IR 05000250/1991004
| ML17348A882 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/08/1991 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17348A881 | List: |
| References | |
| 50-250-91-04, 50-250-91-4, 50-251-91-04, 50-251-91-4, NUDOCS 9103050273 | |
| Download: ML17348A882 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 1!
101 MARIETTASTREET, N.IN.
ATLANTA,GEORGIA 30323 Report Nos.:
50-250/91-04 and 50-'251/91-04 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-250 and 50-251 Facility Name:
Turkey Point 3 and
Inspection Conducted:
January 7-18, 1991 Inspector:
~ (
Approved by:
J.
.
ake, hief Ma r al and Processes Section Engineering Branch Division of Reactor Safety License Nos.:
>gne ate igne SUMMARY Scope:
This routine uannounced inspection was conducted in the areas of observation of inservice inspection work and work activities which included ultrasonic examination of the Unit
Reactor Vessel and eddy current
, examination of the Unit 3 Component Cooling Water Heat Exchanger 3-C.
The inspector also assisted personnel on the NRC-Nondestructive Examination (NDE)
van by providing an interface with Florida Power and Light (FP8L)
management to expedite the NDE Van inspections.
Results:
Inservice Inspection activities observed by the inspector were performed in an excellent manner by highly qualified and capable personnel.
Management at all levels were involved in assuring quality as evident by the Computer based programs initiated by the licensee and their vendors, excellent work practices observed, and FP&L's upper tier management's assistance to ensure that the NRC NDE Van examiners could adequately audit work accomplished by the licensee.
All work observed was performed in a conservative manner which exceeded code requirements.
The ISI program reviewed during this inspection, for 'this site was excellent.
In the areas inspected, violations or deviations were not identified.
9103050273 910215 PDR ADQCK 05990250 G
REPORT DETAILS Persons Contacted Licensee Employees
- E. Anderson, Senior Specialist, Unit 3, Inservice Inspection (ISI)
- R. Daly, Outage Manager
- J. O'rien, equality Control Superintendent
- L. Pearce, Plant Manager
- T. Plunkett, Site Vice President
'0.
Powell, Licensing Superintendent
- W. Skelley, Supervisor, Nuclear Engineering R. Turner, Senior Specialist, Unit 4, ISI Other licensee employees contacted during this inspection included engineers, technicians, and administrative personnel.
Other Organizations D.
Rosow, Director, Southwest Research Institute, Department of NDE Services NRC Resident Inspectors
- G. Schnebli L. Trocine
- Attended exit interview Inservice Inspection (73753)
The inspector observed activities as indicated below, to determine whether ISI work was being conducted in accordance with applicable procedures, regulatory requirements, and licensee commitments.
The applicable Code for ISI, for both Unit 3 and Unit 4 is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME BSPV)
Code, Section Xl, 1980 edition with addenda through Winter 1981 (80W81).
Both Units are in the first outage, of the third 40 month period, of the second ten year ISI Interval ending February 21, 1994 for Unit
and April 14, 1994 for Unit 4.
The inspector 's objectives for this inspection were to audit the automated Ultrasonic examinations which were inprocess on the Unit 3 reactor vessel, to observe eddy current examinations and evaluate the MIZ-18 data for the Unit 3-C Component Cooling Water Heat-Exchanger and to assist in
coordinating the NRC nondestructive test van's independent examination efforts at the Turkey Point site.
a.
Volumetric examination of Unit 3 reactor vessel welds using the automated ultrasonic technique The inspector observed Southwest Research Institute (SwRI)
Nondestructive Test examiners perform ultrasonic examinations of welds in the Unit 3 reactor vessel.
In addition to observing the inprocess ultrasonic examinations and their required calibrations, the inspector concurrently reviewed ultrasonic data which had been processed with SwRI's Enhanced Data Acquisition System (EDAS).
The ultrasonic procedure for the examination.of the reactor vessel welds was SwRI's Procedure, TKY-AUT-15,
"Automated Inside Surface Ultrasonic Examination of Ferrtic Vessels Greater Than 2.0 inches in Thickness".
The ultrasonic procedure for the reactor vessel nozzle welds was SwRI's Procedure, TKY-AUT-14, "Automated Ultrasonic Examination of Austenitic and Dissimilar Pressure Piping Welds".
The following in-process ultrasonic examinations were observed by the inspector:
Exam No.
Exam Area Exam An les
30A
68
72
Nozzle-Pipe 29"-RCS-130 1305-1(810')
Int.-Upper Shell 3-WR-33 (5'-125')
Nozzle - Vessel (Wall)
3,DI-B (8320')
Elbow - Nozzle 27-4"-RCS-1307-14 (880').
