IR 05000440/1980003
| ML19323B370 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/24/1980 |
| From: | Key W, Korklin J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323B368 | List: |
| References | |
| 50-440-80-03, 50-440-80-3, 50-441-80-03, 50-441-80-3, NUDOCS 8005120294 | |
| Download: ML19323B370 (3) | |
Text
8005120 2y
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report Nos. 50-440/80-03; 50-441/80-03 Docket Nos. 50-440; 50-441 License Nos. CPPR-148; CPPR-14 Licensee: The Cleveland Electric Illuminating Company P.O. Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Units 1 and 2 Inspection At: Perry Site, Perry, OH w
Inspection Conducted: March 4, 1980 e
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Inspectors:
J. E. Konklin 2 /30/fC i
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W. 3. Key ju ff.2l/
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w b5bh Approved By:
C. C. Williams, Chief
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Projects Section 2
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Inspection Summary Inspection on March 4, 1980 (Report Nos. 50-440/80-03 and 50-441/80-03)
Areas Inspected: Reactor vessel recirculation nozzle safe-end modifica-tion activities (Units 1 and 2 ).
This inspection involved a total of eight onsite inspector-hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS Persons Contacted
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Principal Licensee Employees M. Edelman, Manager, Nuclear QA Department
- R. Vondrasek, CQE Supervisor
- H. Walls, Senior NDE Administrator i
- R. Williams, Quality Engineer, Mechanical
- J. Mehaffey, Lead Mechanical QE
- L. Young, CQC Lead Mechanical Inspector
- R. Sheer, CQC Mechanical Inspector
- H. Putre, Senior Engineer
- P.
Nichols, Engineer General Electric
- J. Miller, Resident Site Manager
- G. Craigo, QC Supervisor (I&SE)
- J. Bucka, QC Representative
- P.
Irelan, Construction Engineer The inspectors also contacted other licensee and contractor personnel.
- Denotes those attending the exit meeting on March 4, 1980.
Functional or Program Areas Inspected Recirculation Nozzle Safe-End Replacement Previous RIII Inspection Report (50-440/80-02; 50-441/80-02), which reported the results of interviews with site craftsmen during a February 27-29, 1980 inspection, identified an area of concern regard-ing the reactor vessel recirculation nozzle modification activities.
This inspection on March 4, 1980 was performed as a followup on that area of concern.
The specific identified area of concern involved the recirculation (N-2)
nozzles on the Unit I reactor vessel at the 30, 150, 210, and 300 azimuths. The weld end preparations on these nozzles did not meet the specifie'd liquid penetrant acceptance requirements of the ASME Code,Section III, NB5350. However, these weld end preps do meet the revised acceptance criteria (NB5130) as approved for use by General Electric in FDDR KL1-053.. Revision 2, " Weld Edge Preparation Surfaces".
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The Region III inspectors examined the Unit 1 N-2 nozzles, including the weld end preparations, and then met with CEI and GE representatives i
to discuss the repair and welding activities on the nozzles. The follow-ing course of action was agreed upon by the meeting attendees:
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Since the nozzle at 150 azimuth appears to be the worst case, based on the depth of the excavations, that nozzle will be used as a test case to demonstrate that the use of NB5130 and the approved
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automatic welding process will result in an acceptable weld to the
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established RT/PT acceptance criteria of NB5000.
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Along with the existing production steps and NDE acceptance crit-eria, additional RT examinations will be performed on the 150 nozzle after the root pass, after each initial pass in an area of deep excavation, and at the end of each day after filler passes.
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All radiographs on the 150 nozzle welds will be reviewed and accepted by CEI before proceeding with additional welding, and work on the other three nozzles in question will not continue until the 150 nozzle weld has been accepted by CEI.
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All radiographs and inspection reports for the 150 nozzle will be-come part of the permanent records retained by CEI.
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Welding on those nozzles which meet the acceptance criteria of NB5350 can continue without delay; the acceptance criteria of
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NB5130 will be used only on a case-by-case basis where fully justified.
l The RIII inspectors emphasized that NRC agreement with the above approach (
does not relieve the licensee of the respcnsibility to meet all require-ments of the ASME Code, including approval of the Code authorities where i
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No items of noncompliance or deviations were identified, a
Exit Interview i
The inspectors met with site staff representatives (denoted under Persons Contacted) at the conclusion of the inspection on March 4, 1980. The licensee acknowledged the findings reported herein.
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