IR 05000250/1982008
| ML20050N501 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/16/1982 |
| From: | Blake J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050N498 | List: |
| References | |
| 50-250-82-08, 50-250-82-8, 50-251-82-08, 50-251-82-8, NUDOCS 8204140368 | |
| Download: ML20050N501 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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E REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 k
ATLANTA, GEORGIA 30303 o
Report Nos. 50-250/82-08 and 50-251/82-08 Licensee:
Florida Power and Light P. O. Box 529100 Miami, FL 33152 Facility Name:
Turkey Point Docket Nos. 50-250 and 50-251 License Nos. OPR-31 and DPR-41 Inspection at I key Poljn site near Homestead, Florida Inspector:
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J. 4 pk Date Signed Approved b
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A. R. Herdt, Section Chief Dats Signed Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on February 23-26, 1982 Areas Inspected This routine, unannounced inspection involved 26 inspector-hours on site in the areas of licensee action on previous inspection findings; steam generator repair program; preservice and inservice inspections.
Results Of the three areas inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- H. E. Yaeger, Site Manager
- J. K. Hays, Plant Manager, Nuclear
- D. W. Jones, Q.C. Supervisor
- S. M. Feith, QA Operations Supervisor
- J. D. Ferrare, QA Engineer
- R. E. Tucker, Senior QA Engineer
- G. Gotch, PNS Section Supervisor
- E. L. Anderson, ISI Engineer
- T. Essinger, Assistant Manager QA Turkey Point
- M. Crisler, QA Engineer
- S. M. Mowbray, Power Plant Engineer Other personnel contacted included inservice inspection engineering and inspection personnel, construction engineering personnel and of fice per-sonnel.
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NRC Resident Inspector
- R. Vogt - Lowell, SRI
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 26, 1982, with those persons indicated in paragraph 1 above. The inspector informed the licensee that an unresolved item existed in that a procedure which FP&L had committed to implement had been turned down by the PNSC. (After returning to the Regional Office the inspector was informed by telecon that the PNSC had reconvened and had approved the procedure for use in the steam generator repair program; thereby eliminating the unresolved item).
Other items identified for follow-up inspection included the following:
a.
Inspector Follow-up Item (50-250/82-08-01)
Resolution of Grinding Repair on Steam Generator "A" Channel Head Casting.
b.
Inspector Follow-up Item (50-250/82-08-02) Resolution of Mechanical Denting Indications in Unit 3 Steam Generator Tubes.
c.
Inspection Follow-up Item (50-251/82-08-03) Location of Over-Expanded Tubes in Unit 4 Steam Generator..
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3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation (250, 251/81-26-01) " Inadequate Measures to Control Welding and Welder Qualification" - The inspector reviewed the correc-tive actions discussed in the licensee's letter No. L82-10 dated January 11, 1982. There are no further questions at this time.
b.
(Closed) Violation (250, 251/81-26-02) Failing to Establish Controls for Storage and Preservation of Installed Equipment.
The inspector reviewed the corrective actions discussed in the licensee letter No. L82-10 dated January 11, 1982 and noted that everything appeared to be as described except that site procedure ASP-15 " Control of Expend-able Products" was still in the approval cycle as of the start of this inspection. On Friday, February 26, 1982 the inspector was informed that the licensee's PNSC had rejected site procedure ASP-15. After some consideration the inspector informed the site manager that it appeared that there was now a deviation from the commitment of Letter No. L82-10 but that it would be identified as an unresolved item until it could be discussed with Region II management. On Monday, March 1, 1982 a licensee representative called the Regional Office to inform the inspector that the PNSC had approved the procedure for use by construc-tion (Steam Generator Repair Program) which satisfied the commitment of Letter No. L82-10.
Therefore the violation is closed and the unre-solved item was cancelled.
c.
(Closed) Violation (250, 251/81-26-03) " Failure to Include All Required Nonessential Variables in WPS" - The licensee's responses L82-10 of January 11,1982 and L82-48 of February 9,1982 were reviewed and based on these letters and discussions with the licensee the violation has been retracted.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Previously Identified Inspector Follow-up Items (Closed) (50-250/82-01-01) Resolution of Channel Head Weld Radiographs -
Steam Generator "A" The inspector reviewed the report prepared by Mr. Sam Wenk, Southwest Research Institute, Level III, concerning the resolution of the areas of concern in these radiographs. The radiographs and Mr. Wenk's review were discussed with Mr. Roger Tucker, FP&L Level III. This item is closed.
