IR 05000329/1979024
| ML19211D098 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 11/14/1979 |
| From: | Danielson D, Lee E K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19211D096 | List: |
| References | |
| 50-329-79-24, 50-330-79-24, NUDOCS 8001160349 | |
| Download: ML19211D098 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-329/79-24; 50-330/79-24 License No. CPPR-81; CPPR-82 Docket No. 50-329; 50-330 Licensee: Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Midland Nuclear Plent, Units 1 and 2 Facility Name:
Inspection At: Midland Site, Midland, MI Inspection Conducted: October 31-November 2, 1979 l7.} b t.
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Approved By:
D. H. Danielson, Chief Engineering Support Section 2 Inspection Summary 50-329/79-24; Inspection on October 31-November 2, 1979 (Report No.
50-330/79-24)
Reactor Coolant Pressure Boundary and Safety Related Areas Inspected:
The inspection involved a total of Piping and welding work activities.
15 inspector-hours by e e NRC inspector.No items of noncompliance or deviatio Results:
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DETAILS Persons Contacted Principal Licensee Employees
- D. D. Balinsky, QA Group Supervisor
- J. L. Corley, Section Head-Inspection, Examination and Test Verification R. Ostrowski, Inspection, Examination and Test Verification K. O. Rafferty, Inspection, Examination and Test Verification
- D. J. Vokal, PMO, Field Staff (Mechanical)
Other Personnel
- R. Shope, QC Supervisor, Babcock and Wilcox Construction Company
- Denotes those present at the exit interview.
Licensee Action on Previously Identified Items (Closed) Deviation (330/78-16-01):
Charpy Impact Testing - The inspector reviewed numerous correspondences between the licensee and his contractor.
It was determined that the impact test values of the pipe material in question met the code requirements and the UT thickness measurements by ITT Grinnell were in error and voided by measurements made by Bechte Power Corporation.
Functional or Program Areas Inspected Reactor Coolant Pressure Boundary Piping - Observation of Work and 1.
Work Activities (Unit 2)
The inspector observed cold bending of Decay Heat Remo No. 1"-2CCA-94.
in accordance with the applicable procedures and drawings and good con-struction practices were adhered to.
No items of noncompliance or deviations were identified.
Reactor Coolant Pressure Boundary Piping - Welding Material Control 2.
(Units 1 and 2)
Review of Documents a.
The inspector reviewed the following documents:
Babcock and Wilcox Construction Company (B & WCC) Procedure No. 9-QPP-118, Revision 1, " Procurement of Weld Filler Material (1)
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B&WCC Procedure No. 9-WG-107, Revision 2, " Storage, Handling (2)
and Issuing of Welding filler Metals."
B&WCC Procedure No. 9-QPP-108, Revision 4, " Receiving (3)
Inspection."
Receiving Inspection Reports and Material Certification (4)
for E8015-C3 electrodes with heat No. 422B8721 and lot 762570 ERNiCr-3 welding rod with heat No.
No. 818-200027; and E7015 electrodes with heat No. 422B8721 and lot No. 818-020924.
It was determined that the above documents met the PSAR, 10 CFR 50, Appendix B and the applicable code requiremen This matter is considered in B&WCC Procedure No. 9-WG-107.
unresolved pending a review of the revised procedure during a subsequent inspection.
(329/79-24-01; 330/79-24-01)
b.
Control of Materials The inspector toured B&WCC welding material issuing station.
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 in accordance with approved procedures.
No items of noncompliance or deviations were identified.
Reactor Coolant Pressure Boundary Piping - Observation of Welding 3.
Activities (Unit 2)
The inspector observed the following welding activities:
Pressure Surge System Weld No. 1 of line No. 2CCA-17.
a.
11 of line No. 2CCA-19.
Makeup and Purification System, Weld No.
b.
Reactor Coolant and Pressure Control System Weld No. 4 of line c.
No. 2CCA-78.
It was determined that (1) work was conducted in accordance with traveler; (2) proper welding materials were used; (3) welding pro-(4) work area was free of weld rod-cedure requirements were met; stubs and (5) phy ical appearance was acceptable.
No items of nonccmpliance or deviations were identified.
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Reactor Coolant Pressure Boundary Piping - Observation of NDE Work 4.
Activities (Unit 2)
The inspector observed liquid penetrant examination of Reactor 4, No. 5 and No. 6 of line Coolant System welds No. 2, No.
