ML12053A147
| ML12053A147 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/15/2012 |
| From: | Mogren T Constellation Energy Nuclear Group, EDF Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12053A147 (20) | |
Text
Thomas Mogren R.E. Ginna Nuclear Power Plant, LLC Manager - Engineering Services 1503 Lake Road Ontario, New York 14519-9364 585.771.5208 585.771.3392 Fax Thomas.Mogren@cengllc.com CENG a joint venture of o mww
~~t~l eDF February 15, 2012 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
R.E. Ginna Nuclear Power Plant Docket No. 50-244 Response to Reauest for Additional Information RE: The 2011 Steam Generator Tube Inspections - R.E. Ginna Nuclear Power Plant
REFERENCES:
(a) Letter from Mr. T. G. Mogren (Ginna LLC) to Document Control Desk (NRC) dated November 15, 2011,
Subject:
2011 Steam Generator Tube Inspection Report (ML11325A118)
(b) Letter from Mr. D. V. Pickett (NRC) to Mr. J. E. Pacher (Ginna LLC) dated January 23, 2012,
Subject:
Request for Additional Information RE: The 2011 Steam Generator Tube Inspections - R.E. Ginna Nuclear Power Plant (TAC No. ME7597)
By Reference (a), R.E. Ginna Nuclear Plant, LLC (Ginna LLC) submitted the report of the 2011 Steam Generator Tube Inspections performed during the End of Cycle 35 Refueling Outage in May 2011. On January 23, 2012 the NRC responded to that submittal with a request for additional information Reference (b).
Attached please find the response to the staff's questions.
Should you have any questions regarding this matter, please contact Mr. Thomas Harding at (585) 771-5219 or Thomas. Hard inpgJr gcengllc.com.
Very truly yours, Thomas Mogreb : Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspection Report : Ginna Steam Generator A and B Bobbin Coil Dents Detected During the 2011 Refueling Outage (RFO) : Ginna Steam Generator A Tubesheet Map cc: W. M. Dean, NRC D. V. Pickett, NRC Resident Inspector, NRC
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Inspection Report R.E. Ginna Nuclear Power Plant, LLC February 15, 2012
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Question 1:
During the 2011 inspection, 237 dents were observed in the tubes at the top of the tubesheet on the cold-leg side of the steam generator. During the 2008 inspection, 80 tubes were identified with dents at the top of the tubesheet on the cold-leg side of the steam generator. It was then indicated that there were 156 newly reporteddents in the tubes at the top of the tubesheet on the cold-leg side of the steam generator.Please confirm these numbers (e.g., were there 81 dents in the 80 tubes with dents during the 2008 inspection?).
Response
To clarify the 2008 and 2011 cold leg (CL) and hot leg (HL) top of tubesheet (TTS) dents and the number of tubes affected with dents in the Ginna A and B Steam Generators (SGs),
Table 1 is provided below. No more than one dent was identified in any one tube.
Table I Number of Number of Number of Number of Number of Reported 2008 Reported 2008 Reported 2011 Reported 2011 Reported 2011 TTS CL dents TTS CL dents TTS CL dents TTS CL dents TTS HL dents
(# of tubes) in (# of tubes) in (# of tubes) in (# of tubes) in (# of tubes) in SG-A SG-B SG-A SG-B SG-B 2 (2) 80(80) 4(4) 236 (236) 1 Question 2:
Regarding the denting at the top of the tubesheet, what is the voltage associatedwith these dents, what corrective action, (if any), was taken to address the denting, and what insights, (if any), were obtained from profiling the dents?
Response
The bobbin coil voltages range from a minimum of 2.07 Volts to a maximum of 40.46 Volts.
See Attachment 2 for a full listing of top of tubesheet dents detected during the 2011 refueling outage (RFO) with the bobbin coil. There is a separate listing for SG-A cold leg bobbin coil detected dents, SG-B cold leg bobbin coil detected dents, and the one SG-B hot leg bobbin coil detected dent.
The steam generator denting was entered into the Ginna corrective action program in 2008 when top of tubesheet denting was first detected and again in 2011.. The corrective actions that have been taken to date include more frequent sludge lancing to remove sludge material from the tubesheet secondary face. Ginna and vendor personnel worked to improve the sludge lance process at Ginna. The Sludge lance system was redesigned for the Ginna 2011 RFO, and sludge lance process enhancements were made to improve sludge removal.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 1 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections While Ginna has generally met industry corrosion product transport requirements, Ginna has further reduced corrosion product transport to the steam generators to minimize deposit accumulation. Ginna implemented a relaxation of main steam cation conductivity limit from 0.3 ps/cm to 0.5 ps/cm. This allows higher feedwater ethanolamine concentration which minimizes corrosion product creation in the heater drain system. The heater drain system accounts for approximately 1/3 of the contribution to the feedwater iron transport.
