IR 05000250/1994008
| ML17352A583 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/10/1994 |
| From: | Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17352A582 | List: |
| References | |
| 50-250-94-08, 50-250-94-8, 50-251-94-08, 50-251-94-8, NUDOCS 9405160228 | |
| Download: ML17352A583 (18) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30323-0199 Report Nos.:
50-250/94-08 and 50-251/94-08 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-250 and 50-251 License Nos.:
DPR-31 and DPR-41 Facility Name:
Turkey Point 3 and
Inspection Conduc d:
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,
1993 Inspector: / /'i
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eir'I's ge P.E Re c ec r
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Da e Signed Approved by:
Jer me J.
Blake, Chief M
er als and Process Section gi eering Branch ivision of Reactor Safety SUMMARY Date Signed Scope:
This routine, announced inspection was conducted in the areas of Inservice Inspection (ISI), and Flow Accelerated Corrosion (FAC).
Results:
In each of the areas examined, the inspector discovered that nondestructive test (NDE) examiners have conducted conservative examinations in accordance with the appropriate test procedures.
NDE procedures were also noted to be very detailed, well organized and technically effective in implementing the applicable code requirements.
Supervisors, engineers, and NDE examiners contacted during this inspection were very knowledgeable in their areas of responsibility.
ISI records reflect the accomplishment of ISI activities consistent with procedural and regulatory requirements.
The licensee FAC program continues to maintain high energy carbon steel piping systems within acceptable wall thickness limits.
A weakness was identified related to cleaning in the course of liquid penetrant examinations.
In the areas inspected, no violations or deviations were identified.
I 9405ib0228 940510 PDR ADQCK 05000250
0, Persons Contacted REPORT DETAILS Licensee Employees
- T. Abbatiello, Site guality Manager
- G. Alexander, Supervisor Inspections Support and Inspection (CSI)
- H. Blew, ISI Coordinator
- F. Carr, ISI Level III
- J. Hutchinson, Manager Component, CSI
- D. Jeningan, Operations Hanager
- W. Klein, CSI
- R. Kundaikar, Engineering Manager L. Motley, Supervisor Code Programs CSI
- C. Howrey, Licensing
- L. Pearce, Plant General Manager
- T. Plumkett, Vice President
- R. Turner, ISI Specialist Other licensee employees contacted during this inspection included engineers, mechanics, technicians and administrative personnel.
NRC Resident Inspectors
- T. Johnson, Senior Resident Inspector (SRI)
- L. Trocine, Resident Inspector (RI)
- Attended exit interview
2.
Acronyms and initialisms used throughout this report are listed in the last paragraph.
Inservice Inspection (ISI)
The inspector reviewed documents and records, and observed activities, as indicated below, to determine whether ISI was being conducted in accor-dance with applicable procedures, regulatory requirements, and licensee commitments.
The applicable code for ISI; for Units 3 and 4 is the ASHE BKPV Code,Section XI, 1989 Edition with no Addenda (89NA).
Unit 3 is in refueling outage (RFO)
14; the first outage of the first, 40-month period, of the third, ten-year interval (01,Pl, I3) ending February 21, 2004.
Unit 4 is operating in the first, 40-month period; of the third, ten-year interval (Pl, I3) ending April 14, 2004.
Unit 3 was granted a
construction permit April 27, 1967, received its Operating License July 19, 1972, and commenced commercial operations on December 14, 1972.
Unit 4 was granted a construction permit April 27, 1967, received its Operating License on April 10, 1973, and commenced commercial operations on September 7,
1973.
The licensee's nondestructive examination (NDE) personnel, augmented by contract personnel from EBASCO, were performing liquid penetrant (PT),
magnetic particle (HT), visual (VT), radiographic (RT),
and ultrasonic (UT) examinations.
Steam Generator (S/G) tubing eddy current (ET)
examination data acquisition and analysis was being accomplished by the licensee's nondestructive examination personnel, augmented by contract personnel from Assea Brown Boveri Combustion Engineering (ABBCE), Zetec, Master-Lee (M-L), and Allen Nuclear Associates Inc.
(ANA). All the above activities were being accomplished under the umbrella of the FPEL guality Ass'urance (gA) Program.
a.
ISI Program Review, Units 3 and 4 (73051)
The inspector reviewed the following documents relating to the ISI program to determine whether the plan had been approved by the licensee and to assure that procedures and plans had been estab-lished for the applicable activities.
Procedures were also reviewed for technical content.
ID Procedures Reviewed Rev.
