IR 05000250/1991001
| ML17348A890 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/01/1991 |
| From: | Gray E, Harris R, Modes M, Peterson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17348A889 | List: |
| References | |
| 50-250-91-01, 50-250-91-1, 50-251-91-01, 50-251-91-1, NUDOCS 9103050461 | |
| Download: ML17348A890 (15) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION REGION 9 DOCKET NO.
REPORT NO.
$~20
~0-2~1-2
/ 1-
-2 1/
1-
LICENSE NO.
~DPR-I DPR-41 LICENSEE:
We t Fla ler'ree Mi mi Flori 33174 FACILITYNAME: T RKEY POINT P WER PLANT d dddONdd.'d~id d
id INSPECTION CONDUCTED:
nuar
1 1 t J nua
1
INSPECTORS:
M. C. Modes, Project Manager NDE, Materials date and Processes Section, EB, DRS R. H. Harris, NDE T hnician, Materials and Processes Section, EB, DRS z/(/vi date P. M. Peterson, NDE Technician, Materials and Processes Section, EB, DRS D. C. Wiggins; TET, Inc.; Mobile, Alabama W. M. Mingus; TET, Inc.; Mobile, Alabama date E. H. Gray, Chief, Mate als, and Processes Section, EB, DRS, Region I
</i Je date 910305046i 910222 PDR ADOCK 05000250
Ins ection Summa nd ncl i n A routine announced inspection was conducted at Turkey Point Power Plant Units 3 and 4 during the period January 7, 1991 through January'18, 1991 using the NRC's Mobile Nondestructive Examination (NDE) Laboratory
.
(Report No. 50-250 & 251/91-01)
IL a:
S 1 W fU*
g
fM byp y
(SGFB),
reactor coolant safety injection system (RCSI), main steam system (MS), residual heat removal (RHR), atmospheric cleanup system (AC), component cooling water system (CCW),
and feedwater (FW) piping were independently examined by NDE methods.
The licensee's procedures used for nondestructive evaluation and the licensee's evaluation results, including radiographs and ultrasonic test reports, were reviewed.
Re~jul r. No violations or deviations were identified in the review of the program areas examine DETAILS 1.0 Person ntacted:
rolin P wer and Li h P L
- K. Remington
- M. Blew
- A. Zielonka W. Blandon
- L. Pearce
- D. Powell
- J. Mack
- M. Abside J. O'rien M. Huba T. Finn J. Knorr R. Turner System Performance Supervisor ISI Coordinator Technical Department Supervisor Quality Manager Plant Manager Licensing Superintendent IST Coordinator Licensing Q.C. Superintendent Engineering Operations Licensing ISI Staff Nuclear Re ul to R. Butcher
- G. Schnebli
- L. Trocine
- J. Coley
- J. Blake
- E. Gray.
ommission Senior Resident RII Resident Inspector RII Resident Inspector RII Reactor Inspector MI Chief, MPS RII Chief, MPS RI
- Denotes those attending the exit meeting on January 17, 1990 The inspector also contacted other administrative and technical personnel during the inspection.
2.0 Inde endent Mea urement
- NR Nondestructive Examinati n and ualit Records Review of afet Relat stem Concurrent with a refueling outage during the period January 7th through January 18th 1991, an onsite independent inspection was conducted at Florida Power and Light's (FP&L) Turkey Point Power Plant utilizing the NRC Mobile NDE Laboratory. The inspection was conducted by NRC regional based inspectors and NRC contracted NDE personnel. The objectives of this inspection were to assess the adequacy of the licensee's inservice inspection program gSI), and welding quality control program.
ASME Code pipe weldments, supports and pipe were independently
examined by various NDE methods. Included in this examination were components, welds and areas selected from the steam generator feedwater bypass system (SGFB),
reactor coolant safety injection system (RCSI), main steam system (MS), residual heat removal (RHR), atmospheric cleanup system (AC), component cooling water system (CCW), and feedwater (FW) piping. This was accomplished by duplicating those examinations required of the licensee by regulations and codes, then evaluating the results.
2.1 Monde tructive Examination E
2.2 Visual Examin ti n
\\
Sixteen (16) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were visually examined in accordance with NRC procedure NDE-10, Rev. 1, Appendix A, and FPEcL procedure NDE-4.3 Rev 2.