Ginna has implemented a fleet Chemical Control Program to further reduce the impurity ingress into plant systems. From an equipment perspective, the program operates from a prevention standpoint. Implementation also includes a chemical foreign material reduction briefing to all plant personnel as well as chemistry review of potentially impactful Ginna plant work orders.
Ginna SG sludge sampling has been performed periodically since SG replacement. The Ginna SG sludge was again analyzed in 2011 with additional insight from the 2008 RFO.
Sludge binding agents and impurity identification was improved which is an important input for future potential corrective actions that are being evaluated.
During the 2011 RFO, dents were examined for cracking and were profiled by eddy current testing using a "D" probe. The first important insight with the "D" probe was associated with the +Point coil which is qualified for the detection of axial and circumferential outside diameter stress corrosion cracking, as well as the detection of axial and circumferential inside diameter primary water stress corrosion cracking. The entire top of tubesheet dent population was tested with the "D" probe (+Point coil) and there was no detected degradation.
The "D" probe also has a 0.080" high frequency nonsurface riding pancake coil that is designed for profilometry type of applications which also provided important insights. The 0.080" coil provided improved dent axial elevation resolution over the bobbin coil. While the bobbin coil is very good for dent detection, its ability to resolve the dent axial elevation was not as accurate as the 0.080" coil. With this improved resolution, the dents were shown to be slightly below the tubesheet secondary face in the small crevice where the tube is not expanded into the tubesheet. The average dent axial location was centered 0.07" below the tubesheet. The crevice depth is 0.0" - 0.165".
The additional 0.080" coil also provided insight on the circumferential extent of the denting, which ranged from less than 45 degrees to 360 degrees, with a mean circumferential extent of 160 degrees. This circumferential extent corresponded well with the bobbin coil voltage.
The larger bobbin coil dent voltages had the larger circumferential extents.
Further data analyses work is in progress that will provide dent radial dimensioning. Recent vendor software upgrades have given us the ability to perform dent radial dimensioning utilizing the data taken during the 2011 RFO. The dent radial information will support further evaluation.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 2 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Question 3:
In Table 3.1.1, please clarify what constitutes the "centralbox area."
Response
The tubesheet map, Attachment 3, shows the examination area. The central box area is a large portion of the examination area, and was selected to bound the denting extent of condition.
Question 4:
It was indicatedthat the divider plate in both SGs was inspected. Pleaseclarify the materialsof construction of the dividerplate, the stub runner,(if any), and the associatedwelds. Please discuss the results of these inspections.
Response
The Ginna divider plate material is fabricated from SB-1 68 N06690 (Alloy 690) material and the weld material used to weld the divider plate to the seat bar is Incoloy 152, which is an Alloy 690 compatible weld material. The seat bar, which is manufactured by weld buildup, is made of Incoloy 82 (1-82) material. It should be mentioned that the 1-82 weld overlay on the tubesheet, on which the weld buildup is deposited, has been subjected to postweld heat treatment process to a minimum temperature of 11 00°F. After the closing seam between the primary head and the tubesheet was completed, the weld was postweld heat treated.
During this process the weld between the divider plate and the tubesheet was heated to the postweld heat treating temperature as well. The design of the Ginna divider plate uses a weld buildup bar and not a rolled bar for the stub runner. The 1-82 weld buildup has slightly higher chromium content than Alloy 600 and has better resistance to stress corrosion cracking (SCC). In addition, the weld between the divider plate and the seat bar was postweld heat treated, which reduced the weld hardness. This has proven to be beneficial against SCC.
Ginna has performed visual inspections of the divider plate weld areas during the last two steam generator outages, 2008 and 2011, with no detectable degradation. The visual acuity was a VT-1 examination. While performing this examination, fine machining marks were detectable along surfaces indicating good examination detectability and resolution. The Ginna divider plate and associated welds were found to have maintained an as-manufactured appearance and no service induced defects were detected.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 3 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Question 5:
Pleasediscuss the nature of the restrictionof the tube in SG A. For example, is the restriction service-induced,is it located in a low row tube, or has this tube been previously inspected successfully with a 0. 610-inch bobbin probe?
Response
The restricted tube is row 9, column 121, and has been determined to have been caused by a manufacturing dent. This tube was thermally stress relieved during manufacture and has been discussed in previous Ginna steam generator reports. The tube dent is not service induced. As a clarification for the 2011 refueling outage (RFO) examination, row 9, column 121, was examined full length with a combination of bobbin probe from each tube end and
+Point coil through the dent area. No degradation was detected.