Title J I-CPS-2. 1 01/94 JI-CPS-2.3 Ol/94 J I-CPS-4. 0 01/94 JI-CPS-5.1 01/94 JI-CPS-5.2 01/94 JI-CPS-6. 0 02/94 JI-CPS-6.1 06/30/92 J I-CPS-10. 0 01/14/92 JI-CPS-10.1 06/08/92 JI-CPS-10. 2 06/05/92 CSI-ET-94-02 04/8/94 0 w/
PCN 92-008 0 w/
PCN 92-009 0 w/
PCN92-010 ASME Code Selection and Applica-bility ASME Code Selection Classification Criteria Inservice Inspection Services Vender Performance Requirements Changes To Inspection Plans and Schedules Changes to Code Programs Instruc-tions/Procedures Document Control Control of Field Generated Docu-mentation Packages Inservi ce Inspection (ISI)
NRC Summary Program Preparation of Inservice Inspec-tion (ISI) Programs Preparation of Relief Requests Eddy Current Examination Plan For Steam Generator Tubing At Turkey Point Unit 3
Relative to the review indicated above the inspector noted the following:
o Procedure JI-CPS-5. I, "Changes To Inspection Plans and Sched-ules,"
does not provide a formal mechanism for changes made to the ISI Inspection Schedule (Data Base).
It should be noted that the ISI Inspection Schedule (Data Base) will become a
portion of the FP&L submittal to NRC.
o Procedure JI-CPS-10. 1, "Preparation of Inservice Inspection (ISI) Programs,"
does not reflect the current ASME B&PV Code Section XI Edition applicable to Turkey Point Units 3 and 4.
Except as noted above, procedures were well written and appropriate for their intended application.
b.
Review of NDE Procedures, Units 3 and 4 (73052)
The inspector reviewed the procedures listed below to determine whether these procedures were consistent with regulatory require-ments and licensee commitments.
The procedures were also reviewed for technical content.
Procedures Reviewed NDE 1.3 ID NDE 2.2 12/03/93 NDE 3.3 11/05/93 NDE 3.4 12/03/93 NDE 4.1 02/09/94 NDE 4.2 02/09/94 NDE 4.3 02/10/94 NDE 5.2 01/03/94 NDE 5.4 12/13/93 Rev.
Title Eddy Current Examination of Non Fer-romagnetic Tubing With MIS-18 Magnetic Particle Examination Liquid Penetrant Examination Solvent Removable Visible Dye Technique Liquid Penetrant Examination Visible Dye
& Fluorescent Water Wash Tech-nique Visual Examination VT-1 Welds/Bolting/Bushings/Washers Visual Examination VT-2 Conducted During System Pressure Test Visual Examination VT-3 Ultrasonic Examination of Ferritic Piping Welds
& c 2" Thick Vessels Ultrasonic Examination of Austenitic Piping Welds
& x 2" Thick Vessels
ID Procedures Reviewed Rev.
Title NDE 5.5 12/13/93 NDE 5.11 01/03/94 NDE 5.12 03/25/94 NDE 5.15 02/08/94 NDE 5.16 02/10/94 Ultrasonic Examination of Hain Cool-ant Piping Welds (Turkey Point
&
4)
Ultrasonic Examination of Dissimilar Hetal Piping Welds 3 w/
Hanual Ultrasonic Examination of FC A Reactor Vessel Flange-To-Shell Welds
& Stud Hole Threads Ultrasonic Examination of Reactor Coolant Pump Flywheels Ultrasonic Examination Technique for the Evaluation of Cracking in Feed-water Piping Procedures were well written and appropriate for their intended application.
Observation of Work and Work Activities, Unit 3 (73753)
The inspector observed work activities, reviewed certification records of NDE equipment and materials, and reviewed NDE personnel qualifications for personnel who had been utilized in the ISI examinations during this outage.
The observations and reviews conducted by the inspector are documented below.
Activities Observed Liquid Penetrant Examination (PT)
The inspector observed PT examinations of the welds listed below.
The observations were compared with the applicable procedures and the Code.
The inspector performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.
Liquid Penetrant Examinations Observed Weld No.
System 12"-RC-1301-8 12"-RC-1301-8A Reactor Coolant Reactor Coolant
The inspector noted that the cleaning of the area of interest on the two welds identified above was poor.
White material was noted to remain in some of the crevices at the toe of the welds.
It could not be readily determined whether the material was developer from a previous PT examination or residue from the removed thermal insula-tion.
The inspector questioned the examiners about the residue, but they continued with the examination.
Upon developing the inspection area of interest, indications were noted at the toes of both welds.
The bleed out was a dark pink, not red, indicating that the indica-tions were the result of the poor cleaning (unremoved white residue)
and not discontinuities in the weld/base material.
In view of the above, and the high radiation field in the examination area, the licensee did not repeat the examination.
The licensee indicated that they would suitably annotate the examination records to assure that "all extraneous matter" is removed from the area of interest during the next PT examination of these welds as required by NDE 3.3.
The inspector concurs with the licensee in this matter, however considers the licensee's PT cleaning practices poor.
