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{{#Wiki_filter:Calvert Cliffs Nuclear Power Plant Constellation Energy-Nuclear Generation Group 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 December 3, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
{{#Wiki_filter:Calvert Cliffs Nuclear Power Plant                               1650 Calvert Cliffs Parkway Lusby, Maryland 20657 Constellation Energy-Nuclear Generation Group December 3, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:               Document Control Desk


==SUBJECT:==
==SUBJECT:==
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-318 Response to Request for Additional Information  
Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-318 Response to Request for Additional Information - 180 Day Report on the Spring 2008 Steam Generator Tube Inspection
-180 Day Report on the Spring 2008 Steam Generator Tube Inspection (a) Letter from Mr. M. D. Flaherty (CCNPP), to Document Control Desk (NRC), dated July 31, 2008, Spring 2008 -180 Day Steam Generator Report


==REFERENCES:==
==REFERENCES:==
(b) Letter from Mr. D. V. Pickett (NRC) to Mr. J. A. Spina (CCNPP), dated October 15, 2008, Request for Additional Information Re: 180-Day Report on the Spring 2008 Steam Generator Tube Inspection-Calvert Cliffs Nuclear Power Plant, Unit No. I (TAC No. MD9446)In Reference (a), Calvert Cliffs Nuclear Power Plant submitted the 180 Day Report on the Spring 2008 Unit I Steam Generator Tube Inspection.
(a)    Letter from Mr. M. D. Flaherty (CCNPP), to Document Control Desk (NRC), dated July 31, 2008, Spring 2008 - 180 Day Steam Generator Report (b)   Letter from Mr. D. V. Pickett (NRC) to Mr. J. A. Spina (CCNPP), dated October 15, 2008, Request for Additional Information Re: 180-Day Report on the Spring 2008 Steam Generator Tube Inspection- Calvert Cliffs Nuclear Power Plant, Unit No. I (TAC No. MD9446)
In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted to support their review of the report. Our response to this request is attached.Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410),495-5219.
In Reference (a), Calvert Cliffs Nuclear Power Plant submitted the 180 Day Report on the Spring 2008 Unit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted to support their review of the report. Our response to this request is attached.
Very truly yours, Mark D. Flaherty Manager -Engineering Services MDF/KLG/bjd
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410),495-5219.
Very truly yours, Mark D. Flaherty Manager - Engineering Services MDF/KLG/bjd


==Attachment:==
==Attachment:==
(1)    Response to Request for Additional Information -- Unit 1 180 Day Steam Generator Report cc:      D. V. Pickett, NRC                                Resident Inspector, NRC S. J. Collins, NRC                                S. Gray, DNR X047
                                                                                                        .QV4?


(1)Response to Request for Additional Information
ATTACHMENT (1)
-- Unit 1 180 Day Steam Generator Report cc: D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC S. Gray, DNR X047.QV4?
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1 180 DAY STEAM GENERATOR REPORT Calvert Cliffs Nuclear Power Plant, Inc.
ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
December 3, 2008
-- UNIT 1 180 DAY STEAM GENERATOR REPORT Calvert Cliffs Nuclear Power Plant, Inc.December 3, 2008 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
 
-- UNIT 1180 DAY STEAM GENERATOR REPORT RAI 1: For each refueling outage since installation of the steam generators (SGs), please provide the cumulative effective full power months that the SGs have operated.CCNPP Response: As of the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) Unit 1 2004 refueling outage, both SGs 11 and 12 had operated for 21.13 effective full power months (EFPM). As of the 2006 refueling outage, they had operated for 42.38 EFPM. As of the 2008 refueling outage, they have operated for 64.34 EFPM.RAI 2: In the report, it is stated that "324fan bar wear (FBW) indications in 272 tubes were identified in the Calvert Cliffs Nuclear Power Plant Unit 1 SGs during the spring 2008 inspection; an increase of approximately 2/3fioom the 189 indications in 166 tubes identified during the 2004 inspection." Please describe any insights on the cause of the increase of FBW indications.
ATTACHMENT (1)
Please also describe the size distribution of the new FBW indications found in the spring 2008 inspection in comparison to the size distribution of the FBW indications found in the 2004 inspection.
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT
If the size distribution of the new indications is comparable or more severe than the size distribution of the old indications, please discuss whether the conditions are becoming worse with time. Please also discuss what tubes are considered to be in the "'pre-definedfan bar wear susceptible region" and why it appears to differ between the two SGs.CCNPP Response: Based on the known degradation mechanism of FBW in Babcock and Wilcox (B&W) replacement SGs, it was expected that there would be new indications of FBW during the 2008 inspection.
 
