IR 05000250/1982001
| ML20041A754 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/28/1982 |
| From: | Blake J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20041A750 | List: |
| References | |
| 50-250-82-01, 50-250-82-1, 50-251-82-01, 50-251-82-1, NUDOCS 8202220468 | |
| Download: ML20041A754 (4) | |
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UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION n
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REGION 11
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101 MARIETTA ST., N.W., SulTE 3100 o
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s ATLANTA, GEORGIA 30303 Report Nos. 50-250/82-01 and 50-251/82-01 Licensee:
Florida Power and Light Company
- P. O. Box 529100 Miami, FL 33152 Facility Name: Turkey Point Docket Nos. 50-250 and 50-251 License Nos. DPR-31 and DPR-41 Inspection at-ey P int site near Homestead, Florida f
//.2EM u Inspector:
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J tt J. J.
Take Date Signed Approved b :
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ol A. R. Herdt, Section Chief
/Date' Signed Engineering Inspection Branch Engineering and Technical Inspection Division
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SUMMARY I
Inspection on January 12-15, 1982 Areas Inspected
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This routine, unannounced inspection involved 33 inspector-hours on site in the areas of steam generator repair; and inservice inspection.
Results Of the two areas inspected, no violations or deviations Vere identified.
r 8202220468 820129 PDR ADOCK 05000250 O
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- H. E. Yaeger, Site Manager
- J. K. Hays, Plant Manager, Nuclear
- S. M. Feith, Supervisor,-QA Operations
- M. J. Crisler, Supervisor, QA Construction
- T. P. Coste, QA Engineer
- R. E. Tucker,' QA Engineer
- J. D. Ferrare, QA Engineer
- D. W. Jones, Supervisor, QC Operations
- R. 8. Cook, QC Engineer J. F. O'Brien, Supervisor, QC Construction E. Anderson, ISI Engineer E. Hartman, ISI Engineer J. Moore, Startup Supervisor A.' Abbott, Startup Engineer Other licensee employees contacted included construction craftsmen, QC and QA technicians,- security force members, and office personnel.
Other Organizations D. M. Swann, Welding and QA Supervisor, CB&I-R. Neimeyer, SwRI S. Wenk, SwRI
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 15, 1982, with those persons indicated in paragraph 1 above. One new inspector followup
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item was identified during this inspection.
50-250/82-01-01:
Resolution of channel head weld radiographs - ~ steam-i generator "A", paragraph 5.a.
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Licensee Action on Previous Inspection Findings
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Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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5.
Steam Generator Repair The nspector observed work activities and reviewed procedures and QC d
documentation for the following activities:
a.
Steam generator welds - The steam generator shell welds were welded and inspected by CB&I. The inspector reviewed. the final - documentation,
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including radiographs, for the -lower girth weld on steam generator A.
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During. the review of the radiographs the inspector questioned the interpretation of some of the indications in the radiographs.
During discussions with the licensee the inspector learned that questions had
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been raised by FP&L concerning one of the indications in the base material adjacent to the weld.
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Af ter discussing. the concerns, the licensee elected to have an inde-pendent review made of the radiographs by S. Wenk of Southwest Research, Inc., who was on site for the radiography of the main. coolant pump welds. The inspector informed the licensee that the resolution of.
the concerns would be followed up during a future inspection. This was ihntified as inspector followup item 50-250/82-01-01, Resolution of channel head weld radiographs steam generator "A".
There were no other questions or concerns identified in this area.
b.
Piping welds - The inspector reviewed the documentation, including radiographs, for the following piping welds associated with steam generator "C":
Feedwater, FSK-M-804-R2 - FW4, FW5, FW6.
Main Steam, FSK-M-641-R2 - FW-C-1, FW-C-2.
A= visual inspection was conducted on the final weld surface of the welds in the feedwater lines of steam generators B and C and the main steam line for steam generator C.
Preparations for welding the final weld in the main feedwater line on steam generator A were also observed.
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There were no questions or concerns identified'in this area of inspec-tion.
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c.
Pressure testing - The inspector observed the preparations for.the.
hydrostatic testing of the secondary side of "C" steam generator and associated piping.
The observations included discussions with the startup test organization responsible for conduct of the test, the
. construction QC and. operations ISI Groups responsible for inspections
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during the test and the construction QA group responsible for surveil-lance of the activities.
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The inspector reviewed Preoperational Procedure 0800.7 dated January 14, 1982, titled: Post SGRP Steam Generator and Associated Piping Pressure Test.
The inspector noted that the conduct of the pressure test was going to involve participation by the Pre-op Test Group, the inservice inspec-tion contractor, Construction QA, Construction QC, CBI,- and the-authorized nuclear inspectors (ANI) for CBI and FP&L. With this level of participation, clearing of pre-test requirements and communications during the test were the areas most likely to cause problems.
The inspector observed the clearing of a number of the pre-test require-ments.during the evening of January 14, 1982. Upon arrival at the site on January 15, 1982, the inspector learned that a communicatioas error had caused the test to be concluded prior to the authorized nuclear inspectors completing their walk-down of the piping. A review of the circumstances showed that the only part of the test not completed was the leak test verification by the CBI and FP&L ANI's.
The pressure test was complete and_ verified. At the time of the exit interview the licensee was in the final stages of repressurizing to the leak test -
pressure for completion of the test.
There were no violations or deviations identified in this area of the inspection.
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Inservice Inspection (ISI)
The licensee is conducting the majority of the inspections required to complete the first ten year inspection interval. As reported in RII Report 50-250/81-14, the mechanized inspection of the reactor ressel was conducted in June 1981.
During thi; inspection the licensee was starting to volumetrically inspect the welds in the A main coolant pump body.
The inspection was being done using the J. A. Jones 2.5 Mev X-ray machine operated by Southwest Research Institute. On January 15, 1982, the inspector reviewed the eight radio-graphs representing station marker 12 through 102 of weld B of the pump.
There were no questions or concerns identified' during this part of-the inspection.
The inspector revictied the status of the inspection with the licensee's ISI engineers and observed the interaction between the licensee's ISI engineers and the ISI contractor, Southwest Research.
There were no violations or deviations noted during this area of the inspection.