IR 05000250/1991028
| ML17348B083 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/16/1991 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17348B082 | List: |
| References | |
| 50-250-91-28, 50-251-91-28, NUDOCS 9109100065 | |
| Download: ML17348B083 (8) | |
Text
~Q 8EQ(1~
VpO C'y 0O C
gO
+>>*++
UNITEDSTATES NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTASTREET, N.IN.
ATLANTA,GEORGIA 30323 Report Nos.:
50-250/91-28 and 50-251/91-28 Licensee:
Florida Power and Light 9250 West Flagler Street Miami, FL 33102 Docket Nos.:
50-250 and 50-251 License Nos.:
DPR-31 and DPR-41 Faci'lity Name:
Turkey Point 3 and
Inspection Conducted:
July 29 - August 2, 1991 Inspector:
o ey Approved by:
J J
Blake, Chief a
rials and Processes Section E gineering Branch Division of Reactor Safety ate sgne
= (~/1 Date Signed SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of review of completed inservice inspection (ISI) examination records which also included augmented inspections, evaluations, and disposition of examination findings; and review of radiographic film for new welds resulting from modifications performed during the 1991 extended outage of Units 3 and 4.
Results:
In the areas inspected, violations or deviations were not identified.
The licensee's ISI examination records documented examinations and discontinuities in a
very effective manner.
Evaluations and disposition of examination findings were also effectively analyzed and resolved.
The inspector's review of radiographic film revealed excellent radiographic technique, good work practice, and sound judgment in the evaluation and disposition of discontinuities.
In addition, it was obvious from the review of data and discussions with cognizant personnel that management and the licensee's technical staff assure that technical issues are resolved conservatively.
1091000h5 910822 PDR ADQCK 05000250 PDR
REPORT DETAILS Persons Contacted Licensee Employees
- J. Arias Jr.,Senior Technical Advisor to the Vice President
, *W. Bladow, Quality Manager
- M. Blew, ISI Coordinator
- D. Councill, Quality Control Specialist, Mechnical and Welding
- M. Huba, Lead Nuclear Engineer JPN
- J. O'rien, Quality Control Superintendent
- T. Plunkett, Site Vice President
- D. Powell, Licensing Superintendent
- K. Remington, System Performance Supervisor
- R. Turner, ISI specialist
- M. Wayland, Maintenance Superintendent
- A. Zielonka, Technical Department Supervisor Other licensee employees contacted during this inspection included managers, engineers, specialists, and technicians.
NRC Resident Inspectors
- R. Butcher, Senior Resident Inspector
- G. Schnebli, Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the-last paragraph.
Inservice Inspection Data Review and Evaluation, Units 3 5 4 (73755)
The inspector reviewed completed examination records, evaluations, and engineering disposition of findings, to determine whether ISI records were in fact complete, within previously established acceptance criteria, and whether the licensee's disposition of adverse findings and subsequent re-examination if necessary was consistent with regulatory requirements.
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 XI, 1980 Edition with Addenda through Winter l981.
Completed examinations records for all of the nondestructive examination (NDE) methods were reviewed for completeness.
However, the inspector selected a
sample with findings for detailed review by using the ISI Customer Notification Reports (CNR's)
and then working backwards to the examination reports that recorded the findings.
The following CNR's and applicable examination reports including all other supporting information were reviewed by the inspector:
288500 061300 120300 066500 066450 062250 116700 174750 115300 122440 071320 071550 135440 163440 163460 317900 303000 304500 306700 301000 30900 327700 302400 314200 299300 288450 128150 275850 119450 287400 209490 314000 217740 280650 280250 279050 279650 322400 300600 329300 327400 077450 325500 323700 014500 145500N 128300 122400 T.NN.