Fan bar wear is caused by locally increased tube support clearances.
===RAI 1===
These increased clearances may be the result of a different method of bundle support used during manufacturing, or the result of grid adjustments that were made to improve manufacturability.
For each refueling outage since installationof the steam generators(SGs), pleaseprovide the cumulative effective full power months that the SGs have operated.
These causes do not change with time, so the condition of the SGs is not becoming worse with time. Indications of wear in new tube locations during the 2008 inspection were seen because wear occurs over a spectrum of wear rates. Those locations with higher wear rates were evident as wear indications during the first inspection in 2004. Areas with lower wear rates likely had wear below the detectability threshold in 2004, and only after an additional two cycles of operation did they show up as "new" wear in 2008. In all cases, the FBW rate is expected to slow dramatically after wear is initiated.
CCNPP Response:
This was supported by the 2008 inspection results which revealed only a small growth rate of existing indications.
As of the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) Unit 1 2004 refueling outage, both SGs 11 and 12 had operated for 21.13 effective full power months (EFPM). As of the 2006 refueling outage, they had operated for 42.38 EFPM. As of the 2008 refueling outage, they have operated for 64.34 EFPM.
 
===RAI 2===
In the report, it is stated that "324fan bar wear (FBW) indications in 272 tubes were identified in the Calvert Cliffs Nuclear Power Plant Unit 1 SGs during the spring 2008 inspection; an increase of approximately 2/3fioom the 189 indicationsin 166 tubes identified during the 2004 inspection." Please describe any insights on the cause of the increase of FBW indications. Please also describe the size distribution of the new FBW indicationsfound in the spring 2008 inspection in comparison to the size distribution of the FBW indicationsfound in the 2004 inspection. If the size distribution of the new indications is comparableor more severe than the size distribution of the old indications,please discuss whether the conditions are becoming worse with time. Please also discuss what tubes are consideredto be in the "'pre-definedfanbar wear susceptible region" andwhy it appearsto differ between the two SGs.
CCNPP Response:
Based on the known degradation mechanism of FBW in Babcock and Wilcox (B&W) replacement SGs, it was expected that there would be new indications of FBW during the 2008 inspection. Fan bar wear is caused by locally increased tube support clearances. These increased clearances may be the result of a different method of bundle support used during manufacturing, or the result of grid adjustments that were made to improve manufacturability. These causes do not change with time, so the condition of the SGs is not becoming worse with time. Indications of wear in new tube locations during the 2008 inspection were seen because wear occurs over a spectrum of wear rates. Those locations with higher wear rates were evident as wear indications during the first inspection in 2004. Areas with lower wear rates likely had wear below the detectability threshold in 2004, and only after an additional two cycles of operation did they show up as "new" wear in 2008. In all cases, the FBW rate is expected to slow dramatically after wear is initiated. This was supported by the 2008 inspection results which revealed only a small growth rate of existing indications.
In addition the FBW indications, first reported in 2008, were generally shallower than those reported in 2004, despite having been in service three times longer. This can be seen by the results presented in Figures 1 and 2 below. Figure 1 shows the FBW indications that were reported in 2004. Figure 2 shows the indications that were first reported in 2008, which are, on average, shallower.
In addition the FBW indications, first reported in 2008, were generally shallower than those reported in 2004, despite having been in service three times longer. This can be seen by the results presented in Figures 1 and 2 below. Figure 1 shows the FBW indications that were reported in 2004. Figure 2 shows the indications that were first reported in 2008, which are, on average, shallower.
I ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
I
-- UNIT 1180 DAY STEAM GENERATOR REPORT 2004 Fan Bar Wear Indications 35 *SG 11 ESG 12 o 25 0 20 .Lo 15-E 10 -z : L.. lih,. ..U 0 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (% Through-Wall)
 
