L-96-166, Forwards Response to Request for Addl Info Re Review of SG Tube Insp & Repair Criteria for Unit 1
| ML17228B535 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/25/1996 |
| From: | Stall J FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-96-166, NUDOCS 9606270259 | |
| Download: ML17228B535 (75) | |
Text
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ACCESS iON NBR:9606270259 DOC.DATE: 96/06/25 NOTARIZED: NO FACIAL:50-335 St. Lucie Plant, Unit 1, Florida Power a Light Co.
AUTH.NAME AUTHOR AFFILIATION STALl,J+...
Florida Power 6 Light Co.
RECIP.AAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to request for addi info re review of SG tube insp
& repair criteria for Unit l.
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Florida Power 5 Light Company, P.O. Box128, Fort Pierce, FL34954-0128 June 25, 1996 L-96-166 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555 RE:
St. Lucie Unit 1 Docket No. 50-335 Steam Generator Tube Inspection Re uest for Additional Information (RAI) Res onse As a result of a meeting with Florida and Light Company (FPL) on April 22,
- 1996, the NRC has been reviewing the steam generator inspection and repair criteria for St. Lucie Unit 1.
In order to complete their review, the NRC identified the need for additional information.
The specific information needed was identified in the enclosure to your letter dated May 24, 1996.
In a conference call on June 5,
- 1996, the NRC staff extended the response date for the RAI to June 25, 1996.
The extension of the response date was based on the expanded scope of inspection of the St. Lucie Unit 1 steam generators being performed by FPL.
The responses to questions and the supporting information are enclosed.
Please contact us if there are additional questions.
Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/GRM cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9'606270259 960625 PDR,'DQCK 05000335 I
8 PDR pnl ~i an FPL Group company
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St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 1
Request for Additional Information Responses NRC Request 1
The repair criteria to be used to,disposition eddy current indications (e.g.,
indications at the expansion transitions, drilled hole tube support plate intersections, and in the free span)
FPL Response Eddy current indications of tube degradation at tube expansion transitions and drilled support plate intersections will be removed from service based on detection by motorized rotating pancake coil (MRPC) inspections.
Circumferentially oriented degradation will be stabilized.
Eddy current indications of tube degradation in free span regions which are crack-like will be removed from service based on detection by MRPC inspection.
Free span indications which are not crack-like by MRPC inspection may remain in service provided the indication was present on pre-service baseline inspection data and the through-wall bobbin coil depth is less than 40%.
Request 2
The qualification data supporting the sizing capability of indications in the sludge pile and the eggcrate supports (e.g.,
eddy current determined depth and length, destructive examination
- length, destructive examination average and maximum depth).
FPL Response Qualification data supporting the sizing capability of indications in the sludge pile and eggcrate supports is provided as Enclosure 2 of this letter.
The qualification effort includes all available destructive examination results for tubes pulled from sludge pile and eggcrate regions in Combustion Engineering (CE) design steam generators.
The results for this qualification exceed the Electric Power
St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 2
Research Institute (EPRI) requirements, PVR Steam Generator Exami na tion Gui delines, Appendix H,
for threshold and probability of detection and sizing accuracy.
Applicable correspondence, eddy current determined depth and
- length, destructive examination
- length, and destructive examination average depth and maximum depth are included.
Eddy current bobbin coil graphics for tube flaws used for the qualification are also included in Enclosure 2.
Request 3
The 95/95 confidence level values for growth, NDE uncertainty, material properties, and limiting flaw sizes.
For the limiting flaw sizes, the following should be submitted:
(1) the limiting depth given an infinitely long indication, (2) the limiting length given a through-wall indication, and (3) the correlation relating depth and/or length to the structural integrity of the tube.
FPL Response Burst pressure calculations are based on the Framatome equation using average crack depth.
Attachment A Figure 1,
Predicted Burst Pressure Versus Normali zed Observed Burst Pressure PVNGS Unit 2 Pulled Tube Data, shows pulled tube data from Palo Verde Nuclear Generating Station (PVNGS) Unit 2 supporting the use of the Framatome equation.
Attachment A Figure 2,
RPC Crack Length Versus. Structurally significant Crack Length PVNGS Unit 2 Pulled Tube Data, shows that crack length based on pancake coil eddy current data is a
conservative estimate of the structurally significant crack length and Attachment A Figure 3, Maximum Crack depth Versus Avera ge Crack Depth
PVNGS Uni t 2
Pulled tube Da ta, illustrates that the structurally significant portion of the crack profile has a characteristic ratio of maximum depth to average depth.
