IR 05000454/1980003
| ML19344D700 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/10/1980 |
| From: | Danielson D, Eric Lee NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19344D694 | List: |
| References | |
| 50-454-80-03, 50-454-80-3, 50-455-80-03, 50-455-80-3, NUDOCS 8004280039 | |
| Download: ML19344D700 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report Nos. 545/80-03; 455/80-03
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Docket Nos. 50-454; 50-455 License Nos. CPPR-130; CPPR-131 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name: Byron Nuclear Generating Station, Units 1 and 2 Inspection At: Byron Site, Byron, IL February 20-21, 1980 Corporate Office, Chicago, IL February 27, 1980 Inspection Conducted: February 20-21, and 27, 1980 E. W. K. Le,/. /. $b <--
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Approved By:
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Inspection Summary Inspection on February 20, 21, and 27, 1980 (Report Nos. 50-454/80-03; 50-455/80-03)
Areas Inspected: Reactor Coolant Pressure Boundary Piping work activities, welding and procedures; previously identified un..olved and noncompliance
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items. The inspection involved a total of 13
. : ector-hours on site by one NRC inspector.
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Results: No items of noncompliance or deviations were identified.
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r DETAILS
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Persons Contacted
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Principal Licensee Employees
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G. Marcus, Director of QA
- J. T. McIntire, QA Supervisor
- J. J. Mihovilovich, Lead Structural Engineer
- J. T. Porter, QA Inspector
- M. A. Stanish, QA Engineer
- J. G. Young, Field Engineer The inspector also contacted and interviewed other licensee and conctrac-tor personnel, including area superintendents and craftsmen.
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance Item (454/79-16-02) Inadequate procedure to cover fit up and weld end preparation: The inspector reviewed the revised welding procedure specifications, training records and the nonconformance report.
It was determined that corrective action taken appeared to be acceptable.
(Closed) Unresolved Item (454/79-16-01) Audit followup:
The inspector reviewed CECO reports of audit performed at Westinghouse Corporation, Monroeville for years 1979 and 1980, follow-up actions and checklists for audits performed between 1977 and 1980.
It was determined that findings identified were closed out.
Functional or Program Areas Inspected
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1.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Unit 1)
The inspector observed the following work activities:
a.
Rigging and handling of Safety Injection System spool No. SIl0-5.
b.
Rigging and handling of Residual Heat Removal System spool No. RH12.
c.
Tacking of consumable insert ring to Residual Heat Removal System Weld No. FW47 on drawing No. RH-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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e No items of noncompliance or deviations were identified.
2.
Reactor Coolant Pressure Boundary Piping - Observation of Welding Activities (Units 1 and 2)
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The inspector observed the following welding activities:
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a.
Unit 1 Safety Injection System welds No. 386 and No. 223 on drawing No. SI-4.
b.
Unit 1 Residual Heat Removal System Welds No. 56 on drawing No. RH-8 and weld No. 48 on drawing No. RH-1.
c.
Unit 2 Reactor Coolant System Welds No. 197 and No. 198 on drawing No. 2H-CBE-2.
It was determined that (1) work was conducted in accordance with traveller; (2) proper welding materials were used; (3) welding procedure requirements were met; (4) work area was free of weld rod-stubs; and (5) physical appearance was acceptable.
No items of noncompliance or deviations were identified.
3.
Reactor Coolant Pressure Boundary Piping - Welder Qualification (Units 1 and 2)
The inspector established that Hunter Corporation procedure a.
for welder qualification has not been revised since the last review (IE Inspection Reports No. 454/79-16 and No. 455/79-16).
b.
The inspector randomly selected the qualification record of sixteen (16) welders who performed welding on welds stated in paragraph 2 of this report.
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It was determined that the above documents met the requirements of ASME B&PV Code Section IX.
No items of noncompliance or deviations were identified.
4.
Reactor Coolant Pressure Boundary Piping - Weld Heat Treatment (Units 1 and 2)
a.
Review of Procedure The inspector reviewed the applicable welding procedures used in welds stated in paragraph 2 of this report and determined that preheating and monitoring methods are specified and ac-
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ceptable.
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b.
Observation of Preheating While observing welding activities for items stated in para-graph 2 of this report, the inspector determined that preheat met the welding procedure requirements.
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No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on February 21, 1980.
The inspector summarized findings of the inspection. The licensee ac-knowledged the findings.
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