6.
Steam Generator Repair Program The inspector reviewed the following problems which had been identified during the preparations for testing and preservice inspections of the steam generators in Units 3 and 4.
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a.
Steam Generator A, Unit 3 - Channel Head Casting Indication.
On February 20, 1982 during installation of temporary insulation around the primary side (channel head) of the steam generators, an insulator discovered what appeared to be a crack in the base metal adjacent to the Z-Weld of Steam Generator A.
(The Z-Weld joins the existing cast carbon steel channel head to the replacement tube sheet assembly.)
By February 23, 1982, the indication had been tentatively identified as a sand inclusion from the original casting process and had been removed by grinding. The inspector reviewed the photographs of the indication and the radiographs of the Z-Weld. (The indication was located approx-imately 1-inch below the edge of the Z-Weld between radiographic station markers No. 30 and 31). The photographs show two irregularly shaped indications in an area which appears to have been recently ground, buf fed, or power wire brushed. The radiographs show that these indications had existed all along but there is no evidence that they had been open to the surface until their discovery by the insulator.
The indication was removed by grinding to a depth of approximately one-inch below the outside surface; and the resulting depression was sloped to minimize the stress concentration. The Westinghouse stress analyst who had done the final stress analysis for the steam generator
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replacement was called in to examine the depression and determine if it could be left as-is or if more grinding and/or weld repairs would have to be done.
The inspector informed the licensee that the removal of this indication was a special ASME Section XI repair and as such the repair program would have to specify the method of measure, tent of the cavity created by removing the flaw.
This concern over accurately measuring the ground area was identified as an inspector follow-up item.
No. 50-250/82-08-01, Resolution of Grinding Repair on Steam Generator
"A" Channel Head.
b.
Repair of Steam Generator A Feedwater Nozzle.
During the preservice examination of the feedwater nozzle extension to nozzle remnant weld (A-2), a code rejectable indication was discovered by ultrasonic examination and subsequently repaired by grinding on the inside surface
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of the nozzle.
The inspector reviewed the documentation of the
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inspections which detected the defect and the final inspections which
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verified the removal and final acceptance.
There were no further questions concern'ng this repair, at this time.
c.
Mechanical Denting, Unit 3 Steam Generators. During post-installation eddy current inspection of the Unit 3 steam generators the licensee noted a significant number of the tubes exhibited evidence of mechanical denting. After the problem was identified, the licensee re-inspected all of the tubes in the three generators. The inspection results were as follows:
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STEAM STEAM STEAM GENERATOR GENERATOR GENERATOR A
B C
Total Tubes Inspected 3207 3211 3205 Total Tubes With Dents.
Less than.001 225 308 1024
.001 to.003
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Total Tubes With Indications Less than 20*.
26
Tubes To Be Plugged
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At the time of this inspection the licensee had determined that the majority of these mechanical dents were in the vicinity of the 5th and 6th support plates. Investigation as to the cause was continuing. The inspector informed the licensee that this item would be inspector follow-up item 50-250/82-08-02 Resolution of Mechanical Denting Indi-cations in Unit 3 Steam Generator Tubes.
d.
Eddy Current Inspection of Unit 4 Steam Generators.
The inspector observed eddy current testing of Unit 4 replacement steam generator tubes. During this eddy current testing the licensee's ISI coordin-ators were reviewing the fabrication documentation concerning overex-panded tubes in these steam generators. A review of the documentation showed the location of only 34 of the tubes which had been overex-panded. The data also indicated that a significantly larger number of tubes had been overexpanded.
The licensee has requested that Westinghouse provide the exact location of all tubes which were overexpanded.
The inspector informed the licensee that this would be inspector follow-up item 50-251/82-08-03 Location of Overexpanded Tubes in Unit 4 Steam Generators.
There were no violations er deviations in this area of the inspection.
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