IR 05000369/1980036
| ML19340E796 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/24/1980 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19340E794 | List: |
| References | |
| 50-369-80-36, NUDOCS 8101150773 | |
| Download: ML19340E796 (4) | |
Text
<f UNITED STATES
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NUCLEAR REGULATORY COMMISSION
E REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGI A 30303
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Report No. 50-369/80-36 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station, Unit 1 Docket No. 50-369 License No. CPPR-83 Inspection at McG ir site near Charlotte, North Carolina
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d U //h Inspect N. Economos Date Signed Approved by:
- 8[ [v A. R. Herdt, Section Chief, RC&ES Branch Date Slgned SUMMARY Inspection on November 3-6, 1980 i
Areas Inspected This routine, announced inspection involved 25 inspector-hours on site and corporate office in the areas of preservice inspection data review and, evaluation.
Results No violations or deviations were identified in the areas inspected.
A 77.3 8101150
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DETAILS 1.
Persons Contacted Licensee Employees
- J. O. Barbour, Quality Assurance Manager Operations
- C.
B. Cheezem, Inservice Inspection Engineer Other licensee employees contacted included technicians, and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 6, 1980 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preservice Inspection Data Review and Evaluation
The preservice (baseline) inspection (PSI) of class 1 and 2 portions of the l
Nuclear Steam Supply System of McGuire Unit I was performed by B&W customer
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Service Department. The PSI program including applicable proceduras were written to comply with the requirements of ASME Section XI (71W72). The licensee has submitted approximately thrity-one (31) requests for relief involving welds and/or components where accessability and other reasons has made it impractical to conduct the code required preservice inspection.
Relief on these items was granted by letter on July 11, 1980 (S. S. Pawlicki to W. J. Youngblood, Division of Licensing).
l The inspector reviewed-results of the PSI, documented in summary form and,
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in supportive field data sheets. Specific areas of review were as follows:
1.
Pressurizer 3.
Reactor coolant pumps 5.
Class 1 Piping and supports, Reactor coolant system - hot and cold legs, crossovers.
6.
Class 1 valves
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Class 2 piping In order to confirm results of certain UT inspectior. results, the inspector selected the following welds for a review of construction radiographs.
Weld No.
System 1 MI-486-2 Safety Injection NI1F-683 Safety Injection NI1F-685 Safety Injection INI-483-1 Safety Injection 1NI-467-2 Safety Injection NCIF-108 Safety Injection NCIF-1072 Reactor Coolant NCIF-1072 Reactor Coolant NCIF-3613-3092 Reactor Coolant NCIF-2643 Reactor Coolant IND-193-2 Residual beat removal CFIF-712 Feedwater CFIF-474 Feedwater CFIF-467 Feedwater CFIF-461 Feedwater CFIF-45 Feedwater CFIF-106-VLV29 Feedwater MK2 to MK3 Feedwater (C F 94, A)
MK 4 to HK 2 Feedwater (C F 94, B)
MK 1 to MK 4 Feedwater (C F 94, C)
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Within these areas the following items were discussed with the licensee's representative who agreed to persue them further.
1.
Visual examination of the RPV closure head washers disclosed that washer #42 exhibited porosity.
2.
An arc. strike detected in weld number NI1F2008, of the safety injec-tion system, identified as PSI figure 4.4 66.23.
3.
Stud #3 on valve INI 38, FL-10 identified as PSI figure 4.3.25. did not have proper thread engagement.
4.
Class 1 Valves a.
The #6 nut on the apposite flange of valve INC-2 was not properly torqued.
b.
On the outlet side of valve INC-1, nuts (#1, #8, #9, ei5 and #11)
were not sufficiently engaged on their respective studs.
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Valve bolts for figure numbers 6.5.57, 6.5.58 and 6.5.59 were not inspected (visual).
5.
Internal valve Body Examination The code required visual examination was substituted for code and DPC required documentation.
However the request for relief, referenced MC-1-106 in the PSI summary report, applies to hydrostatic testing.
6.
C6ntainment Spray Heat Exchange Nozzle Welds i
MT was substituted for the code required UT examinations. However the request for relief MC-1-025, referenced in the PSI summary report, applies only to RHR heat exchangers National Board #635 and 636.
7.
Containment Spray Pump 1A Studs Visual examination of 1A pump studs #1-#24 disclosed that they were not fully engage in their respective nuts.
The inspector stated that this matter would be identified as inspector followup item 369/80-36-01 " Disposition of PSI Related Findings".
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