IR 05000329/1978016
| ML19274D760 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/15/1978 |
| From: | Danielson D, Eric Lee NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19274D754 | List: |
| References | |
| 50-329-78-16, 50-330-78-16, NUDOCS 7902260020 | |
| Download: ML19274D760 (5) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-329/78-16; 50-330/78-16 Docket No. 50-329; 50-330 License No. CPPR-81; CPPR-E2 Licensee:
Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At:
Midland Site, Midland, Michigan Inspection Conducted:
November 13-16, 1978 Inspectors:
E. W.
K. Lee II/' 'N ( i -i r,.
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Approved By:
D. H. Danielson, Chief 0' -
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Engineering Support Section 2 Inspection Summarv Inspection on November l_3-16, 1978 (Report No. 50-329/78-16; 50-330/78-16)
Areas Inspected:
Reactor coolant pressure boundary and safety related piping welding work activities and records; presiously identified non-compliance item.
The inspection involved 24 inspector-hours onsite by one NRC inspector.
Results: Of the seven areas inspected, no apparent items of noncompli-ance or deviations were identified in six areas; one item of deviation was identified in one area (deviated from code - Paragraph 5.a)
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DETAILS Persons Contacted Principal Licensee Employees
- D.
R. Keating, Quality Assurance Group Supervisor
- B. 11. Peck, Construction Supervisor
- K.
O. Rafferty, inspection Evaluation and Test Verification
- R.
G. Wollney, Staff Engineer Other Persannel
- A.
C. Ashwo th, Sr., Inspection Supervisor, Babcock and Wilcox Construction Company (B&WCC)
- W.
L. Barclay, Project Field Quality Control Engineer, Bechtel Power Corporation (Bechtel)
- T.
W.
Davis, Jr., Field Welding Supervisor, B6WCC
- L.
A.
Dreisbach, Project Quality Assurance Engineer, Bechtel
- J. J. Gilmartin, Field Engineer, Bechtel
- J.
E. Russell, Assistant Project Field Quality Control Engineer Eechtel
- Denotes those present at the exit interview.
Licensee Acticas on Previous Inspection Findings (Closed) Noncompliance (330/78-09-02): Purge gas flow rate.
The inspector reviewed Bechtel NCR-1318, Consumers Power Company NCR M-01-4-8-071 and the associated revised procedures and training records.
It was determined that the NCR's were properly closed.
Functional or Prcgram Areas Inspected 1.
Reactor Coolant Pressure Boundary and Safety Related Piping -
Observation of Work Activities (Units 1 and 2)
The inspector toured the Poscyville Laydown area where pipes are stored and the storage area adjacent to warehouse No. 2 where the Unit 1 Reactor Coolant piping are stored.
It was determined that:
(1) spools are identified; (2) spools are resting on dunnage and (3) ends are covered.
No items of noncompliance or deviations were identified.
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2.
Reactor Coolant Pressure Boundarv _ Piping (Weld _i_ng)_ - Observation of Work Activities (Unit 2)
Welding Beyond Root Pass a.
The inspector observed welding of fill passes for the Reactor Coolant System Line No 2-CCA-1, Weld No. WJ6-2.
It wap determined that: (1) applicable welding procedure was used; (2) welders were currently qualified; (3) welding procedure requirements were met; (4) work area is free of weld rod-stubs and (5) physical appearances were acceptable.
b.
Storage and Control of Welding Materials The inspector visited the Babcock and Wilcox Construction Company (B&WCC) welding material issuing location.
It was determined that:
(1) the welding materials are properly identified and segregated; (2) the temperature of the rod ovens is maintained; (3) records are properly kept and (4)
issuance and return of welding materials are controlled.
No items of noncomplance or deviations were identified.
3.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records (Unit 2)
The inspector reviewed.3ME data reports, shop traveler, NDE reports, material certificates and receiving inspection report for the Reactor Coolant System Spool No. 2CCA-15-S602-2-3.
The inspector determined that applicable code requirements were met.
No items of noncompliance or deviations were identified.
4.
Safety Related Piping (Weldi_ng) - Observation of Work Activities (Units 1 and 2)
a.
Joint Preparation and Alignment The inspector observed fit-up of Unit 1 Decay Heat Removal System weld No. 17 on drawing No. M610, Sheet 7 and Unit 2 Auxiliary Feedwater System Weld No. 51 on drawing No. M634, Sheet 5.
It was determined that: (1) weld No. 17 met the-3-
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applicable code and procedure requirements and QC verified the alignment prior to welding; (2) weld No. 51 failed to meet the procedure requirement and was rejected by the Ouality Control Engineer.
b.
Wel_d_ing of Root Pass The inspector observed welding of the root pass on Unit 2 Boron Recovery System weld No. 23 on drawing No. M608 -
Sheet 1.
It was determined that:
(1) proper welding pro-cedure was used; (2) welder was currently qualified and (3)
physical appearance was acceptable.
c.
Welding Beyond Root Pass The inspector observed welding of fill passes on Unit 1 Decay Heat Removal System weld No. 51 on drawing No. M610, Sheet 3.
It was determined that:
(1) applicable welding procedure was used; (2) welder was currently qualified; (3) welding procedure requirements were met; (4) work area was free of weld rod-stubs and (5) physical appearance was acceptable.
d.
Storage and Control of Welding Ma_terials The inspector visited Bechtel's welding material issuing location No. 2.
It was determined that:
(1) The welding materials are properly identified and segregated; (2) the temperature of the rod ovens is maintained; (3) records are properly kept and (4) issuance and return of welding materials are controlled.
No items of noncompliance or deviations were identified.
5.
Saf e_ty Related__Pi_ ping - Review of Quality Records (Units 2)
The inspector reviewed ASME data reports, shop travelers, NDE reports, material certificates, repair records, stress relief charts and receiving inspection reports for the following components:
a.
Main Steam System Spools No. 2ELB-12-S632-3-1, and No. 2ELB-12-5632-3-2.
b.
Reactor Coolant System Spool No. 2ECC-3-S602-3-3A.
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The inspector determined that applicable code requirements were met except the following:
Ladish Company Material Analysis Report with heat No. YS4538, a.
used to fabricate pipe spools No. 2ELB-12-S632-3-1 and No.
2ELB-12-S632-3-2, indicated one V-notch charpy test specimen failed to meet the code requirement.
This item is a deviation identified in Appendix A (50-330/
78-16-01)
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b.
Ultrasonic thickness Examination Report dated May 19, 1978, for spool No. 2ELB-12-S632-3-1 requires clarification relative to:
(1) why the minimum thickness was changed to 2 1/8" from 2 3/8" and (2) location where measurement was taken.
This item is considered unresolved.
(50-330/78-16-02)
Except as noted, no items of noncompliance or deviations were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompli-ance or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 5.b.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on November 16, 1976.
The inspector summarized the scope and findings of the inspection.
The licensee acknowledged the information.
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