Figure 1: 2004 Fan Bar Wear Indications 35 30 o 25 20 Sb.o 15 1..E 10 z 5 0 2008 New Fan Bar Wear Indications
ATTACHMENT (1)
*SG 11 ISG 12 I.. I All.lh1111 1 a,.I- ,E 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (%Through-Wall)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT 2004 Fan Bar Wear Indications 35-30-                                            *SG 11 ESG 12 o 25 0   20                   .
Figure 2: Fan Bar Wear Indications First Reported in 2008 To show the growth rate of wear from 2004 to 2008, Figure 3 shows the depth in 2008 of FBW indications that were first reported in 2004 (those values are shown in Figure 1). In comparing Figures 1 and 3, one can see that little overall growth occurred between 2004 and 2008, which supports the analysis that FBW growth slows over time. Based on the smaller size of new indications, and the very small growth rate of existing indications, it is concluded that conditions are not becoming worse with time.2 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
Lo 15-E 10 -
-- UNIT 1180 DAY STEAM GENERATOR REPORT 2008 Pre-Existing Fan Bar Wear 35 3SG 11 uSG 12 30 , o 25"am Z*0 20 ' ' 'C o 15 -E 10 f Z 5 -l a 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (%Through-Wall)
z 0
Figure 3: 2008 Distribution of Fan Bar Wear Indications First Reported in 2004 Regarding the "Pre-Defined Fan Bar Wear Susceptible Region," it is known from industry experience that FBW occurs at tubes with intermediate radii. This is confirmed by the following explanation provided by a B&W representative in an email response to Calvert Cliffs: "It is recognized that achieving small clearances between tubes and supports is essential for mitigation of wear. Within the susceptible region the tube to support clearances are somewhat variable since the layers of tubes are capable of laterally shifting within their available clearances.
L..:
If a few layers within the susceptible region bunch up then larger clearances may open in other positions within the susceptible region thereby initiating tube wear. The smaller radius tubes are stiffer in their out-of-plane direction and have less cross flow therefore have better clearance control and are less susceptible to wear and consequently are not within the susceptible region. Also the tubes closest to the external U-bend support structure are stiffer in their out-of- plane direction since the support structure maintains a regular pitch pattern. This enhanced pitch control in the region closest to the support structure helps to control the clearances and therefore is less susceptible to wear." The "fan bar wear susceptible region" was not defined to encompass every region that could possibly experience fan bar wear; rather it was defined to bound the location of the 2004 FBW indications, and therefore the region where higher growth rate wear is more likely. The possibility exists for less significant FBW to occur outside the defined susceptible region, and a sample of tubes was inspected throughout the rest of the SG to find any such wear. Between the two SGs, only 1 FBW indication was seen outside the "fan bar wear susceptible region." In SG 12, the susceptible region was slightly larger because a single indication was identified in 2004 that was located away from the location of the other indications.
lih,.         .     .U 0       2   4     6     8   10     12   14   16     18   20 22   24 Wear Depth (%Through-Wall)