Row 9, column 121, has been examined full length during refueling outages in 1997, 1999, 2002, and 2005 with a 0.610" bobbin coil. There has been no increase in dent voltage from these repeated examinations, so the dent is not experiencing any in-service growth. Row 9, column 121, was also examined through the dent location during refueling outages in 1997, 1999, 2002, and 2005 with a +Point coil. No indications of degradation were detected.
During previous examinations, the probe was positioned at the dent location with the probe pusher and the manipulator elevator, which was then used to assist the probe through the dent location. The present manipulator is a lower torque version that does not have an elevator assist function. We now inspect the tube full-length from both ends.
Question 6:
Besides the flow acceleratedcorrosionin three of the secondary steam separators,was there any other degradation/anomalousconditions identified during the secondary side internals and upperbundle inspections?
Response
There were other secondary separators that exhibited areas of removed oxide from steam flow, but no degradation. The comprehensive secondary side examinations exhibited no additional degradation or anomalous conditions.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 4 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Question 7:
Fourindicationsof wear were identified and attributedto loose parts. Pleasediscuss whether the parts that caused these wear indications were removed from the SGs. In addition, please discuss how these indicationshave changed with time. Please discuss the number of known loose parts or possible loose parts in the SGs and the source of these loose parts.
Response
The loose parts that caused the wear are no longer at the wear locations in all four cases.
These indications were verified with no loose parts present during the 2008 refueling outage (RFO), and again confirmed during the 2011 RFO. Since indication #2 was first detected during the 2011 RFO, the no loose part verification was performed during the 2011 RFO.
These parts were not removed from the SGs, but it was verified that the part is no longer there. Based upon the tolerance of the tube-to-tube support grid, it is most likely that the parts have diminished in size and moved on. It would be normal Ginna practice to remove the tube from service due to tube wear and if the loose part associated with the tube wear is still present.
The following insights are provided when comparing the 2008 RFO detected loose part wear location to the 2011 RFO detected loose part wear indications. The intent is to apply the most appropriate loose part sizing examination technique specification sheet (ETSS) for each wear shape. See Table 2 for a summary.
Indication #1 was sized with ETSS 21998.1 and has not changed in maximum depth.
Because 2008 length and width dimensioning used an overly conservative estimate using indication baseline as a threshold vs. using a flaw peak, a reduced and more appropriate length and width dimensioning was performed during the 2011 RFO.
Indication #2 was sized with ETSS 27901.2 and was initially detected during the 2011 RFO.
A flaw peak length and width dimensioning was performed during the 2011 RFO.
Indication #3 was sized with ETSS 21998.1 and has changed slightly in maximum depth from 2008, but within eddy current tolerance. Because 2008 length and width dimensioning used an overly conservative estimate using indication baseline as a threshold vs. using a flaw peak, a reduced and more appropriate length and width dimensioning was performed during the 2011 RFO.
Indication #4 was sized with ETSS 21998.1 and has changed slightly in maximum depth from 2008, but within eddy current tolerance. Because 2008 length and width dimensioning used an overly conservative estimate using indication baseline as a threshold vs. using a flaw peak, a reduced and more appropriate length and width dimensioning was performed during the 2011 RFO.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 5 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Table 2 Indication SG Row Column Location Degradation ETSS NDE Measurement Type Parameter(s)*
1 A 91 51 05H +0.34" Volumetric 21998.1 29% through wall
+ Point (TW), 0.10" length x 0.16" (250) width using flaw peaks 2 A 53 85 02H+36.93" Volumetric 27901.2 19% TW, 0.12" length (0.5" below + Point x 0.16" (250) width 03H) using flaw peaks 3 B 78 24 01H +0.91" Volumetric 21998.1 25% TW, 0.14" length
+ Point x 0.19" (290) width using flaw peaks 4 B 78 24 01H +1.20" Volumetric 21998.1 22% TW, 1.11" length
+ Point x 0.19" (290) width using flaw peaks Table 3 shows the confirmed loose parts that were left in-service during the 2011 RFO.
Each specific loose part was evaluated for potential wear rate to justify leaving the tube in-service. Most of the loose parts involve Flexitallic gaskets. Ginna has replaced all in-stock Flexitallic gasket material with an improved Flexitallic gasket, which is less susceptible to in-service uncoiling.