Visual examination was performed of pipe systems and attached components utilizing QC documents, isometrics and as-built drawings.
Examined during this inspection were ASME Class 1 and Class 3 pipe weldments selected from the SGFB, MS, RCSI, RHR, FWB and FW systems.
The examination was performed specifically to identify any cracks or linear indications, gouges, leakage, arc strikes with craters, or corrosion, which may infringe upon the minimum pipe wall thickness.
Mirrors, flash lights and weld gauges were used, as required, to aid in the inspection and evaluation of the weldments.
~Re nlt: No violations or deviations were identified in the review of this program area.
2.3 Li uid Penetrant Examinati n 5706 Eleven (11) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye, solvent removable, liquid penetrant method per NRC procedure NDE-,9, Rev.0, in conjunction with the licensee's procedure NDE 3.3, Rev 2. Included in this inspection were ASME Class 2 weldments selected from the RCSI and MS systems and ASME Class 2 weldments from the RHR system.
Arc strikes were noted on two of the welds in the RCSI (16"-SI-341:Weld 6 and 2"-SI-1303:Weld 8). Although arc strikes are not specifically prohibited by the ASME Code they are a concern.
These two welds were brought to the attention of the licensee for corrective action in keeping with their quality control program and technical specifications.
REQJLTS:
No violations or deviations were identified in the review of this program are.4 Ma neticP i leEx min i n 7070 Sixteen (16) safety related pipe weldments including the adjacent base material (1/2 inch on either side of the weld) were examined using the direct contact, magnetic particle method utilizing a solid state yoke with dry powder as the inspection medium. The examination was performed in accordance with NRC procedure NDE-6, Rev.1 in conjunction with the licensee's procedure NDE 2.2, Rev 2 (FCA) and associated QC records. Included in this examination were ASME Class 3 and ANSI B31.1 pipe weldments selected from the SGFWB, MS, and FW systems.
~Result:
No violations or deviations were identified in the review of this program area.
2.5 Radi ra hic Examin i n
0 Twelve (12) safety related pipe weldments were examined using an Iridium 192 source which resulted in thirty nine (39) radiographs being produced. The method of radiography was in co'nformance with the requirements of NRC procedure NDE-5, Rev.1 in conjunction with the licensee's radiographic procedure TS 9.3, Rev 1.
Results The resulting radiographs were compared to radiographs produced by the licensee to ensure that the welds identified were the same as those identified by the NRC.
The radiographs compared favorably in all cases.
The licensee's radiographs revealed the same weld imperfections, flaws and anomalies as the NRC's radiographs. In three cases, original construction radiographs were obtained for the welds being analyzed.
The original radiographs were fourteen years old. The original radiographs did not reveal any archival degradation and were in conformance with the requirements imposed at the time they were produced.
No violations or deviations were identified in the review of this program area.
2.6 I
onic Ex min ti n
Eight (8) welds in the RCSI, FW, RHR and MS systems were ultrasonically examined using a Stavely Model 136D ultrasonic flaw detector in accordance with NRC procedure NDE-1, Rev.'1 and FP&L procedures for ASME weldments; NDE 5.2, Rev. 4 (Ferritic Piping) and NDE 5.4, Rev 7 (Austenitic Piping).
The Stavely Model 136D was verified for linearity in
conformance with NRC procedure NDE-2, Rev 1. To obtain the greatest possible repeatability the examination was undertaken utilizing transducers and cable that matched those used by the licensee as. closely as possible. The distance amplitude compensation curve was established utilizing FP&L calibration standards as listed in the table on page 9 of this report.
~Rgi~l: No violations or deviations were identified in the review of this program area.
2.7 Erosion/Corr si n
Concern regarding erosion and corrosion in balance of plant piping'ystems has been heightened as a result of the December 9, 1986 feedwater line rupture that occurred at Surry Unit 2.
This event was the subject of NRC Information Notice 86-106 issued December 16, 1986 and its supplement issued on February 13, 1987.
The licensee's actions with regard to the detection of erosion/corrosion in plant components were reviewed with respect to NUREG-1344, "Erosion/Corrosion Induced Pipe Wall Thinning in U. S. Nuclear Power Plants", dated April 1989, Generic Letter 88-08 issued May 2, 1989, and NUMARC Technical Subcommittee Working Group on Piping and Erosion /Corrosion Summary Report dated June 11, 1987.