N N
4
4
4
4,
4
4
4
4
4
4
4
4
4
4
4
4
3
3
3
Method MT PT PT VT-1 YT-1 VT-1 VT-1 VT-1 VT-1 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-,3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT<<3 VT-3 MT MT MT PT PT PT Com onent/Weld ID 14" FWC-2403-10 29" RCS-1408-4 10" SI-1401-14 RV-4-551C BOLTING 4"-RC-1403-FB1 14"-RC-1401 MOV-4-751 BOLTING 2"-CH-1403-FB MOV-4-750 BOLTING 8073-H-826-01 4-RCH-30A 4-RCH-30 M-711A-5 4-VCH-74 SR-488 4-ACH-185 SR-705 4-ACH-28 4-ACH-46 4-ACH-207IA 4-ACH-207 80117-H-341-06 SR-694 4-ACH-182 4-ACH-50 4-FWH-13 SR-451 78102B-H-422-05 SR-450C 4-FWH-26 4-SR-626 4-ACH-267 4-SR-623 4-FWH-38 78102 8-H-423-06 78102B-H-423-17 78102B-H-423-11 80117-H-324-04 4-ACA-212 8123-H-254-02 80117-H-341-08 4-RCH-4 6" BDC-2306-FW-30 6" BDC-2303-FW-29 3-WH-12 2" SI-1303-8 10".SI-1302-14 14" RHR-1301-9 CNR IF 024 045 040 026 027 034 035 036 038 043 044 044 044 044 044 015 016 017 018 019 019 020 021 022 023 025 031 037 039 005 001 002 003 004 007 007 007 009 011 012 013 014 007 024 052 002 003 004
.NO.
Method Com onent/Weld ID CNR 0 126000 247100 048800 202800 060900 154100 141200 145300 139000 051200 127000 123300 321200 278100 175000 153500 356200 346010 364800 212000 289400 286900 283300-2670700
3
3
,3
3
3
.3
3
3
3
3
3
. VT-I VT-1 VT-1 VT-1 VT-1 VT-3 VT-3 VT-3/4 VT-3 VT-3/4 VT-3 VT-3 VT-3 UT UT UT UT UT 8" RHR-1301-1 005 16" SI-2301-6 006 31-RCS-1303-5 049 RCP-SPB-L2 056 PCP-3-355B 018 3-866-B VALVE BOLTING 037 3-868-B VALVE BOLTING 044 3-868-C VALVE BOLTING 045 3-868-A VALVE BOLTING 046 GENERAL VISUAL/BU-88-80 048 3-875B VALVE BOLTING 059 3-875D VALVE BOLTING 053 78101B-H-'322-05 043 SR-165-SPRING HANGER 039 FSK-M-146 BOX RESTRAINT 038 8086-H-010-14 036 3-SMH-15 ROD HANGER 032
= 3-ARH-105 RIGID HANGER 030 3-BAH-26 SPRING CAN 023 3-SG-C-CL 050 14" FW LOOP-C(AUGMENTED) 028 14" FW LOOP-B(AUGMENTED) 029 14" FW LOOP-A(AUGMENTED) 030 14" MSC-2405-1 006 The inspector's review of the above examination records revealed that they were in compliance with the licensee's ISI program, the applicable nondestructive examination (NDE)
procedure, commitments to NRC for augmented examination, and the ASME Code.
In most cases the examination records were strongly supported with sketches, photographs,=video tapes, and descriptive documentation.
One exception was noted however.
Evaluations of discontinuities found during ultrasonic examinations were inconsistent in providing calulations for determining their acceptance.
This concern was discussed with plant management who indicated that the matter would be properly addressed.
Not all of the CNR's reviewed, particularly on Unit 3, had been completed because repair work, or re-examination of the repair, required by the engineering disposition were still in-process.
The inspector also noted that the licensee had detected acceptable crack initiation in the elbows off the A, B, and C Steam Generator Feedwater Nozzles on Unit 4.
These examinations were conservatively examined in Accordance with NRC Bulletin 79-13,
"Cracking in Feedwater System Piping".
All of the reported indications were below 25%
DAC and
exhibited very little through-wall travel.
The steam generator feedwater pipe cracking has been a recurring problem on Unit 4 and has resulted in this piping being replaced twice previously (1980 5 1984).
The new indications will be re-examined for growth during each subsequent outage.
Examinations performed on Unit 3 steam generator feedwater piping did not reveal any cracks.
Within the areas examined, no violation or-deviation was identified.