Attachment A Figure 2 and Attachment A Figure 3 are also based on pulled tube data from PVNGS Unit 2 where the operative degradation mechanism is upper bundle, axial outside diameter stress corrosion cracking/intergranular attack (ODSCC/IGA).
Until plant specific data is obtained, the lower 95 percent tolerance limit for the sum of the yield plus ultimate strength at temperature is taken as 124.4 ksi.
Attachment A
~'t. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 3
Figure 4, Distribution of Sum of Yield and Ultimate Strengths of alloy 600 Tubing at Operating Temperature ANO Unit 2, is a histogram of these sums for Arkansas Nuclear One (ANO) Unit 2 which provides a good correspondence to St.
Lucie Unit 1.
Attachment A Figure 5,
Tube Flow Strength Distribution for Unit 2 Analysis, and Attachment A Figure 6,
Palo Verde Unit 3 Tube Strength Distribution Function, illustrate that other Combustion Engineering (CE) designed units have very similar lower tolerance limit mechanical properties.
In fact the chosen lower tolerance limit value would be a
reasonable choice for all Westinghouse, CE, and Babcock and Wilcox (B&W) steam generators.
Attachment A Figure 7, Preliminary Deterministic Analysis for St. Lucie Unit 2
Axial Corrosion Degradation, is a plot of maximum crack depth versus runtime.
Regulatory Guide 1.121 structural limits on maximum crack depth for St.
Lucie are shown for different crack lengths using lower tolerance limits mechanical properties.
Projected depth versus time is illustrated for both an average and a
95 percent upper bound growth rate, as determined from St. Lucie Unit 1 bobbin probe eddy current data.
Finally, the through wall crack lengths meeting 3 times differential pressure and steam line break differential pressures are listed in a note on Attachment A
Figure 7.
The figures referred to in this response are included as Attachment A of this enclosure.
NRC Request 4
The plans for ensuring adequate operational leakage integrity (e.g.,
adopting industry guidance with respect to program implementation and leakage limits).
FPL Response St.
Lucie Plant off-normal operating procedure (ONOP) 1-
- 0830030, Steam Generator Tube
- Leak, has been revised to incorporate the criteria for shutdown based on primary to secondary leak rates as established in EPRI TR-104788, PNR Primary to Secondary Leak Guidelines, dated May 1995.
St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 4
Request 5
FPL The method for ensuring adequate leakage integrity under postulated accident conditions.
Response
The method to be used to establish end of cycle (EOC) leak rate will be a probabilistic method using a
Monte Carlo numerical simulation of deterministic models for crack opening area and through-wall leak rate.
Statistical distributions for material strengths and through-wall crack lengths are included in the simulation.
The analysis will follow a
mechanistic approach whereby the beginning of cycle (BOC) flaw distributions of undetected flaws will be projected (grown in size) over the cycle to give EOC probability distribution for through-wall cracks (leakers) should a main steam line break (MSLB) occur.
The deterministic leakage model for MSLB conditions is based on a
two-phase fluids model that represents the flow through a
crack.
Non-equilibrium
- flashing, mass transfer between liquid and vapor phases, fluid friction due to surface roughness, and convergent/divergent flow paths are modeled.
Fracture mechanics methods and industry leakage data are used to establish the crack opening area as a function of MSLB pressure and crack length.
The NRC Generic Letter 95-05 will be used as guidance in establishing the EOC leakage acceptance criteria.
Request 6
The distribution of indications detected (length and depth, as appropriate),
the distribution of growth rates (length and
- depth, as appropriate),
the distribution of NDE uncertainty (length and depth, as appropriate).
FPL Response The distribution of defects for St. Lucie Unit 1 is given in Attachment B
Figure 1,
PSI,-1 Distri buti on of'ndicati on Maximum Depths.
The data is from bobbin coil inspection during the current refueling outage (SL1-14) and consists of more than 17000 data points from both steam generators.
The "upper 95 percent probability/confidence value for this data, is less than 40 percent through wall.
St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 5
The distribution of defect growth rates for the St. Lucie Unit 1
bobbin data is given in Attachment B
Figure 2,
PSL-1 Distribution of'ndication Growth Rates.
The upper 95 percent probability/confidence value for this data is less than 32 percent through wall/EFPY.
The defect length distribution for the more limited size rotating pancake coil (RPC) data set is given in Attachment B
Figure 3,
Compari son of'SL1 Crack Lengths wi th Palo Verde Unit 2
Crack
- Lengths, and compared with the length distribution (RPC) obtained for PVNGS Unit 2.