The program, in general, follows the guidance found in the NUMARC report.
The selection, trending and tracking of systems is based on the computer programs "CHEC" and "CHECMATE" developed by the EPRI NDE Center.
In addition to the program review discussed above, two areas originally inspected by the licensee were reinspected by the NRC NDE team.
The results were compared and the measurements were found to be in close agreement.
R~tesult:
No violations or deviations were identified in the review of, this program area.
3.0 Review f ite NDE Pr edure nd Manual The following Florida Power and Light procedures were reviewed in the regional office during this inspection period for compliance to the licensee's FSAR commitments, technical specifications, applicable codes, and standard,h
l
'I
Procedure NDE 2.2 Title Magnetic Particle Examination Rev.
FCA ate 5/25/88 02/20/90 NDE 3.3 NDE 4.1 NDE 4.3 Liquid Penetrant Examination Solvent Removable Visible Dye Technique Visual Examination VT-1 for Welds/Bolting/Bush-ings/Washers Visual Examination VT-3/VT-4 02/02/89 01/26/90 01/26/90 Procedure Title Rev.
Date NDE 5.1 NDE 5.2 NDE 5.3 NDE 5.4 NDE 5.5 Ultrasonic Examination of Pressure Vessel Welds Except Reactor Vessels Ultrasonic Examination of Ferritic Piping Welds Ultrasonic Examination of Primary Coolant Piping Welds (PSL-I &2)
Ultrasonic Examination of Austenitic Piping Welds Ultrasonic Examination of Main Coolant Main Piping Welds
FCA 05/23/88 05/25/88 02/09/89 10/26/90 09/14/88
'1/17/86 NDE 5.8 Ultrasonic Examination of Bolting Material for Cracking 07/12/88 NDE 5.9 Ultrasonic Examination of Bolting Material for Corrosion 07/12/88 NDE 5.10 Ultrasonic Examination of Nuts Two Inches in Diameter or Greater 05/12/88 NDE 5.11 Ultrasonic Examination of Dissimilar Metal Piping Welds 05/25/88
NDE 5.16 Ultrasonic Examination Tech-for the Evaluation of Cracking in Steam Generator Feedwater Piping 05/23/88 NDE 5.18 Ultrasonic Thickness Measure-ment 02/07/90 Ts 9.3 Radiographic Inspection 02/14/84 No violations or deviations were identified in review of the above procedures.
4,0 S no sis Of N nde tructive In ecti n Re ult WELD IDENTIFICATION SYSTEM NONDESTRUCTIVE TEST ACCEPT/
REJECT CODE RT UT MT VT 5610-M-341 UNIT 4, VALVE 4-489 WELD FW-1 5610-M-341 UNIT 4 VALVE 4-489 WELD FW-2 5610-M-341 UNIT 4 VALVE 4-499 WELD FW-1 5610-M-341 UNIT 4 VALVE 4-499 WELD FW-2 16"-SZ-2301 UNIT 3 VALVE 3-864B WELD 5 SGFWB 1.26 D
SGFWB 1.26 D
SGFWB 1.26 D
SGFWB 1'6 D
RCSZ 1.26 C
X X
ACCEPT ACCEPT ACCEPT ACCEPT ACCEPT 16"-SZ-341 UNIT 3 VALVE 3-864B WELD 6 AGREE 16"-SI-2401 UNIT 4 TANK CONNECTION WELD 1 16"-SI-2401 UNIT 4 VALVE MOV-4-864B WELD 5 2"-SI-1303 UNIT 3 WELD 7 RCSI 1.26 C
RCSI 1.26 C
RCSI 1.26 C
RCSZ 1.26 B
X ARC STRIKES NOTED
"
ACCEPT ACCEPT ACCEPT
WELD IDENTIFICATION SYSTEM CODE'T UT PT MT VT NONDESTRUCTIVE TEST ACCEPT/
REJECT 10"-SI-1302 UNIT 3 WELD 14 LOOP B
AGREE 8"-RHR-1303 UNIT 3 WELD 2 LOOP B AGREE 14"-RHR-1301 UNIT 3 WELD 9 LOOP C 'GREE 8"-RHR-1301 UNIT 3 WELD 1 LOOP A AGREE 10" SUPPORT
-
UNIT 3 3-ACH-29 DWG 5613-H-602 AGREE 26" SUPPORT UNIT 3 A
DWG 5613-H-654 AGREE 14" SUPPORT UNIT 3 3-RCH-10 DWG 5613-H-669 14"-MSC-2306 UNIT 3 WELD 1
~ LOOP C
16" SUPPORT UNIT 3 SR-158 DWG 5613-H-596 AGREE RCSI 1.26 B
1.26 B
1.26 B
1;26 B
AC CL B MS CL B CL A MS 1.26 D
CCW CL C X
X X
CAL:UT-27 X
X X,
CAL:UT-41 I AN.
