IR 05000369/1981032
| ML20039D214 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/09/1981 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039D209 | List: |
| References | |
| 50-369-81-32, 50-370-81-22, NUDOCS 8112310428 | |
| Download: ML20039D214 (3) | |
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UNITED STATES:
NUCLEAR REGULATORY COMMISSION
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ATLANTA, GEORGIA 30303
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Report Nos. 50-369/81-32 and 50-370/81-22
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Licensee: Duke Power Company
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422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station
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Docket Nos. 50-369 and 50-370
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License Nos. CPPR-83 and CPPR-84
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Inspection at Mc
'near Charlott'e, North Carolina
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Date Signed Inspector:
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Approved by'
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l A. R. Herdt, SectiWChief
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Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on November 18-20, 1981 Areas Inspected This routine, announced inspection involved 44 inspector-hours on site.and at NRC headquarters, Bethesda, Maryland in the areas of Eddy current steam generator tube examination to determine the possible effects of feedwater flow induced vibration in the area of the preheater section.
Results No violations or deviations were identified.
8112310428 811210 PDR ADOCK 05000
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REPORT DETAILS
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Persons Contacted
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Licensee Emplosees
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J. T. Moore, Project Manager J. W. Willis, Project QA Engineer
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- D. B. Lampke, Licensing Engineer
- W. M. Sample, Project and Licensing Engineer G. A. Copp, Licensing Engineer
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C. B. Cheezem, ISI Engineer Other Organizations Babcock Wilcox N; clear Power Generation Division (NPGD)
G. F. Able, Level III Eddy Current Examiner NRC Resident Inspector
- P. R. Bemis
- M. Graham
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 19, 1981 with those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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Steam Generator Tube Eddy Current Examination To Determine Affects of Feedwater Induced Vibration in the Preheater Section Area (Unit 1).
On October 30, 1981 the licensee informed the Commission (NRR) by letter, W. O. Parker to H. R. Denton, of impending action on McGuire-1 Steam Gener-ators (SG) following notification from Westinghouse (W) of SG experience on a W non-domestic nuclear power plant (ALMARAZ) with the same type, Model-D steam generators.
At the time McGuire-1 was undergoing power ascension testing at 30% power and was anticipating progressing to the 50% power level
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for tests t at that plateau.
The licensee reported that a conservative
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evaluation of existing data indicated that operation for one month at 50%
was not expected to cause unacceptable tube wall degradation. On November 16, 1981 the licensee informed RII (Atlanta) that McGuire 1 was shutting down for approximately two weeks to conduct eddy current (EC) examinations
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on certain SG tubes around the preheater section. On November 18, 1981
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inspector N. Economos accompanied by A. R. Herdt met with representatives of
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DPC and B&W (NPGD) to discuss details of the EC examination; review appli-
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cable procedure (s), personnel qualification records and other related
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quality records.
In addition the i nspectors observed equipment / system calibration and tube examination on SG-1A. The examination was performed to
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B&W procedure ISI-424 Rev. O, "Multifrequency Eddy Current Examination of 0.750"00 X 0.044" Wall RSG Tubing for Detection of Tube Wear at Support Plates." The area of interest involved only tubes in peripheral rows 49, 48
.and 47 in. the preheater section adjacent to the feedwater inlet. No evi-dence of unacceptable tube degradation was revealed by the examination.
On November 20,1981 following this inspection, the inspectors attended a meeting at NRC Headquarters in Bethesda, Maryland where W discussed the SG Model-D experience at Almaraz and Ringhals. W presented preliminary results of the ongoing investigation of degraded SG tubes from these plants and discussed in detail other current and planned analytical evaluation / studies, including simulated flow tests, vibration and metal impact monitoring instrument installation. Possible SG modifications (fixes) to alleviate the existing problem were also discussed. Tne licensee outlined the plan for installing various monitoring devices on the SGs, the program for power
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asce.nsion testing and, the plan for EC examination of SG tubes between the present 30% power level and when full power is reached.
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Within the areas inspected no violations or deviations were identified.
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Plant Tour (Unit-2)
The inspectors performed a general walk-thru inspection inside containment to observe pipe welding activity, cleanliness and weld consumable control.
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The inspectors noted the reactor vessel had been left without appropriate protective cover. Subsequent discussions with cognizant licensee personnel disclosed that the cover had been removed for the purpose of performing a safety injection line test and that it would be replaced upon test comple-tion.
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Within the areas inspected no deviations or violations were identified.
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