Table 3 Number of parts left in- Description of loose part service source SG-A Cold Leg 1 1 - Flexitallic gasket piece SG-A Hot Leg 24 17 - Flexitallic gasket pieces 4 - sludge rocks 3 - metallic pieces SG-B Cold Leg 4 1 - Flexitallic gasket piece 2 - metallic pieces 1 - wire brush bristle SG-B Hot Leg 15 12 - Flexitallic gasket pieces 2 - wire brush bristles 1 - metallic piece R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 6 of 7
ATTACHMENT 1 Response to Request for Additional Information Regarding the 2011 Steam Generator Tube Inspections Question 8:
Pleasediscuss whether there has been any change in the number of tubes in close proximity or the extent to which the affected tubes are in close proximity (e.g., decreasedspacing or length of tubing in close proximity increasing).
Response
Ginna became aware of the potential for tube-to-tube proximity issue prior to the first SG inservice inspection (ISI) performed during the 1997 refueling outage (RFO) as a result of an original manufacturer's information notice. Ginna has examined the susceptible proximity areas during each RFO. A new set of proximity tubes were detected in SG-A and SG-B during the 1999 RFO due to improved eddy current analyses and sensitivity. When reviewing the data, these new sets of proximity tubes were detectable in the previous 1997 RFO examination. Since the 1999 RFO, no additional tube-to-tube proximity tubes have been detected. The total history is in Table 4.
Table 4 Steam Generator A Steam Generator B detected proximity tubes detected proximity tubes 1997 RFO SG ISI 11 10 1999 RFO SG ISI 13 12 2002 RFO SG ISI 13 12 2005 RFO SG ISI 13 12 2008 RFO SG ISl 13 12 2011 RFO SG ISI 13 12 When reviewing the tube data with tube-to-tube proximity, there have been no changes in the affected tube proximity locations or extent since the original detection of these indications. Based upon the specific Ginna manufacturing process that provided the tube-to-tube proximity issues, this is the expected result. There has been no evidence of tube-to-tube wear detected in these tubes. The detected proximity within a given set of tubes is over several inches and to date the Ginna proximity tubes have been consistent.
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012 Page 7 of 7
ATTACHMENT 2 Ginna Steam Generator A and B Bobbin Coil Dents Detected During the 2011 Refueling Outage (RFO)
R.E. Ginna Nuclear Power Plant, LLC February 15, 2012
Attachment, 2 Ginna Steam.Generator A.Coidleg Bobbin, CoilDents (2011 RFO)
'I6W cOL. VOLTS' 6DEG. fIkND PE,'ER CHN L.OCN INCHI. IN*H2 BEGT ENDT` PDIA PTYPE. C-A L OUTIL-,
49 43A ý5A42 179 'DNT Pi, TSC 0.15 TEC TEH' 0.61 ZBA2B 17 H 51 43 13.28 178 DNTT Pp1, -TSC 012, TEC TEH 0.061: ZBAZB 17 H 50 '44: 4.46 179 DNT P1 TSC 0:28 TEC 'TEH :0.61 ZBAZB 17 H Pi i52 TSk 0.28 TEC TEH. 0.61 ZBBAZB 17 I7. .H 44 3.93 79 DT Pagel of 8
Aftachment. 2 Ginna Steam Genetator BWcoldideg SBobIbin Coil Dentsý (2011 RFO)
ROW CbOL VOLTS'. DEG IND PER CHN iNCHi INcH2 BEGT EIDT ELoN PDIA; PTYPE, CA L UTILI 34 36 10. 89. 182 DNlqT* .P1 TSC 0'.44 TEC TEH 0,616 NBAZ.B 17 H',
362 5.68 177 DNT 0.39 TEC TEH 02.61 :NBAZB!: 17 HR 3,7 '40.46 TSC 0.1, 35 '181 DNT- 0.,1 TEC TEH 0.61 NBAZB 18 2; H
.TSC
- 37. ý37 1-8.17" 181 DNT' TEC -TEH 0.61. NBAZB 18 H J8 7i.8 180~ DJNT TEC TEH 061 NBAZB. 1 H' 3*6 38 8.72 177 DNT iPl,. TIst .0.34 TEC TEH 0.6i NBAZB :1 H' TSC 3.2 '50 3.2 178 DNTý :P1 TSC 0:2 ,o.ic 'TEC. 0.61. ZBAZB 2' C, 34 56 6-74 180 DNT 0.21 TEC TEH 0.61: NBAZB 1213H
'56, 7.443 P1 .0.26 36 180 DNT TSC, fTEC tEH J0.61, NBAZB 12 H 33 182 DNT TEC TEH 0.61 NBAZB 13 H.