ACCEPT ACCEPT X
CAL:UT-30 I AN.
X X
ACCEPT X
CAL:UT-41 ACCEPT X
ACCEPT X
ACCEPT X
ACCEPT X
ACCEPT X
ACCEPT X
ACCEPT X
X ACCEPT NOTE: 'Z.N.
~ Indication Noted in the Weld
WELD IDENTIFICATION PAGE 3/3 14"-MSC-2306 UNIT 3 WELD 4 LOOP C
AGREE 26"-MSB-2405 UNIT 4 WELD 5 LOOP B
SYSTEM CODE MS 1.26 D
MS 1.26 C
CALs UT-21 NONDESTRUCTIVE TEST ACCEPT REJECT ACCEPT I.N.
ACCEPT 14" SUPPORT UNIT 4 4-SR-623 DWG 5614-H-503 AGREE 14" SUPPORT UNIT 4 SR-450C DWG 5614-H-509 AGREE 14" SUPPORT UNIT 4 4-SR-626 DWG 5614-H-503 AGREE 16" SUPPORT UNIT 4 4-ACH-267 AGREE DWG 5614-P-501-S 14" SUPPORT UNIT 4 4-FWH-26 DWG 5614-H-770 AGREE 14" SUPPORT UNIT 4 4-FWH-38 DWG 5614-H-770 AGREE 14"-FW-2401 UNIT 4 WELD 3 LOOP A CL B CL B CL B CCW CL C FW CL B FW CL B FW 1.26 C
X X
X X
CALs UT-20 X
X ACCEPT ACCEPT ACCEPT ACCEPT ACCEPT ACCEPT ACCEPT ACCEPT NOTEs I.N. = Indication Noted in the Weld
WELD IDENTIFICATION SYSTEM NONDESTRUCTIVE TEST ACCEPT REJECT 14"-MSA-2401 UNIT 4 WELD 2 LOOP A CODE MS 1.26 D
VT X
ACCEPT 14"-MSA-2302 UNIT 3 WELD 5 LOOP A 6"-FW-2403 UNIT 4 WELD 3 LOOP C
14"-MSC-2405 UNIT 4 WELD 5 LOOP C
MS 1.26 D
FWB 1.26 MS 1.26 D
X ACCEPT ACCEPT X
ACCEPT 2"-SI-1303 UNIT 3 WELD 8 2"-.SI-1303 UNIT 3 WELD 10 14"-MSA-2302 UNIT 3 WELD 2 LOOP A RCSI 1.26 B
RCSZ 1.26 B
MS 1.26 D
ARC STRIKES NOTED ACCEPT ROOT CON-CAVITY 14"-MSA-2401 UNIT 4 WELD 5 LOOP A MS 1.26 D
X ACCEPT 14"-FW-2402 UNIT 4 WELD 3 LOOP B
FW X
CAL: UT-20 ACCEPT 1.26 C
X X
ACCEPT 14"-FW-2403 UNIT 4 WELD 3 LOOP C
FW 1.26 C
X GALS UT-20 ACCEPT X
X ACCEPT
tl 5.0 Mana ement Meetin
Licensee management was informed of the scope and purpose of the inspection at the entrance interview on January 7, 1991. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the exit interview (see paragraph 1.0 for those who attended).
At no time during the inspection was written material provided to the licensee by the inspector. The licensee did not indicate that proprietary information was involved within the scope of this inspection.
I