Elbow-Nozzle 27-j"-RCS-1309 -14 (8200')
Elbow-Nozzle 274" RCS-1306-14 (8320')
Upper Shell-Flange 3-h'R-18 45RL 50/70 0,45T,60T, 50/70T 50/70 50/70 50/70 0,45,60,50/70T
76
Elbow-Nozzle 274"-RCS-1307-14 (880')
ELbow-Nozzle 27$ -RCS-1309-14 (8200')
Elbow-Nozzle 274-RCS-1306-14 (8320)
50/70 CW/CCW 50/70 Ch'/CCW 50/70 CW/CCW'
e The above examinations were observed to ensur'e that the approve procedures were available, were being followed, by competent test examiners and the specified nondestructive examination equipment was being used.
In addition to the above observations, the inspector concurrently reviewed EDAS data with SwRI data analysts (Level II and III examiners) for the following welds:
Exam No.
41 25A 27A
32-A 31A
Exam Area Nozzle-Vessel (Wall)
3-DO-B (810')
Nozzle-Vessel (Wall)
3-DO-B (810')
Nozzle-Vessel (Wall)
3DO-A 8130'NT Upper Shell 3-WR-33 INT Upper Shell 3-WR-33 (5'-125')
Nozzle - Pipe 29"-RCS-1304-1 8130'NT Upper Shell 3-WR-33 (245'-365')
INT Upper shell 3-WR-33 (125'-245')
Nozzle-Pipe 29"-RCS-1305-1 810'xam An les 0,45T,60T,50/70T CW 0,45T,60T,50/70T CCW 0,45T,60T,50/70T CCW 50/70 DN rerun due to final calibration being out 50/70 CW rerun due to final calibration being out 45RL 50/70 CCW rerun due to final calibration being out 50/70 CCW rerun due to final calibration being out 45 Shear Wave
74
78 Nozzle-Pipe 29"-RCS-1304-1 8130'5 Shear Wave Elbow-Nozzle 27>"-RCS-13097-14 880'0/70 CW/CCW Elbow-Nozzle 50/70 CW/CCW 27$ " RCS-1309-14 8200'lbow-Nozzle 27)"-RCS 1306-14 8320'0/70 CW/CCW
The inspector reviewed the data for the above welds to ensure that examination results, evaluation of results and any corrective actions were being recorded as specified in the ISI program and the NDE procedures.
The inspector's review concluded that the SwRI examinations were conservatively performed and data 'was.effectively evaluated and recorded.
No recordable indications. were observed in the reactor vessel or nozzle examinations.
Evaluation of eddy current examination data for the Component Cooling Water (CCW) Heat-Exchanger 3-C The inspector reviewed Zetec's MIZ-18 data for the eddy current examinations of the CCW heat-exchanger 3-C to determine whether FP&L's evaluation of the examination results were accurately
- dispositioned and recor'ded.
FPSL's procedure for these examinations was Procedure NDE-1.3,
"Eddy Current Examinations of Non-Ferromagnetic Tubing with the Multi-Frequency Te'chnique MIZ-18".
Evaluations for.201 tubes were verified by the inspector.
Twenty-four of the examinations had been performed with a pancake coil and 177 of the tube examinations had been performed with a bobbin coil.
During the evaluation, cracks were observed on'he inside surface of some tubes 9 the tube sheet.
.Depth numbers were assigned to these indications and the results were put in a data base computer program for comparisons to the previous examination data for each tube.
Tubes showing unacceptable crack growth are selected by the data base program and these results are sent to the Nuclear engineering to determine tube plugging or replacement criteria.
Final disposition-ing of the tubes identified during the inspection was not complete prior to the inspector's departure.
The inspector's audit of evaluations by the FPSL analysts for the eddy current examinations indicated that these individuals were very knowledgeable of procedural requirements, operation of the test equipment, and their responsibilities to accurately disposition and record the results.
Coordination of NRC Independent Measurements NDE Van Activities The inspector also assisted the NDE Van personnel in interfacing with cognizant licensee personnel to achieved their independent inspection goals.
The plant Manager for the Turkey Point facility was very helpful in establishing this effort as a priority, although the plant ISI of piping had not started at this time.
The van objectives were completed within the time limits scheduled and none of the sample selected was found to be deficient.
Within the areas examine, no violations or deviations were identifie jiI
3.
Exit Interview The inspection scope and results were summarized on January 18, 1991, with those persons indicated in paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results.
Proprietary information is not contained in this report.
Dissenting comments were not recei'ved from the license "r