3.5 5s' 129.87 180 DNT TEC TEH 0.61 NBAZB 13 H
'TSC 0.124 37 :57' 12.'ý7L 180 DNT. TEC TEH 0.61, NBAZB 1:i3 HR
'TSC 0.15 53 57 4.'5 180 DNT P, TEC TEH 0":61 N'BAZB 8, H, 55 57-84 178 DNT 0ý TEC TEH 0Q.61 NBAZB H
- P1 .TSC 57 4.b06 181 DN.T -TEC "TEH 0.61 NBAZB H
'8 34 58: ?11.28 179 DNT
.pt P1: I'Sc 0.31 TEC 'TEHý '0.61 NBAZB 3IlH JTSC 36 58 '19,.05 180 DNT '0.28 TEC 'TEH 0.61 NBAZB 143 H
'TSC 52 58 6.32, 181 DN!T Týsc
'*TSC TE TEH 09.61 NBAZB 8a, H 54 TEEHC 0.61 1 NBAZBI 8HI TSC 58' 1037 179 DNT TEC TE. 0b.61, NBAZB 8I:H*
182, ýDNT' '0.26, *EC ýTEH 0.61: NBAZB 8: H
-TSC 35 59 .335: 183 DNTý p.1 TSC 0.26 TEC JTEH 0.61 NBAZB 182ýH 39 59 12.79 179 DNT 024; 5.59 :9.55`1 ,179'DNT Rii 0.34 0'ic TeC 0.61 ZBAZB I C
,59, 13.03Q 178 DNT -0iC TEC 0.61 ZBAZB 1 -C tSC
'55. '59- 7.;58' 179 DNT P1. TSC 0.',24 ,01C TEC: 0,61 ZBAZB ' C, "TSC 57: ,59, 2.75. ,175 DNT TSC 0.34 ,1C TEC 0.61 ZBAZB 1 C
- .60
- 5.74z 179. 'DNT; P1 ,0C. TE~C.: 0.61. ZBA~zBi 1: c
- 38. 178 -DINT 0.29 TEC TE , NBAZB
-061 12 H
,40Z!
.*l, Pi :T'ic TEC '0.61 NBA.B 1 C
- 60 3.
- 62* 173' DNT 'c, TEC' 0.61, ZBAZB 1.
-TSC 0.'24 39 61 '379* 179 DNT 01C TEC 0.61 ZBAZB 1: C 748, 62- -23'8 184., DNT Pl: TEC ,TEH 0.61 NBAZB 8 H 5S3: Tsc 179 DNT TSC *TC TEC 0.61: NBAZB 1 ýC P1 imc 55, 177' DNT oi ,C Tc' 0.61, ZBAZB; 1 C 0.27
ý0.22
'50 64: 5.73' 177 DNT P1- TSC,, QIC TEC 0.61 ZBAZB 1ICI 0:27
'52' '64. 3.06' 179 DNT 01C' TEC" 0.61 ZBAZB, 1 C
- 39 '0ic,
'6 2.09, 177 DNT .0.27 TEC 0.61 ZBAZB 1 C 184 D:NT. T-kc TSC' TEc FEH 0.61 NBAZB 8 H 49' 184.DN TSC.
TEC TEHR :o.6i NBAZB I8 H 51, 65c ;7.73 178 DNT A019 :TEc' TEH -0.61 NBAZB 8 Hl
',34.
TSC 66 7.52 179 DNT Pi "ISC' TSC 0.16 TEC' TE H 06.61 NBAZ'B 13 H
,66, 5.62 -179 DNT, PI 0 TEC TEH 0.611 NBAIZB -8. H 52 66 3.09 '182 DNT Tsc, TSC .0j2'6 TEc" TME ,0.61. NBgAZB -8'H
- 54 66' 384 182 INT
.:0.1:6. TEC -TEH *0.61, NBAZB 8 -H
!33 67. 2.45: 183 DNT 0.12 'TEC' TEH -0.61, NBAZB 10, :H
,35, 67 -9.79 180 DNT 0.22 'TEc' TER, 0.61, NBAZB 10 ýH Page 2 of 8
AttaChment 2 Giinn St~eam, Geneira~tor B-ColdLeg BobbinCoiDents! (2011 RFO)