Review of Radiographic Film - Units
8 4 (57090)
The inspector reviewed radiographic film and associated weld packages for the welds listed below to determin'e whether they had been examined in accordance with regulatory requirements and the licensee's approved Radiographic Procedure No. TS-9.3 Rev. l.
All of the welds exayined were the result of plant modifications performed on Units 3 and 4 during the 1991 extended outage on each unit.
The inspector's review of the radiographic procedure revealed it to be well written technically, covering all code requirements in a clear and conservative manner.
Radiographs for the following ASME Code Class
and
welds were examined:
WEl D ID NO.
FW-3A-2 FW-38-2 FW-3C-4 W-4A-2 W-4B-2 W-4C-4 Weld 5 FW-3 FW-1 FW-4 FW-8 FW-5 FW-6 FW-4 FW-1 FW-2 FW-17 FW-7 FW-5 FW-4 FW-16 FW-3 FW-4 FW-6
.,FW-37 FW-39 FW-45 UNIT/IR
3
4
3
3
W91-1116 W91-7101 W91-6833 W91-7100 W91-5846 W91-5778 W91-1066 W91-1037 W91-1036 W91-1035 W91-0662 W91-5757 W91-7038 W91-7037 W91-3594 W91-3596 W91-3599 SYSTEM RCS RCS RCS RCS RCS RCS RHR RHR RHR RHR MS NS NS NS NS NS MS MS MS NS MS NS, NS MS CYCS CYCS CVCS SIZE 3llDia 3 IIDia 3"Dia.
,3 "Dia.
3"Dia.
3"Dia.
10"Dia.
10"Dia.
IO"Oia.
10"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
6 IIDia 6"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
6"Dia.
2"Dia.
2"Dia.
2"Dia.
COMMENTS
.
RTD Loop "A" RTD Loop "B" RTD Loop "C" RTD Loop "A" RTD Loop "B" RTD Loop "C" Pipe Replacement Pipe Replacement Pipe Replacement Pipe Replacement Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Atmosphere Disch.
Discharge R/V Line Discharge R/V Line Discharge R/V Line
WELD ID NO.
UNIT/IR SYSTEM SIZE COMMENTS FW-49 FW-57 FW-59 FW-61 FW-1 FW-6 FW-13 W91-3601 W91-3604 W91-3605 W91-3606 W91-3607 W91-3608 W91-3609 CVCS CVCS CVCS CVCS CVCS CVCS CVCS 2"Dia.
2"Dia.
2"Dia.
2"Dia.
2"Dia.
2"Dia.
2"Dia.
Discharge Discharge Discharge Discharge Discharge Discharge Discharge R/V Line R/V Line R/V Line R/V Line R/V Line R/V Line R/V Line The, inspector reviewed the radiographs listed above to verify that the following radiographic parameters were in accordance with the approved procedure:
penetrameter type, size, and placement; penetrameter sensitivity; film density, and density variation; film identification; film quality; and weld coverage.
In addition to the preceeding radiographic quality and coverage verifications, the inspector reviewed the radiographs to'etermine whether they were evaluated and.
dispositioned in accordance with the requirements and acceptance criteria of the approved procedure.
The inspector's review concluded that the radiographs for the welds listed above met or exceeded code requirements for both radiographic quality and weld acceptance.
Note:
Densitometer used:
S/N FPL-PTP-4302 Calibrated 7-27-91 Within the areas examined, no violation or deviation was identified.
Exit Interview The inspection scope and results were summarized on August 2, 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.
No dissenting comments were received from the license Acronyms and, Initialisms ASME BSPV DAC FPL ID IR ISI MT NDE No.
NRC PT QA QC UT VT CNR RHR CVCS RCS MS DISH RTD American Society of Mechanical Engineers Boiler and Pressure Vessel
. Distance Amplitude Curve Florida Power and Light Identification Inspection Report Inservice Inspection Magnetic Particles Nondestructive Examination Number Nuclear Regulatory Commission Liquid Penetrant Quality Assurance Quality Control Ultrasonic Visual Customer Notification Report Residual Heat Removal System Chemical and Volume Control System Reactor Coolant System Main Steam System Discharge Reactor temperature Detector