The inspector reviewed the certification, qualification, and visual acuity documentation for the PT examiners (See paragraph 2.d below).
The performance of the examinations was marginally satisfactory.
Nagnetic Particle 'Examination (NT)
The inspector observed NT examinations of the weld listed below.
The observations were compared with the applicable procedures and the Code.
The inspector performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.
Nagnetic Particle Examinations Observed Weld No.
System 6"-BDA-2301-18 Steam Generator Blowdown The inspector reviewed the certification documentation for the NT powder, the yoke, and the 10 Lbs. test weight (See Paragraph 2.d below).
The inspector reviewed the certification, qualification, and visual acuity documentation for the NT examiners (See paragraph 2.d below).
The examination was performed satisfactoril Ultrasonic Examination (UT)
The inspector observed UT examinations of the weld listed below.
The observations were compared with the applicable procedures and the Code.
The inspector performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.
Ultrasonic Examinations Observed Weld No.
4"-RC-1304-10 System Reactor Coolant The inspector reviewed the certification documentation for the UT instruments, transducers, and couplant (See paragraph 2.d below).
The inspector reviewed the certification, qualification, and visual acuity documentation for the UT examiners (See paragraph 2.d below).
The examination was performed satisfactorily.
Eddy Current Testing (ET) Steam Generator Tubing The inspector observed ET data acquisition and analysis activities.
The observations were compared with the applicable procedures and the Code.
The licensee plans to perform 100% bobbin coil examination (tube sheet to tube sheet)
of the non-plugged tubes in all three genera-tors, and Rotating Pancake Coil (RPC) examinations at 366 intersec-tions in S/G "B" and
"C" (196 dent intersections, 144 over-expanded intersections, and 26 non-over-expanded intersections).
Four tubes were plugged in the three generators as indicated below.
Steam Generator Tube Plug Summary U3 S/G IIAII S/G IlBll S/G IIC II Tubes Previously Plugged Tubes Preventively Plugged in RFO
Defective Tubes (z 40%)
Plugged in RFO
Total Tubes Plugged Degraded Tubes (20-39%) Prior to RFO
Degraded Tubes (20-39%)
identified in RFO 14
17
15
]2
474
21
42'
Steam Generator Tube Plug Summary U3 S
G "A"
$/G II8 II Total Degraded Tubes (20-39%) including RFO
Total Tubes Examined (Bobbin Coil)
3198 3199 3183 Notes:
1.
Wear at Anti-Vibration Bar (AVB).
2.
Previously degraded tube.
3.
Previously reported as 62 which included 38 non-degraded flagged tubes.
4.
Previously reported as 80 which included 33 non-degraded flagged tubes.
5.
Previously reported as 49 which included 7 non-de-graded flagged tubes.
The examinations were performed satisfactorily.
d.
Data Review and Evaluation, Unit 3 (73755)
The inspector reviewed completed ISI examination records and the supporting certification for:
examiner qualification, certification and visual acuity; PT cleaner, penetrant and developer; HT powder, yokes and 10 Lbs. test weights; and UT instruments, transducers, and couplant.
The inspector also reviewed baseline data of the welds to determine whether the indications were previously recorded and if so, were there any noticeable differences in the recorded informa-tion.
Records for the following welds and the supporting data were reviewed:
Examination Records Examined Exam Item 6"-BDA-2301-6 6" -BDA-2301-5 6" -BDA-2301-8 6"-BDA-2301-1 6"-BDA-2301-1 6"-BDA-2301-8 6"- BDA-2301-6 6"-BDA-2301-5 Blowdown Blowdown Blowdown Blowdown Blowdown Blowdown Blowdown Blowdown System Hethod UT UT UT UT HT HT HT HT
Exam Item Examination Records Examined System method 2"-CH-1305-4 2"-CH-1305-FB2 2" -CH-1305-1 2"-CH-1305-2 1. 5" -CH-1303-3 2"-CH-1305-3 SR-142 5 IA SR-172
& IA 3-ARH-91-IA 14"-FWA-2301-21B 31"-RCS-1302-1 4"-RC-1304-10 31"-RCS-1302-8 Chemical and Volume Chemical and Volume Control Control Chemical and Volume Control Chemical and Volume Control Chemical and Volume Control Chemical and Volume Control Component Cooling Component Cooling Component Cooling Feedwater Reactor Coolant Reactor Coolant Reactor Coolant 27)"-RCS-1306-4 Reactor Coolant 27j"-RCS-1306-1 Reactor Coolant 31"-RCS-1302-10 Reactor Coolant 27("-RCS-1306-3 Reactor Coolant 3-WH-12 3-WH-12 8"-SI-2309-21 8"-SI-2309-22'"-SI-2309-23 8"-SI-2309-20 8"-SI-2309-22 8"-SI-2309-24 8"-SI-2309-20 8"-SI-2309-21 8"-SI-2309-24 8"-SI-2309-23 RPV Closure Head RPV Closure Head Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection Safety Injection 1.5"-CH-1303-FBI Chemical and'olume Control VT-1 PT VT-1 PT PT PT PT VT-3 VT-3 VT-3 HT PT PT PT PT PT PT PT UT HT PT PT PT PT UT PT UT UT UT UT
NDE Equipment and Consumables Records Examined Equipment/Consumables Serial No/ Heat No./ Lot No./
Batch No.