ROW COL -VOLTS. DEG IND PER tCHN LOCN INCH1. INCH2 BEGT ENDT PDIA PTYPE CA-L. L. IUTILi
- 67 5159 178 'DNT P1! TSCS '0i TE(
f 0:.61 ZBAZB '1 C 67 12.65 i78 DNT P1 TSC 01C TE.C '.6i ZBAZB' ! C,'
0.05-55 67 1736 1,79 DNT P1 :TSC 0,05. O0C, TEC 0.61: ZBAZB 1 C
- P1I TSC oiC TEC 0.61 ZBAB. 1-57 ,67 2128 183 DNT 0.29
- - C0 68 12.85, 0:22 38 i76 DNNT TEC TEH 0.61 NBAZB, H 56 178 DNTW P1; oiC TEC 0.6i, ZBAZB 1 C s§ ;68 5 177 'DNT-IP1*
58 68 :2.72, 1892 DNT
-TSC 0.12
,01C 'TEC ,061. ZBAZB 1 c
'TSc 60 68- 23T77' 181 DNT P1 P1 .ýTsc i0:227 53 ,69 *13.62179 DNT- .. ". I:! TEc TEH 0.61 NBAZB 16 C 557 181. DbNT 'TSC TEC TEH TEC -TEH; 0.61 0.61, NBAZB NBAZB ;6 6 H' H
180 DNT P1. "TSC 59 ,69' 7'53: 180 DN T P1 "p1 T-SC 0".05 TEC 0.61 NBAZB 6, TEH i0.61
- TEc* "TEH- 6 H H"
61 ,69 3.33 182 .DNT7 'Sc P1 ý'TS TEC TEH !0.61 NBAZB ,6 H
'54* 70b i2.07* 1-74 "DNT TEC TEt H 0.61 NýBAZB 6 H 180 DNT, 'o8CI TECc0-6.61 ZB9AZ1.6 3
.37: i78 "DNT "TEC TEH 0.61 NBAZB 10Q H TSC 39 71, 5.12' 1,75. *DNT *0.22, TEC 'TEH *0.61. NBAZB 5 H
.7'1, ,3.82: *TSC 0O.12
,43 1i761 DNT; P1 TEC TEH 0.61 NBAZB 5 H 51, 1,74, DNT' ,TEI TEH
,C .0.61 NBAZB. 5 H 2* '71. 2.58 2's i78, DNT 38 Ct P1 0.:17 08 TEC'E "0;61 ZBAZB TSC
-36' '72, 11'.76 180- DNT TEC TEH 0.61- NBAZB 10 H 38- '72' ,11.-28 1-79: ,DNT Pi. -TEC TEH .0.61 NBAZB 5, H
'42 0.21 T's TEC TEH,0.61 NBAzB 5 H 176 ,DNT 1783: DNT 04:* TsC TSC, 0.56 TEC. TEH 0d.61 6NBAZB. H
- 46' 72; 2.!8 TSC:
,173 DNT Pi 0:12 48; 722.53- 173, DNT P1 ~TSC, TSC 0.19 TEC TEH 0.61 NBAZB 5 H
- 50' P.
72' 7.23' 177 DNT ý0.14 TEC: TEH ,0.61 NBAZB S H P01 T-SC
,52 72'31 177,3 DNT TECit TEH, 0.61 NBAZB -65 H TSC :0.24-41 73 3.59 TsC* TECI TECi TEH 0.6 TEH 0.*61 NBAZB 65 NBAZB. HH 43, 73 7.81 '180 P1 'TSC 0.*24* TEC' TEH 0 '.61 BAZB 6 H 177-. DNT TSC 0.31 0.2-1 45' '73 4,68 173 DNT P1 TSC'TSSC, 0.37 TEC, TEH. 0.61 NBAZB 6" H 0.31.
A47 73, 5.5 :179 DNT TEC TEH. 0.61 NBAZB ,6 H 49:' 0.19 179 DNT Pi' 040S TEC, TEH 0.61 NBAZB .6 TEC, TFl- '0.61 :NBAZB, ý6
- .H H
73 5.14$
179DNT Pi -0.26,ý
- 32. 74 '2.14. 178ý DNT. .0:27 P1 TSC.
