 21 on drawing No. M612, sheet 3.
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was determined that:
(1) applicable welding procedure was used, (2) welder was currently qualified, (3) welding pro-cedure requirements were met and (4) work area was free of weld rod-stubs.
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c.
NDE of Weld The inspector observed liquid penetrant examination of Unit 2 Service Water System Weld No. 16 on drawing No M619, sheet 3.
It was determined that:
(1) surface condition was acceptable.
(2) procedure requirements were met and (3) personnel were properly qualified.
Except as noted, no items of noncompliance or deviations were identified.
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i Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-
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pliance or deviations. An unresolved item disclosed during the inspection i
is discussed in Paragraph 4.
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Exit Interview The inspector met with licensee representatives (denoted under Persons
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Contacted) at the conclusion of the inspection on August 31, 1978.,The inspector summarized the scope and findings of the inspection. The j-licensee acknowledged the information.
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