No. 2CCA-78; Decay Heat Removal and Core Flooding System, weld No.
of line No. 2CCA-81 and weld No. 6 of line No. 2CCA-83 and Makeup and Purification System weld No. 4 of line No. 2CCA-89. It was(2) procedure
- l) surface condition was acceptable, (3) personnel were properly qualified and (4)
determined that:
requirements were met;three of the welds were rejected by the examiner becaus of rounded indications exceeded the acceptable criteria.
No items of noncompliance or deviations were identified.
Reactor Coolant Pressure Boundary Piping - Weld Heat Treatment 5.
(Unit 1)
Review of Procedures a.
The inspector reviewed B&WCC Procedures N@. 9-HT-101, Revision 2, "Postweld Heat Treatment" and No. 9-HT-102, Rev It was determined that the procedure met the ASME B&PV Code Section III 1971 Edition with Summer 1973 Addenda requirements.
Observation of Work Activities b.
The inspector observed the following Postweld Heat Treatment Activities:
Cooling down of Reactor Coolant System Welds No. J4-1 and (1)
No. J4-3 after holding at the specified temperature range.
Installation of thermocouples and heating coils for the (2)
Reactor Coolant System Welds No. J4-2 and J4-4.
It was determined that work activities were performed in accordance with the applicable procedures and temperature recorders and thermocouples are calibrated and certified.
Review of Records c.
The inspector reviewed the postweld heat treatme It was determined that the records indicated the procedure and code requirements were met.
No items of noncompliance or deviations were identified.
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6.
Reactor Coolant Pressure Boundary Piping - Welder Qualification
(Units 1 and2)
The inspector established that B&WCC procedure for welder a.
qualification has not been revised since the last review (IE Inspection Reports No. 50-329/79-17 and No. 50-339/79-17, paragraph 3).
b.
The inspector reviewed the randomly selected qualification records of seven welders who performed welding on welds stated in paragraphs 3 and 7 of this report.
No items of noncompliance or deviations were identified.
7.
Reactor Coolant Pressure Boundary Piping - Special Welding Applications (Units 1 and 2)
The inspector observed the following repair work activities:
Weld repair of Unit 1 Reactor Coolant System Weld No. J31-2.
a.
b.
Grinding of Unit 2 Decay Heat Removal System Weld No. 7 of line No. 2CCA-18.
It was determined that (1) work was conducted in accordance with traveler; (2) proper materials were used and (3) procedure require-ments were met.
No items of noncompliance or deviations were identified.
8.
Safety Related Piping - Observation of Work and Work Activities (Units 1 and 2)
The inspector toured the Poseyville laydown area.
It was a.
determined that:
(1) spools are identified; (2) spools are resting on dunnage; (3) ends are covered and (4) a 14" schedule 160 stainless steel pipe with heat no. 55009 has a ground out area of approximately 1 1/2" diameter and 3/8" deep. Upon questioning the licensee relative to the cause of the grinding and whether the minimum wall thickness has been violated, the licensee agreed to investigate. This matter is considered unresolved pending a review during a subsequent inspection.
(329/79-24-02)
b.
The inspector observed the alignment of Unit 1, Decay Heat Removal and Core Flooding System, Weld No. 3 on drawing No.
M610, sheet 1.
It was determined that work activities were performed in accordance with the applicable procedures and good construction practices were adhered to.
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No items of noncompliance or deviations were identified.
Safety Related Piping - Observation of Welding Activities (Unit 2)
9.
The inspector observed welding of the Feedwater System Welds No.
It was determined that 26U, No. 21U, No. 21L, No. 22U and No. 22L.
(1) work was conducted in accordance with traveler; (2) proper welding materials were used; (3) welding procedure requirements were (4) work area was free of weld rod-stubs; and (5) physical met; appearance was acceptable.
No items of noncompliance or deviations were identified.
Unresolved Items Unresolved items are matters about which more information is required in liance, order to ascertain whether they are acceptable items, items of noncomp Unresolved items disclosed during the inspection are or deviations.
discussed in paragraphs 2 and 8.
Exit Interview The inspector met with licensee representatives (denoted under Persons The Contacted) at the conclusion of the inspection on November 2, 1979The inspector summarized the purpose and findings of the inspection.
licensee acknowledged the findings reported herein.
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