The distributions for the two plants are comparable.
The figures referenced in this response are provided in Attachment B of this'nclosure.
Request 7
A commitment to perform a mid-cycle inspection within six months of startup from the current refueling outage, pending staff review of your mid-cycle inspection criteria and your probabilistic tube integrity assessment.
FPL Response While FPL maintains the highest level of confidence in our steam generator inspection program to predict steam generator tube integrity, we are clearly focused on the performance of the St. Lucie Unit 1 steam generators through their last cycle of operation.
We believe we have historically implemented a
conservative maintenance program of the steam generator tubes and will continue this conservative approach through our last cycle of service with these steam generators.
To determine if a mid-cycle inspection is necessary, FPL will complete a runtime analysis to demonstrate compliance with NRC GL 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracki ng.
The methodology used to compute probability of burst for St. Lucie Unit 1 will incorporate guidance contained in NRC GL 95-05.
This will be particularly true for estimation of defect growth rates.
Since St.
Lucie Unit 1
does not apply a voltage-based repair criteria, the difference
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St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 1 Page 6
between the NRC GL 95-05 model and that proposed for use in the Unit 1 evaluation are:
a.
The principal variables will be defect dimensional attributes rather than NDE voltage.
b.
The burst pressure will be treated deterministically with the exception of randomized material properties.
c.
The probability of detection (POD) will be a function of defect depth.
d.
The defect population followed in the analysis will be inferred from probabilistic initiation, growth, and function of depth.
The proposed analyses will be consistent in structure and implementation with those used for the PVNGS Units 2
and 3
evaluations.
A critical element of our decision-making process on the need for a St. Lucie Unit 1 mid-cycle steam generator inspection is the probabilistic analysis of the potential for, and risk of, steam generator tube failures.
Since the probabilistic anal'yses to address potential for steam generator tube failures are not yet 'complete, FPL does not currently have the information necessary to determine the appropriateness of a mid-cycle inspection.
In light of the above, FPL is unable to commit to a mid-cycle inspection of the St. Lucie Unit 1 steam generators.
FPL is scheduled to meet with the NRC on July 3,
- 1996, to discuss the planned development and technical analysis of the criteria discussed above.
As discussed
- above, FPL will have the results of the analysis and will present the results to the NRC within 90 days following the St.
Lucie Unit 1 startup from the current refueling outage (SL1-14).
By this meeting, FPL will have all the required information to inform the NRC staff of mid-cycle steam generator inspection plans for St. Lucie Unit 1.
St. Lucie Unit 1 Docket No. 50-335 L-95-166 Enclosure 1 Page 7
Attachment A Figures Referenced in the Response to Question 3
't. Lucie Unit 1
, bocket No. 50-335 L-95 166 Enclosure 1
. Attachment A page A'-1 12000 APTSCH E
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<<St.
Lucie Unit 1
,,~Docket No. 50-335 L-95;166 Enclosure 1
Attachment A
, Page A.-2 2.50 APTKCH ENG NEERING ERVICES, INC.
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K 0.50 0.00 0.00 0.50 1.00 1.50 2.00 STRUCTURALLYSIGNIFICANTCRACK LENGTH, INCHES 2.50 Figure 2.
RPC Crack Length Versus Structurally Significant Crack Length, PVNGS Unit 2 Pulled Tube Data.
St; Lucie Unit' Pocket No. 50-335
'L-95-166 Enclosure 1
Attachment A
~ Page 3;3 1
APYSCH E
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M'aximum Crack Depth Versus Average Crack depth, PVNGS Unit 2 Pulled Tube Data.
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St. Lucie Unit 1 Docket.No. 50-335 Is-95-166 Enclosure 1
Attachment A Page A-4 0'PTSCH~
EN INEERING SERVICES LNC O~
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Distribution of sum of Yield and Ultimate Strengths of Alloy 600 tubing at Operating Temperature, ANO Unit 2.
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" Docket No. 50-335 L-95-166 Enclosure 1
'Attachment A
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Tube Flow Strength Distribution for Unit 2 Analysis.
St. >Lucie Unit 1 Docket No. 50-335
'I',L-95-166,Enclosure 1
Attachment A Page A-6 ENG NEERING SERVICE, INC 0 COPYRIGHT 0.12
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Palo Verde Unit 3 Tube Strength Distribution Function
t St. Lucie Unit 1 Docket No. 50-335 L-95-166, Enclosure 1
'~Attachment A
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IN ING SERVIC S, INC O~
100 90 0.5" CRACK LENGTH
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1.0" CRACK LENGTH RG 1.121 STRUCTURAL LIMITS 80 xQD0 x
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60 50 40.