PT Cleaner PT Developer PT Penetrant HT Red No.
8 Powder HT 10 LBS. Test Weight HT Yokes UT Instruments UT Transducers UT Couplant ET HIZ-18 Remote Data Acqui-sition Units (RDAU)
ET Calibration Standards Thermometers 93L07K 92A01P 91H02K 93-018 14A 205 and 2043 136-592G, 300D, and 590G J16828, H11823, H11829, B1009, C19408)
D0401, B0133, and E04502 091011 46, 124, 130, 137, 240, and 241 Z-12309, Z-12310, Z12311, Z-12316, Z-12317, Z12318, Z-12319, Z-12320, Z-12321, and Z-12322 94-004)94-005, 94-008, 013,93-018 and 93-021 qualification, Certification, and Visual Acuity Records Examined Examiner Hethod-Level RJV UT-II PT-II HT-II RJV RG NAB PT-II HT-II VT1-II VT1-II VT1-II DRR UT-III BB UT-IT PT-I JN UT-II PT-II HT-II JV UT-IT SC UT-II PT-II HT-II VT3-II
gualification, Certification, and Visual Acuity Records Examined Examiner STF RAL Method-Level MT-IT PT-II FTC UT-III PT-III DAL VRL ASH MAR JCG SJP JEA DPC FLH LRJ LDH GTB WKH WDJ AM KSA PAM RLS WAG TAH ET-IIA ET-III ET-IIA ET-III ET-I ET-I ET-I ET-I ET-II ET-II ET-IIA ET-IIA ER-IIIA ET-IIA ET-IIA ET-IIA ET-IIA ET-IIA ET-IIIA ET-III Records support the conclusion that examinations were conducted in accordance with applicable procedures and regulatory commitments.
Within the areas examined no violations or deviations were identifie '
,
Flow Accelerated Corrosion (FAC) (49001)
The licensee has established a
FAC inspection program which implements the CHECHATE EPRI (Electric Power Research Institute) computer code, industry experience, and previous inspection data as predictive tools for determining and prioritizing inspection locations.
The inspector conducted interviews with licensee and contractor personnel and reviewed records as indicated below.
Observations/Findings During RFO 14, the licensee planned to examine 203 locations in their FAC program.
At this writing the licensee had identified 38 FAC degraded components for replacement:
25 planned from previous outage examinations and
as a result of examinations this outage.
The sample has now expanded to 239 areas, and examination continues.
The remaining life of components was not calculated in the past.
This calculation if done would have provided an effective means to schedule reinspection of components to achieve maximized results.
Remaining life calculations are included in the corporate program, but to date there is no formal mechanism established to track the data to make it useful.
4.
Notwithstanding the above, the licensee has established an effective program to maintain high energy carbon steel piping systems within acceptable wall thickness limits.
Within the areas examined, no violations or deviations were identified.
Exit Interview The inspection scope and results were summarized on April 29, 1993, with those persons indicated in paragraph 1.
The inspector described the areas inspected.
Although reviewed during this inspection, proprietary information is not contained in this report.
Dissenting comments were not received from the licensee.
The licensee provided the inspector with the cumulative S/G ET examina-tion results by telephone on Hay 3, 1994.
5.
Acronyms and Initialisms ABBCE ANA ASHE AVB BKPV BDA CH CSI DPR EPRI Assea Brown Boveri Combustion Engineering Allen Nuclear Associates Inc.
American Society of Hechanical Engineers Anti-Vibration Bar Boiler and Pressure Vessel Blowdown Chemical Volume and Control Component, Support, and Inspection Demonstration Power Reactor Electric Power Research Institute
ET FAC FC FL FPKL FWA ID ISI M-L MT NDE No.
NRC P.E.
RFO RI RPC RPV S/G SI SRI UT VT w/
Eddy Current Flow Accelerated Corrosion Field Change Florida Florida Power and Light Feedwater Identification Inservice Inspection Master-Lee Magnetic Particle Nondestructive Examination Number Nuclear Regulatory Commission Professional Engineer Plant Change Notice Liquid Penetrant Quality Assurance Reactor Coolant Remote Data Acquisition Unit Revision Refueling Outage Resident Inspector Rotating Pancake Coil Reactor Pressure Vessel Steam Generator Safety Injection Senior Resident Inspector Ultrasonic Visual with