Because this was a single indication, the main FBW susceptible region was left unchanged, but a conservative buffer of 60 tubes around this one tube was included in the buffer zone. The shaded regions of Figures 4 and 5 show the FBW susceptible region for SGs 11 and 12, respectively.
Figure 1: 2004 Fan Bar Wear Indications 2008 New Fan Bar Wear Indications 35
Also shown are the FBW indications identified in 2004, which 3 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
                                                                                  *SG 11 ISG 12 30 o 25 20 Sb.
-- UNIT 1180 DAY STEAM GENERATOR REPORT were used to determine the "fan bar wear susceptible region." Figures 6 and 7 show the entire inspection maps for SGs 11 and 12 respectively, which include the bundle peripheries and a sample of the rest of the tube bundles. They also show all of the FBW indications detected in 2008.Calvert Cliffs Unit 1 Fan Bar Wear -Critical Area and Buffer Zone GROUP TUBES 9 S 12,1104 Wwu N LI -3 1r JarWE Vlc- '~e _'c, C re -C -.r Be, 'Oeo CA 1 504 SUALE 60 (1534t X -Tue Jan 29 12:20 N 2M8LI SIG I I HOT PRI41ARY FACE TOTAL IUBES, 3411 SELETE.D TUBES 19M OUT OF SERVICE t#) NA NOI/i F-I .7t:~.-7:-737 t:-7 -t:-: -:t t- ------ -"- ----""-"-' " "' ' l:tT-:T -T--.-:7- --77* : " ".. ...t ... -t ... ..I: -::.I...I MANWAY Figure 4: Fan Bar Wear Susceptible Region for Steam Generator 11 4 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
o 15 1..
-- UNIT 1180 DAY STEAM GENERATOR REPORT Calvert Cliffs Unit 1 Fan Bar Wear -Critical Area and Buffer Zone GROUP TUBES SG 12 2004 Wear 87 B Fan Ear Wear BJfw Zone 389 C Fan Bar Wear CA 1605 S.G 12 HOT PRIMARY FACE TOTAL TUBES: 8471 SELECTED TUBES: 1994 OUT OF SERVICE (#): NA SCALE: 0.067388 X Tue Jan 29 12:09.19 2008.... .. ..NOZZLE-- -- -T,&1 ~ .r tIte--,ýý;-ýý,ýt'-ý.+.tlt.+ý,ýýt.tI  
E 10 z
----------
5 0
--------------7 ----- ----,1 MANWAY Figure 5: Fan Bar Wear Susceptible Region for Steam Generator 12 5 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
I..I All.lh1111*l'                    1a,.I- ,E 0     2     4     6     8   10     12   14   16   18   20 22   24 Wear Depth (%Through-Wall)
-- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP TUBES-HIDDEN Calvert Cliffs Unit 1 C 16M -125 1R18 Fan Bar Wear TestC, ... CA.BZ 238.-0 SO I I TOTAL TUBES. 8471 HOT SELECTED TUBES. 4261 PRIMARY FACE OUT OF SERVICE (t) I SCALE 0,087388 X Tue Mai 04 12 1 06 2008 NOZZLE-.4-" : .--: --= : :' : ' ................. ... .I i., I ._._.. _1. __-As MANWVAY Figure 6: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 11 6 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
Figure 2: Fan Bar Wear Indications First Reported in 2008 To show the growth rate of wear from 2004 to 2008, Figure 3 shows the depth in 2008 of FBW indications that were first reported in 2004 (those values are shown in Figure 1). In comparing Figures 1 and 3, one can see that little overall growth occurred between 2004 and 2008, which supports the analysis that FBW growth slows over time. Based on the smaller size of new indications, and the very small growth rate of existing indications, it is concluded that conditions are not becoming worse with time.
-- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP IUBES-HI-L)-
2
N 0 Fo~Br BtWcon 144-0 Calvert Cliffs Unit 1 C Ciuc.IArwou6  
 