30 oo CRACK LENGTH UPPER BOUND GROWTH RATE AVERAGE GROWTH RATE 20 10 CRITICALTHROUGH WALLCRACK LENGTHS
= 0.85" SLB
= 0.48" 36P 10 15 TIME, EFFECTIVE FULL POWER MONTHS 20 25 Figure 7.
Preliminary Deterministic Analysis for St. Lucie Unit 1, Axial Corrosion Degradation.
St. Lucie Unit 1 Docket No. 50-335 L-95-166 Enclosure 1 Page 15 Attachment B
Figures Referenced in the Response to Question 6
PSL-1 DISTRIBUTION OF INDICATION MAXIMUM-DEPTHS III e
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PSL-1 DISTRIBUTION OF INDICATION GROWTH RATES tt <q Ort C C
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8.6 8.4 8.2 I
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BOBBIN DATA GROWTH RATE - RTHRUWALLiEFPY Figure 2.
A COm KA
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'-95-166,Enclosure 1
,jI Attachment B
APTSCH ENG NEERING S VICES, INC, O~
Page B-3 Comparison of PSL1 Crack Lengths with Palo Verde Unit 2 Crack Lengths 8.8 gl Cl lg 0
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NRPC
St. Lucie Unit 1 Docket No. 50-335 L-95-166 Enclosure 2 Page 1
ENCLOSURE 2
FPL QUALIFICATION DATA SUPPORTING SIZING CAPABILITY OF INDICATIONS IN THE SLUDGE PILE AND THE EGGCRATE SUPPORTS
St. Lucie Unit 1
Docket No. 50-335 L-95-166 Enclosure 2 Page 2
2.
FPL letter dated March 13,
- 1996, Request for Peer Evaluation of Appendix H Bobbin Coil Qualification.
EPRI letter dated March 28, 1996, Results of Peer Review Group at EPRI NDE Center.
3.
4 Eddy Current Bobbin Coil Graphics for Tube Flaws used for the EPRI Qualification Package.
Eddy Current Metallography Correlations for Tubes Pulled at St.
Lucie Unit 1, Arkansas Nuclear One Unit 2, and Arizona Public Service.
wl
~ 4 "St. Lucie Unit 1 Docket; No. 50-335 L-95-166 Enclosure 2
Item 1
Ftorida Power Sr Light Company, P.O..
$4000, Juno Beach, FL 33400-0420 March 13, 1996 Paqe l-l Mr. Mohamad Behravesh Electric Power Research Institute 3412 HillviewAve.
P. O. Box 10412 Palo Alto, CA 94303
Subject:
Peer Review of Appendix H Bobbin Coil Qualification
Dear Mohamad:
Confirming our recent discussions, FPL requests an Industry Peer Review of our efforts to qualify a bobbin coil technique for detection
- 5. sizing of OD IGA/SCC indications.
The attached spread sheet provides summarized results for the data set used in this qualification effort. The Qualification Data Set contains pulled tube flaws from St. Lucie Unit 1, Arkansas Unit 2 and Palo Verde Unit 2. IGA/SCC samples were also provided by the EPRI NDE Center and are included in the Qualification Data Set.
I The Qualification Data Set, along with a Training and Testing Data Set, will be provided with supporting materials to Mr. Gary Henry prior to the Peer Review Meeting at the EPRI NDE Center on March 27, 1996.
Due to limited time availability and the volume of work scheduled for the Peer Review meeting, we suggest that priority be given to completing peer review of the Qualification Data Set to accommodate Spring outage inspection needs.
Review of the Training 8r Testing Data Sets for inclusion into the QDA Program could, if necessary, be deferred to a later peer review meeting.
We look forward to working with your staff on this matter.
If we can provide further information, please contact me at (407) 694-4909.
