IR 05000325/1979004
| ML19294A724 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 02/01/1979 |
| From: | Blake J, Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19294A723 | List: |
| References | |
| 50-325-79-04, 50-325-79-4, NUDOCS 7903130007 | |
| Download: ML19294A724 (3) | |
Text
UNITED STATES n at00g'o NUCLEAR REGULATORY COMMISSION
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101 M ARIETTA STREET, N.W.
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ATLANTA, GEORGIA 30303 o
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Report No. : 50-325/79-4 Licensee:
Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick Steam Electric Plant Docket No..
50-325 License No.-
DPR-7 Inspection at uthport, North Carolina 0/
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Inspector:
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Jr Blake Date Signed Accompany [ngPersonnel:
J. Gieske, Sandia Lab, NRC Consultant J. Smith, ORNL, NRC Consultant MM
- !/ 7 9 Approved by: C T. E. Conlon, Section Chief, RCES Branch SUTiARY Inspection on January 15-19, 1979 Areas Inspected This special, announced inspection involved 40 inspector-hours onsite in the areas of ultrasonic inspection of reactor recirculation inlet nozzle safe ends; and ultrasonic inspection of stainless steel core spray piping.
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Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
7903130007
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a DETAILS 1.
Persons Contacted Licensee Employees
- H, R. Banks, Manager, Nuclear Generation
- R. M. Coats, Manager, Generation Services
- A. C. To11ison, Jr., BSEP Plant Manager
- L. R. Hancock, Inservice Coordinator
- W. Triplett, Supervisor, Engineer Other Organizations Lambert, MacGill, Thomas, Inc. (LMT)
T. Lambert, Level III
- D. MacGill, Level III E. Thomas, Level III J. Hill, Level II W. Raymer, Level II K. King, Level II
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on January 19, 1979, with those persons indicated in Paragraph I above. The inspector reviewed the status of the recirculation system inlet safe end inspection. The final evaluation of the inspection will be made by the Lffice of Nuclear Reactor Regulation, Division of Operating Reactors af ter the NRC Consultants had completed the evaluation of the data. The results of the Core Spray
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Piping inspection were also discussed.
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Unresolved Items Untesolved items were not identified during this inspection.
4.
Core Spray Piping Inspection The stainless steel core spray piping from the reactor vessel to the isolation valve was inspected by LMT to determine if there was indi-cation of intergranular stress corrosion cracking adjacent to any of the velds. Indications were noted at welds 13, 14, 17, and 19 on Loop A and welds 12, 13, 19, 20 and 22 on Loop B.
The indications at weld 19 in Loop B were evaluated as being approximately 30% to 40% through the wal.
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-2-Based on the results of this inspection the licensee elected to replace the stainless steel portion of the core spray loops with carbon steel piping.
5.
Recirculation Inlet Nozzle Safe-End Inspections The safe-ends were inspected by LMT Inc., in accordance with NRC IAL dated January 10, 1979, with inspections witnessed by this inspector and NRC consultants J. Gieske, Sandia Lab and J. Smith, ORNL. Particular attention was given to nozzle N2D safe end which was reported to have the largest UT reflector. At the request of NRC, this nozzle was inspected twice, by two different LtIT inspector and data transcriber crews, with special inspection techniques requested by the NRC consultants during the second inspection.
The special inspections were directed toward identifying and further evaluating the reflectors.
A preliminary review of the data indicated that there had been no significant change in the reflectors since the September and November inspections. The final evaluation of the ultrasonic data taken during this inspection is to be done independently by LMT for the licensee and by the consultants for NRR-DOR with further action, inspection effort, to be determined after comparison of the evaluations.
There were no items of noncompliance or deviations during this part of the inspection.
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