.0;29,
.42- 74, 695 1,77 DNT P1' TEC: TEH 0.61 NBAZB -6, H P1 TSC* 0.17 TEC TEH 0.61 NBAZB 6 .HC 74 ,5.48 17.7 DNT msc TSC:
46 P1 TEC TEH 0.61 NBAZB 6- .H
,4 74 9.14 179, D.NT P'1 TSC& 0.26i TEC. itEH 06 NB"A-ZB 6& Hi 74 211.414 ,17.8 ,DNT TSC'*
50 Pi 74 26.48 *179 DNT P1 Ts"c 0.033- TEC' TEH 0.61' NBAZB' 6: H DH
,52 74 2.61 '179 DNT Pi TSCýTsc 0.31',
TEC. TEH 0.61 'NBAZB 65 TEC. TEH 0.61. :NBAZB, 6 'H H
TSC1 0.19;
'31 75 3.36 181 DNT TEC TEl -0.61 NBAZB 6. 'H DH 41 75' 5.'35,178 DNT P1 0.o.24 TEC, TEHý 0 *61' NBAZB 5, H 0.19
'75 6."17 :1i76, DNT 45 75 2157 176 DNT 0O.19 TEC: TEH 0.61 :NBAZB, 5 ',H Page 3 of 8
.Attachment'2 Ginna Steam Generator B Cold Leg BobbminCodi Dents* (2011 RFO)
ROW COL VOLTS DEG IND PER1 CHN LOCN INCHi iNCH2 BEGT ENDT :PDIA CAL L PTYPE CiA' 47 7S ,16.84. .177, NT mTSC: 0.19 TEC TEH 6;:61 NBAZB- 5 H'
.75 17.918 DN T TSC .TEC TEH 0.61 NBAZB 5 H
.0.19 0.19 75 10.25 '177 DNT TSC TEC, TEH 0:61 'NBAZB: 5, H
.P1 TSC' 0.24 53 75 4.94 1.75 DNT. XEC TEH 0.`61- NBAZB 5- H, 0.14 55 .75 8.95 178 DNT T-SC TECO TIEH 0-.'61 NBAZB 5 HK 57 5.05 181 DONT TsC TEC, TEH 0.61- NBAZB. 5. H-0.17
- 76. 2.52 ý182 DNT 309 TSC TEC: TEH 0.61ý NBAZBg 6' H 40* 6.74 177 DNT ;P.1 TSK TEO TEH 0:61 NBAZB 6 H.
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'30 ;TSC 'TEO TEH 70.61 NBAZB 52; H, 32 780 4;6. 178- DNT TEC TEH 0.61 NBAZB 5 H 42 *8 4.3 176 DNT 0.21 TEC 'TEH 0.61, NBAZB 2 H
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TSC TEH 0.61 NBAZB 5 H 81 :2.72 0*23 29 4183 DNT Tsc. TEH 0.611 NBAZB ý5 H 41 :81 75.82 181 DNT P1l 0.27
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- 49 16.91, 179 DNT TEH 0.61 NBAZB 2 H TECý,
- 51 "6 180 DNT TIEH 0.61. NBAZB -2 H Page 4 of 8
Attachment` 2 Gmina Steam Generator B Cold Leg BobbinCoil Dents (2011 RFO)
ROW COL VOLTS DEG IND PER tCHN LOCN INCH* INCH2 BEGT IENDT. PDIA PTYPE' CAL uTiL1 53 81 271i:i18 DNT TSC 0472 TEC TEH 0.61, NBAZB 2 I
- 82. 2.15 176 DNT P1, Pi. TSC 0.12 TEO. TEH '0.6i NBAZB 5 H
.P1 40 !82 :4.53 181 DNT TSC 0.27 TEC TEH U0.61: NBAZB 2 H 42 82, '30,89 '80 DNT' P1. TSC .0.32 TEC TEH *.0.* NBAZB 2[ Hi 44 82 1,6.5. 179 D TSC TEC EH 061 NBAZB 2 H P1L 48 0b:24 TEC TEH 0.561 NBAZB ;2 H 50 82 '15.01 180 DNT TSC TEC TEH '0.6,1, NBA-ZB 2 H, 0.19 52 82' 937 179' DNT "TSC TEC TEHR .61I NBAZB 2 H PJ1 0.149-54 82, 4.01t 181 DNT TSC TEC TEH D0.61, NBAZB 2: H P1 J37 Pi1 TSC 39 TEC TEH 0-61i NBAZB 6 H 41 `83, ;26J79 179 DNT` -TsC 0.38 TEC TEH, 0:61. NBAZB I H
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83 13.9 180ONT PI TISC 0.31 TEC TEH 0.61 NBAZB 1 H 51 P1, .0.24:
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!TSC- TEC TEH 0.61 BAZ.B 6 H 84 2.16' 186- DNTr TSCý TEC TEH, 0.A61ý NBAZB 6 H 38 ,84 16.1-1 178 DNT G038- TEC TEH ý0.61 NBAZB I H P1,
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- 38 TEC, T'EH' 0.61 N-B'A.Z 2, H 86' 10.05: 177 DNT P.i -012 TECI TEHI 0.61 NBAZB 2. 'H 86, 20.79, 180 DNT TEC TEH ý0.61 NBAZB 2H A28 86 26.48ý `180 ONT PI TSC,* TEC: TEH 0.61 NBAZB 2 'H
- 44 86 12.71 179 DNT TSC; 0.29 86 -5.58 176 DNT
- 48 86 2.86 184; DNT 0.24, TECI TEH 0.61 NBAZB - 2 :H Page 5 of 8
Attachment 2 Ginia Steam Generator BCold Leg rBobbin:CoilDents' (2011 RFO)
ROW COL VOLTS, .DEG, IND PER,- CHN LOCN INCHi INCH2" BEGT ENDT PDIA, PTYPE CAL L, U ILI 17 P1 TSC 0.27 TE C TE H 0061 NBAZB 6 H 23 87 5.'18 .P1 "sc.