Sincerely, gd~) Z8~
Gary L. Boyers, FPL S/G Program Coordinator Attachments:
Spreadsheet and chart CC:
G. P. Alexander J. W. Connor K. R. Craig D. J. Denver A. J. Flowers R. F. Gross W. K. Heise A. Montalbano JPN-CSI-96-032 D. Harrison Entergy Operations G. Henry EPRI NDE Center R. S. Maurer ABB/CE C. Smith BG 5 E J. Smith RG 5 E K. Sweeney APS
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an FPL Group company
EPRI PWR STEAM GENERATOR EXAMINATIONGUIDELINES,APPENDIX "H" QUALIFICATIONDATASET - BOBBIN COIL DETECTION 8 SIZING OF ODSCC IN EGGCRATE SUPPORT PLATE 8 FREESPAN REGIONS (This data set emphasizes inflluence from an eggcrate structure at the flaw location)
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i,:DESCRIP 'i,::::.:&Etormott::":: (FACTOR!,""';I'Io'NTE/'Ec:',-:,
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'SQUARED EPRI - J23 004a.100 EPRI - J23 003a.100 EPRI - J15 003a.100 0.258 0.258 0.2 Lab - 340d Bob/w100'ab
- 340d Bob/w100'ab-170d Bob/w100'.86 None 0.86 EC 0.86 EC 0.52 2.13 16 16 63 24 0
68
-16 25 EPRI-J7 003a.100 0.377 Lab-tod Bob/w100'.86 EC 1.78 59 76 17 28 EPRI-J5 EPRI-J2 003a.100 003 a.100 EPRI - J13 003a.100 PSL1-120/12 050A.103 PSL1-120/12 050A.103 PSL1-59/95 050A.103 PS L1-59/95 050A.103 PSL1-79/91 050A.103 PSL1-79/91 050A.103 NO2-19/55 34C.104 NO2-19/55 34C.104 NO2-96/116 34C.104 PS2-127/140 SG22H.014 PS2-127/140 SG22H.014 0.326 0.89 0.376 0.6 0.4 0.7 0.4 0.5 0.8 0.7 0.5 0.5 0.58 1.05 Lab-40d Lab-43d Bobhv100'obhv100'evrescc Bobhv100'evrescc Bobhv100'GA Patch Bobhv100'GA Patch Bob/w100'GA Patch Bob/w100'GA Patch Bobhv100'GA/IGSCC Bobhv100'GA/IGSCC Bobhv100'GA/IGSCC Bob/w100'GA/IGSCC Bob/w100'GA/IGSCC Bob/w100'ab
- t Iod Bob/w100'.86 EC 0.86 EC 0.86 EC 0.73 3H-'EC 0.73 TSH+2.2" 0.73 01-EC 0.73 02-EC 0.73 TSH+1.2 0.73 TSH+3.9" 0.79 1H EC 0.79 2H EC 0.79 2H EC 0.84 7H EC 0.84 8H EC 10.75 20.74 0.63 1.79 0.64 1.09 0.7 0.91 0.33 0.59 0.73 1.59 1.05 96 100 35 72 30 52 13 16 42 52 49 59 100 89 85 93 29 70 26 46 96 28 44 67 60
-7
-6
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-16
-21
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-33
-29 121 10 25 193 441 22 108 841 Correlation Coifticient =
0.8330948
/os
< 35%
)=35o/o DETECTED 3of5 13 of 13 Free/POD O90% CL 0.6
<.80 1
0.8 Mean =
-5.55 StdDev=
17.54 Sum/Sq =
578 RMSE 17.9319 18 Data Points PSL1 QUAL.XLS Note:
1.
This qualification data set contains EPRI "J" Samples (Lab IGA/SCC) and pulled tube flaws from ST. Lucie 1, ANO 2 and Palo Verde 2 with emphasis on eggcrate interferrence.
Note:
2.
Eggcrate supports produce a much smaller signal than drilled supports and, therefore, interfere less with flaw signal detection &sizing. Other non<frilled support designs may have ECT signal characteristics which are similar to eggcrate designs.
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100 SN POD OINCONFIDENCE LEVELFOR FlAWS35%>
FLORIDA POWER LIGHT ST. LUCIE STEAM GENERATOR PROGRAM BOBBIN COIL APX. H - ODSCC CORRElATION COIFFICIENT ~.83 RMSE = 17.9%
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EPRI Electric Power Research Institute I ~
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~
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- t. Lucie Unit 1, ocket No. 50-335 lc L-95-166 Enclosure 2
t Item 2 t Page 2-1 v~~ i) ev-5 Pouring Progress through Innovative Solutions March 28, 1996 Mr. Gary L. Boyers FPL S/G Coordinator Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
Subject:
Peer Review ofAppendix H Bobbin Coil Qualification
Dear Gary:
Per your request ofMarch 13, 1996 your qualification package for bobbin coil depth sizing was presented to an industry Peer Review Group at the EPRI NDE Center on March 27, 1996.