,-.142 1 R1 8 Fan Bar Wear S.G 12 TOTAL TUBES. 8471 HOT SELECTED TUBES. 423ti PRIMARY FACE OUT OF SERVICE (3) 0 SCALE O W1388 X 1u. J M., U4 12 010 _1J 0M NOZZLE S ,4 4.. : -":el'++:l """+ '!4.4 74: --- --- --: --= ----- : :: -' '-> -'@:.~ ~ ~ ~~~~~~~~~~~~~~...
ATTACHMENT (1)
...... --" ' :. .:. .." " ' ..: iN t MAN WAY Figure 7: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 12 RAI 3: Please describe the scope and results of any secondary side inspections.
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT 2008 Pre-Existing Fan Bar Wear 35 3SG 11 uSG 12 30       ,
CCNPP Response: No secondary side inspections were performed during the 2008 SG inspection.
o 25 "am Z*
This was based upon the following:
0 20                                                 '     '       '
bobbin-probe eddy current was performed on 100% of the periphery and the no tube lane border to look for loose parts (see inspection map in Figures 6 and 7) and none were detected.
C o 15                           -
One tube (SG1 1 R8C130) contained a small indication of wear [7% through-wall (TW)] at the 5th lattice support on the hot side along with an indication that was most likely caused by a lattice bar burr. The surrounding tubes were examined with rotating probes and no foreign object or wear indications were identified.
E 10 f Z     5 -l a
Because the wear conditions in SG1 1 R8C 130 could not be visually investigated on the secondary side due to difficulty in reaching the location, the decision was made to conservatively treat the indication as a foreign object and to preventively stabilize and plug the tube.A secondary side visual inspection was a planned contingency with equipment and personnel available.
0     2   4     6     8   10   12   14     16   18   20   22     24 Wear Depth (%Through-Wall)
Figure 3: 2008 Distribution of Fan Bar Wear Indications First Reported in 2004 Regarding the "Pre-Defined Fan Bar Wear Susceptible Region," it is known from industry experience that FBW occurs at tubes with intermediate radii. This is confirmed by the following explanation provided by a B&W representative in an email response to Calvert Cliffs:
    "It is recognized that achieving small clearances between tubes and supports is essentialfor mitigation of wear. Within the susceptible region the tube to support clearancesare somewhat variable since the layers of tubes are capable of laterally shifting within their available clearances. If a few layers within the susceptible region bunch up then larger clearances may open in other positions within the susceptible region thereby initiating tube wear. The smaller radius tubes are stiffer in their out-of-plane direction and have less cross flow therefore have better clearance control and are less susceptible to wear and consequently are not within the susceptible region. Also the tubes closest to the external U-bend support structure are stiffer in their out-of- plane direction since the support structure maintains a regularpitch pattern. This enhanced pitch control in the region closest to the support structure helps to control the clearances and therefore is less susceptible to wear."
The "fan bar wear susceptible region" was not defined to encompass every region that could possibly experience fan bar wear; rather it was defined to bound the location of the 2004 FBW indications, and therefore the region where higher growth rate wear is more likely. The possibility exists for less significant FBW to occur outside the defined susceptible region, and a sample of tubes was inspected throughout the rest of the SG to find any such wear. Between the two SGs, only 1 FBW indication was seen outside the "fan bar wear susceptible region."
In SG 12, the susceptible region was slightly larger because a single indication was identified in 2004 that was located away from the location of the other indications. Because this was a single indication, the main FBW susceptible region was left unchanged, but a conservative buffer of 60 tubes around this one tube was included in the buffer zone. The shaded regions of Figures 4 and 5 show the FBW susceptible region for SGs 11 and 12, respectively. Also shown are the FBW indications identified in 2004, which 3
 