183 DOT 0,25 TEC TEH 0.61 NBAZB 6, H
- P1, TSC-37' 87 6.99, 178 DNT 'TSC 0.24 TEC TEH 0.61, NBAZB 6, H 39 87 13.13 178 DNT, PI. 0.25 TEC -TEH 0.61: NBAZB 1 H 41 -87 213.93 179 DIT PI 0'46 TEC TEH 0:6*1 NBAZB '1 H
-TSC 43 87J9.49 178DT TEC TEH 0.61 NBAZB 1 H 5.7_7 179 DNT' TSc 0:22 TEC TEH 0.61 NBAZB 1 H 45 87 'P1 Pl.1 47 87 3.4 177 DNT 'TSC 0.24 TEC TEH 0D61 NBAZB 1 H
,16 *88: 6&.21, 179 DNT ýTSC 0.2-7 'TEC TEH 0.Q61 NBAZB6 H6 18 88, 8.33, 180 ONT P1 T'SC 0A TEC TEH 0.61 NBAZB 6 H
'22 88 2.4 i10 DbNT P1- TEC TEH .0I'61 NBAZB 6 H 0'19
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- 42. ;8; 28.78 179 DIjb TEC TEH 0.61 NBAZB 1 H 0:034,
'44 ,88 6.'61, 178 DN0T' TSC TEC. TUEH 0.,61 : NBAZB I H" 89: 2828 181* DNT TSC 0.2' 'TEC TEH 0.61 NBAZB 5 H 23 89, 9ý.58& 181. ýDNT P1' ýTSc TEC -TEH 0'61i, NBAZb 5:5'H i89. :3.:44; 18s0 )NT*
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TETc. - TEH 0.61 NBAZB 5 H 40 ý90ý 17.44 179ý DNT Pi P1 TEC 'tEH 0.61, NBAZB 4, H 42 :90, 9.48 '179" DNT P1l P1 TSC: b0..!ST TEC 'TEH 0.6i NBAZB 4 H P1' 44: ;90 7.53 178, DNT P,1 TSc TEC: TEHTý 0.61 NBAZB .4. H P1I TK7c 46& ;9.0 :6.66 178' DNT' PI TSc TECJ TEHA 0.61 NBAZB 4- H
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37 91, 14'73 177' DNT 'SCY '0:29 ýTEcII TEH .0:61 NBAZB 6 H
'91, Tsc 0*34; TEH ,0.61 NBAZB 3 39 15.31. '178; DNT TE'C 'H 43' 91 '.-41 176' DNTI P-,I TSc 'T(( E'. 061. NBAB '3 H
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- 316 92. 14.51 178 DNT T.ECý TEHI -0.61 NBAZB 4- H 38' 92 18.57 "178 DNT TSc
- TEC TEHz 0.61 NBAZB -3, -H Page 6 of 8
AIttachmenfi 2 GinnaSteam Generator BCold ILeg BobbinrCoili Dents (2011 RFO) oL VOLTS' DEGl tROW ID PER' CHAICN LOCN I INNH "BEýGT E PIiA 06T PTYPE ýCAL L. UTi 40 '92 45A4 1.78 DNT" P1 Tsc 0.29- TEC TEH 0.61 NBAZB 3, H' 42 92 2'.151 180 DNT P1. T SC, ý0:2.4. TEC -TEH' 0.61. NBAZB .3' H:
35 !93 10.1 180. DNT P1 TSC 0.27ý "TEC TEH, 0.61 NBAZB 5 H
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Aftachment: 2 Steam Generator B HotLeg BobbinC.0i;l Dents (2011 RFO)
ROW! C VLVTS- DEG IND PER CHN ILCN INCti INCH2 ENDT PIAXEGT*
P'IPE C-WL I fL.TILl 37 *T.75 3ý.05 179 .DNT 'Pl TSHH6H 0.25 TEC TEH 01 NBAZB Page 8 of 8
ATTACHMENT 3 Ginna Steam Generator A Tubesheet Map R.E. Ginna Nuclear Power Plant, LLC February 15, 2012
SG - A BOBBIN INSPECTION PROGRAM Attachment 3 R.E. Ginna 35RFO RGE RGEACL a 1 PLUGGED TUBE 0 1 Obstructed Tube in 2008 Attempt Full Length 241PS X 3000 TEST FULL LENGTH 40 IPS From HL Then If Neccissary Test Remainder From the CL X 241 TEST FULL LENGTH 24 IPS lCentral Box Area I 95 -
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