In the opinion ofthe Peer Review Group the qualification data that you had submitted meets the requirement ofAppendix H. Please see the attached approval sheet for details ofapplicability and names ofthe Peer Review Group members.
Sincerely, gg
~@~5 Mohamad M. Behravesh
- Manager, Steam Generator NDE and Chair, ISI Guidelines Committee Attachdment CC: Ken Craig / FP&L David Goetcheus /TVA John Smith / RG&E Chuck Welty / EPRI Gary Henry /NDE Center David Black /Duke Power Scott Redner / NSP Richard Marlow/ Rockridge Gary Pierini / Westinghouse Bob Vollmer/ Zetec Headquarters:
3412 HillviewAvenue, Post Office Box 10412, Palo Alto, CA 94303, USA ~ (415) 855-2000 Washington Office: 2000 L Street, NW, Suite 805, Washington, DC 20036, USA ~ (202) 872-9222
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't. Lucie Unit 1 Socket No. 50-335 t
- I5-95-166 Enclosure 2
Item '3
'., ': ISITION TECHNICIUE SPECIFICATION SHEET
< Page 3-19 i".:.")BINIGAODSCC "QUALIFICATIONDATASE7')
ACTS¹ Bobbin iga odscc qual.3/96 PAGE:
1 of 1 BMMINATIONSCOPE Material:
Inconnel 600 Outer Diameter:
.750",.875" Wall Thickness:
.043",
.04o/'pplicability:
Detection of OD IGA/SCC at and non-dented eggcrate (or similar design) support plates and sludge pile regions.
Instrument:
Miz12, Miz18 Manufacturer.
Zetec Model: Miz,12, Miz 18a SofbNare/Mfg./Rev.:
Zetec System Dsk 200/300 Series, Eddynet, Various revs.
Probe Cable:
Yes Type: Shielded Length:
83'robe:
Bobbin Type:
A-xxx-SF, A-xxx-IWULC Manufacturer:
Zetec Size:
Fill Factol =73% to 86%
CABLES Extension Cable:
Yes Type: Shielded Length:
100'REQUENCIES Mode:
Differential Channels/Frequencies/Voltage/Gain:
Absolute Channels/Frequencies/Voltage/Gain:
1-400 3-100 5-600 7-10 400 560 200 990 100 100 10 10 2-400 4-100 6-600 8-10 400 560 200 990 100 100 10 10 CALIBRATIONMETHOD Standard: Various ASME SAMPLING RATE Samples/Sec.:
=>30 Samp.fin.
DATARECORDING Equipment Manufacturer:
Teac / HP Media: Tape Scan Pattern:
Axial Direction: N/ithdrawal Pitch:
n/a q
.Iga Model: 2300S / HCD-75z / 3968a Format: Analog / Digital Probe Speed:
Variable (see Samp/Sec)
Maximum: 24"/sec.
t
'F I
St. Lucie Unit 1 Docket No. 50-335 f-85-166 Enclosure 2
I.Item' j
~
Page 3-20
"."'.'IiLYSIS TECHNIQUE SPECIFICATION SHEET
'"-".. iBBIN IGAODSCC "QUALIFICATIONDATASET")
ANTSY Bobbin iga odscc qual.3/96 Page:
1 of 1 Instrument:
HP Manufacturer.
HP Model: 700 Series Software/Mfg./Rev:
Zetec/Eddynet/Version 27 Reference ACTSC Bobbin iga odscc qual.3/96 Span:
Phase:
Cal Std:
Curve:
Volts:
DIFFERENTIALCHANNELS Channel 1
Channel 3
Channel 5
1QQ% @ 5Q% fsh 1QQ% O 5Q% fsh 1QQ% O 5Q% fsh Probe Motion Horiz Flaws down first Probe Motion Horiz Raws down first Probe Motion Horiz Flaws down first ASME Normalize 5 Volts on 420% FBHs Normalize 5 Volts on 4-20% FBHs Normalize 5 Volts on 4-20% FBHs ABSOLUTE CHANNELS Phase 20,60,100%
Phase20,60,100/o Phase20,60,100%
Channel 7
100% O 50% fsh Probe Motion Horiz Flaws down first Phase 20,60 100%
Normalize 5 Volts on 4-20% FBHs Span:
Phase:
Cal Std:
Curve:
Volts:
Channel 2
ASME flaws visible 8 below screen sat Probe Motion Horiz Flaws up first ASME Normalize 5 Volts on 4-20% FBHs Channel 4
ASME flaws visible 8 below screen sat Probe Motion Horiz Flaws up first ASME Normalize 5 Volts on 4-20% FBHs Channel 6
ASME flaws visible 8 below screen sat.