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT were used to determine the "fan bar wear susceptible region." Figures 6 and 7 show the entire inspection maps for SGs 11 and 12 respectively, which include the bundle peripheries and a sample of the rest of the tube bundles. They also show all of the FBW indications detected in 2008.
GROUP                       TUBES 9 S12,1104 Wwu                 N Calvert Cliffs Unit 1                                      LI -31r JarWE Vlc-       '~e_'c, Cre    -
Fan Bar Wear - Critical Area and Buffer Zone                                C -. r Be, 'Oeo CA               1504 SUALE 60(1534t X           -
SIG I I                                                               TOTALIUBES, 3411 HOT                                                               SELETE.D TUBES 19M           Tue Jan 29 12:20 N 2M8LI PRI41ARYFACE                                                      OUT OF SERVICE t#) NA NOI/i F
                                                                                    -I .7t:~.
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I...I MANWAY Figure 4: Fan Bar Wear Susceptible Region for Steam Generator 11 4
 
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP                    TUBES SG 12 2004 Wear               87 Calvert Cliffs Unit 1                                                            B Fan Ear Wear BJfw Zone       389 C Fan Bar Wear CA             1605 Fan Bar Wear - Critical Area and Buffer Zone SCALE: 0.067388 X S.G 12                                                                                    TOTAL TUBES: 8471       Tue Jan 29 12:09.19 2008 HOT                                                                                  SELECTED TUBES: 1994 PRIMARY FACE                                                                          OUT OF SERVICE (#): NA NOZZLE
                                          -- --     ~
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MANWAY Figure 5: Fan Bar Wear Susceptible Region for Steam Generator 12 5
 
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP           TUBES-HIDDEN Calvert Cliffs Unit 1                                       C                       16M -125 1R18 Fan Bar Wear                                               TestC, ... CA.BZ     238.-0 SO I I                                                                     TOTAL TUBES. 8471 HOT                                                                   SELECTED TUBES. 4261 PRIMARY FACE                                                           OUT OF SERVICE (t)   I         SCALE 0,087388 X Tue Mai 04 12 1 06 2008 NOZZLE
                                                      -. 4-
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                                                                            -As MANWVAY Figure 6: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 11 6
 
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP               IUBES-HI-L)-   N 0 Fo~Br                       144-0 Calvert Cliffs Unit 1                                                             BtWcon C Ciuc.IArwou6                 ,-.142 1R1 8     Fan Bar Wear                                                       Tested*OutsideCA8Z        2242:*
S.G 12                                                                           TOTAL TUBES. 8471 HOT                                                                           SELECTED TUBES. 423ti PRIMARY FACE                                                                   OUT OF SERVICE (3)     0               SCALE O W1388 X 1u.J M., U4 12 010 _1J 0M NOZZLE
                                                                      ,4 4..                   : -":el'++:l
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iN                                                                               t MANWAY Figure 7: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 12
 
===RAI 3===
Pleasedescribe the scope and results of any secondaryside inspections.
CCNPP Response:
No secondary side inspections were performed during the 2008 SG inspection. This was based upon the following: bobbin-probe eddy current was performed on 100% of the periphery and the no tube lane border to look for loose parts (see inspection map in Figures 6 and 7) and none were detected. One tube (SG1 1 R8C130) contained a small indication of wear [7% through-wall (TW)] at the 5th lattice support on the hot side along with an indication that was most likely caused by a lattice bar burr. The surrounding tubes were examined with rotating probes and no foreign object or wear indications were identified.
Because the wear conditions in SG1 1 R8C 130 could not be visually investigated on the secondary side due to difficulty in reaching the location, the decision was made to conservatively treat the indication as a foreign object and to preventively stabilize and plug the tube.
A secondary side visual inspection was a planned contingency with equipment and personnel available.
An inspection would have been performed if conditions required it. However, as stated above, the wear on tube SG 11 R8C 130 could not be investigated because of the difficulty in reaching that location, so a secondary side inspection was not conducted for that indication.
An inspection would have been performed if conditions required it. However, as stated above, the wear on tube SG 11 R8C 130 could not be investigated because of the difficulty in reaching that location, so a secondary side inspection was not conducted for that indication.
It should also be noted that the 2004 Unit 1 SG inspection consisted of a 100% bobbin inspection and an extensive secondary side visual inspection.
It should also be noted that the 2004 Unit 1 SG inspection consisted of a 100% bobbin inspection and an extensive secondary side visual inspection. During this 2004 inspection no foreign objects were detected 7
During this 2004 inspection no foreign objects were detected 7 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
 