Probe Motion Horiz Flaws up first Normalize 5 Volts on 4-20% FBHs Channel 8
ASME flaws visible 8 below screen sat.
Probe Motion Horiz Flaws up first ASME Normalize 5 Volts on 4-20o/o FBHs Screen Setup (Minimum): Lt. Strip - Prime/Qtr Dff. Mix, Rt Strip - 100 Abs. (span of about 10).
Analysis Protocol:
Mixon ASME Std. support ring. This technique is applied for detection 8 sizing of indications associated with OD IGNSCC at non4ented eggcrate (or similar design) tube supports or sludge pile regions. A size threshold does not apply.
Refer to the endosed analysis rules and logic diagrams for analysis of indications.
Free span indications above the 1st support plate, 8 indications which are distorted due to deposits, support plate edge effects or other interferring conditions should be considered for further evaluation and disposition or repair.
ST LUCIE UNIT 1 EDDY CURRENT - METALLOGRAPHY CORRELATION LQS I
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LINE/RO'F/SEC LOCATION SLUDGE PILE (120/12-2)
(BOBBIN)
PPL FIELD 414 404 304 BfcN ACTUAL LAB Sx1 DEPTH DEFECT APPEARANCE IG/TG SCC PM&LLELAXIALCRACKS.
0 4I'ONGEST OVER 1n AXIALLENGTH ACROSS 360 OF TUBE CIRC.
MOST OVER 90.
SLUDGE PILE (79/91-2) 1.4n ATS UDS/694
<204 504 164 IGA PATCH "AXIAL"CIRC. 1/2n x 1/2n 4.4n ATS 57%
50%'0%
424 IGA PATCH nAXIALn CIRC 8n x 1/2n N1 EGG RATE (s~/V<
N2 EGG CRATE (59/95-5) g3 EGG CRATE (120/12-7) 294 254 824 80%
DSS/724 NOT SEEN 50%
52%
304 904 72%
IGA PATCH (0.7 AXIALx 0.3 CIRC.)
IGA PATCH (0.4 AXIALx 0 ~ 3 CIRC.)
IGA/TG SC0 PARALLELAXIALCRACKS IN LAND AREA 0 6n LONGEST OVER 2
INCHES AXIAL ACROSS 0.1n OF TUBE CIRC NO DATA TAKEN POST MET LAB EVALUATION UDS-UNDEFINED SIGNAL DSS-DISTORTED SUPPORT SIGNAL
St, Lucie Umt 1 Docket No.'60-335
%-95-166,Enclosure 2
Item 4'age 4
2 ARKANSAS~MUCL'EAR ENGINEERINS STANDARD ANO-2 STEAM GENERATOR REGP DATA ANALYSISGUIDELINES No.: HEsQs Rev. No.: 2 Page 84 APPENDIX I PULLED TUBE SAMPLE NDE
~ow Line Location ANO-2 SG TUB ULLSAMPLE DE Pre-Po(( UT A
13 147 TSH+ 0.1r DTl SCl 80 Volts Mu(t(p(e Circ 89% Thru-Wali 100% Max 360 Degrees 61% Avg 347 Degrees 360 Degree 100% Max 94% Avg A
55 63 TSH ~ 0.16 DTI SCI 40 Valts 88% Thru-Wall 360 Degrees Mu(tiple Circ 100% Max 49% Avg 289 Degrees 360 Degree 100% Max 88% Avg 8
19 55 TSH + 0.41" DTI TSH ~ 1.55" 31% Thru-Wall 0.56 Vo(ts NDD NOD 5.20% Max Depth NOO Circ Grac(ts NDD NOO 01H ~ 0.68" 0ZH+ 0.70-8 96 116 02K ~ 0.42" OS(
0,26 Volts 26% Thru-Wa(l 0.68 Vo(ts 41 (, Thru-Wa((
o.99 Va(ts SAl O 0.77 Volts 46% Thru-Wali 0.72" Long SA( @ 0.$4 Va(ts 26% Thrv-Wall 0.57 Long SAt 2.05 Va(ts
~
39% Thru-Wa((
0.51 Long NDO Max 52%
Avg 36%
Max 49%
Avg not avat(ab(e Max 59%
Avg 41%
8 38 130 TSH ~ 0.06" OT(
SCi@7Valre wrang raaefran 360 Oegree
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80% Thrv-Wall tested 100% Max 360 Degrees 88% Avg
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- Docket No. 50-335 X,-95-166 ~E'nclosuze 2
Item 4 Page 4-4 surfaces and there appears to be numerous unopened surface cracks.
The axial preference of the opened cracks is due to the tube being squeezed.
Further away from the apex of the bend created by the tube being squeezed, the cracking has not opened up as much.
There also is less surface cracking because the area away from the apex is also away from the r idge deposit.
Figure 10-17 shows the descaled tube surface of Tube R117L144 at the very bottom of the ridge deposit.
In the figure the axial direction is horizontal.
As mentioned above, while particulates and polishing marks are evident, no scratches were found.
Short axially oriented cracks can be seen on the
- surface, but they have not opened up significantly and there is no grain dropout.
Tube 1
0 Section 13 Significant corrosion also occurred at several points where tubes contacted eggcrate support straps.
Three such areas were burst tested and subsequently examined by SEH.
The worst corrosion of an eggcrate contact point occurred at the 07H support intersection with Tube R127L140 (Section l3).
This tube section leaked from a crack at a low pressure and required a bladder to complete the laboratory burst test, however vacuum grease was not used.
Figure 10-18 shows a portion of the burst face of Tube R127L140 Section 13.
The figure shows the cracking extending to the outer surface of the tube.
Cracking is intergranular and was branched.
No transgranular cracking was evident.
In this particular location there was no evidence of elongated grains near the outer surface.
Figure 10-19 presents two areas near the inner wall of the tube section in the vicinity of where the tube leaked during the burst test.
Some erosion of the grains near the ID has occurred.
Cracking was lOCX throughwall at this location.
10-8
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- 't. Lucie Unit 1 Docket Nb. 50-335
'I L-95-166 Enclosure 2
! Item 4
Pa e
~ 4-3 Date g
7 C
Number ofpages including cover sheet To gdXp Brpcms FROM:
Arizona Public Service Phone Pax Phone rttey)et'hone Fax Phone 5801 S Wintersburg Road Mail Station 7696 Tonopah, AZS5354-7529 (602) 393-5049 602 393-5366 CC: Rich Schaller
! REMARKS:
Q Urgent Q
For your review Q
Reply ASAP Q
Please Comment
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Steam Generator 22 Tube R127 L140 Section 13 Burst Face Crack Depth Diagram
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.~ St. Lucie Unit 1 Docket'Ao.
50-335 L-95-166 Enclosure Item 4 Page 4-5 Because of relative movement between the tube and the support, a significant amount of surface wear occurred on the OD of the tube.
Evidence of this is seen in Figure 10-20.
Severe elongation of grains is shown in the figure, especia11y near the OD surface, that is 4-5 grains deep (roughly 4 mils).
Beyond this depth the grains are similar in appearance to those shown in Figure 10-18.
Also shown in Figure 10-20 is a ligament.
Ligaments were
. present over the whole burst surface.
Figure 10-21 shows the outer surface of Tube R127L140 where it contacted a 07H support strap.
The figure shows a tube wear mark next to the burst fractur e.
The burst fracture is intergranular in this area where the grains at the surface have been smeared and elongated by mechanical means.
There is evidence of other surface cracks in the wear area.
Tube R127L140 Section 15 The portion of Tube R127L140 that contacted the 08H suppor t (Section
- 15) also experienced intergranular corrosion.
This section was burst tested, sectioned and then examined by SEH.
The corrosion in this section was similar, but not as deep as that of the 07H support.
The maximum penetration (XTM) was 89.3 and the avera e
enetration (XTW) was 58,0.
Also smeared grains were not seen on this sample.
Cracking was simi ar o the cases presented earlier; cracking was OD initiated, intergranular, with no signs of transgranular
- cracking, branching can be seen from the main crack and there were numerous ligaments on the burst crack.
Tube R117L144 Section 13 The 07H eggcrate support contact region of Tube R117L144 (Section
- 13) also experienced OD initiated intergranular corrosion.
This section was pressurized to 7938 psi when it developed a leak. lt was descaled in an EDTA solution and dye penetrant tested.
Unlike the other areas of corrosion mentioned this area consisted of 4-5 short axially oriented cracks.
The area 10-9
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100%
Tubs outside Surface Tube inside Surface Figure 10-30 Steam Generator 22 Tube R12? L140 Section 15 Surst Face Crack Depth Olagrarn 1.0' I
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