-- UNIT 1180 DAY STEAM GENERATOR REPORT in the Unit I SGs. Therefore it is believed that foreign material intrusion is not a significant problem for Calvert Cliffs Unit I SGs.RAT 4: Please discuss the nature of the "ambiguous bobbin indications." CCNPP Response: The term "ambiguous bobbin indication" was used to refer to any indication that was not caused by FBW and required follow-up testing. There were six "ambiguous bobbin indications" on SG 11 and three on SG 12, as shown in Table I below. After inspection with a rotating probe coil, all of these indications were confidently classified as described below.* SGlI R8C130 showed an indication of a lattice grid burr and was conservatively plugged as described above." The indications in tubes SGII R17C55, SG11 R115C125, and SGI 1 R137C83 were determined not to represent tube damage or degradation after inspection with a rotating probe coil.* The indications in tubes SG1 1 R78C94, SG12 R122C86, and SG12 R134C88 were determined to be wear caused by lattice support wear. Based on the low observed growth rate from the initial operation of the SGs to the 2008 inspection, it was concluded that these indications will not threaten tube integrity before the next scheduled inspection.
ATTACHMENT (1)
* The indications in tubes SGI 1 R126C 114 and SG12 R106C134 were determined to be caused by foreign objects. In both cases, no foreign objects remained adjacent to the tube. More information about the evaluation of these indications is provided in the response to RAI 8.Table 1: Description of"Ambiguous" Bobbin Indications Foreign Steam Offset Maximum Cause o F Object Plugged Generator Row Column Elevation (in) Depth Damae POtent and (in) (%TW) Damage Potentially Stabilized Present 11 8 130 05H -1.51 7 Foreign Object Yes* Yes Wear 11 17 55 TSC -0.13 N/A No Damage No No 11 78 94 04H 0.51 11 Lattice Support No No Wear 11 115 125 F07 12.11 N/A No Damage No No 11 126 114 TSH 0.95 26 Foreign Object No No Wear 11 137 83 F06 12.09 N/A No Damage No No 12 106 134 TSH 7.12 30 Foreign Object No No Wear 12 122 86 07C 1.07 9 Lattice Support No No Wear 12 134 88 02H -1.53 14 Lattice Support No No I I_ Wear Lattice support burr or small foreign object. Conservatively treated as foreign object.8 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT in the Unit I SGs. Therefore it is believed that foreign material intrusion is not a significant problem for Calvert Cliffs Unit I SGs.
-- UNIT 1180 DAY STEAM GENERATOR REPORT RAI 5: Presumably, a number of new bobbin indications were identified near the fan bars. Of tlwse new bobbin indications, it does not appear that all were inspected with rotating probes and that only those indications greater than 15% through-wall were inspected with a rotating probe. If the Nuclear Regulatory Commission staff's understanding is correct, discuss how the causal mechanisms for these new bobbin indications were determined.
RAT 4:
Please discuss how wear attributed to tube-to-tube contact and loose parts was ruled out as the causal mechanism.
Please discuss the natureof the "ambiguousbobbin indications."
CCNPP Response: A cutoff of 15% TW for inspecting with rotating probes was chosen to provide a reasonably large inspection population of large wear in order to confirm that the length of the new and pre-existing wear did not exceed the bounding value of length used in the Condition Monitoring  
CCNPP Response:
/ Operational Assessment report. During the 2004 inspection, all indications of FBW were inspected with a rotating probe coil.Because there was very little growth of existing indications, it was determined that only the tubes with the largest wear needed to be inspected in 2008 in order to confirm that the wear had the same characteristics.
The term "ambiguous bobbin indication" was used to refer to any indication that was not caused by FBW and required follow-up testing. There were six "ambiguous bobbin indications" on SG 11 and three on SG 12, as shown in Table I below. After inspection with a rotating probe coil, all of these indications were confidently classified as described below.
The plants that operate B&W replacement SGs share their experiences at an annual meeting and through interim phone calls. None of these plants have experienced foreign object wear in the fan bar region, and it is unlikely that a part small enough to work its way that high in the SG could cause significant damage.Additionally, the fan bar supports have only two offset contact points with the tube, whereas the lattice supports have four contact points, which further decreases the likelihood of a loose part causing damage at a fan bar support rather than becoming stuck at a lattice support. Based on this information, the absence of loose part indications in the eddy current data was taken as reasonable assurance that the wear identified was not caused by loose parts. In addition, tube-to-tube contact was ruled out because FBW occurs only at the fan bar supports, while tube-to-tube contact occurs between supports.
* SGlI R8C130 showed an indication of a lattice grid burr and was conservatively plugged as described above.
The fan bars are identifiable with eddy current by their unique signal, and no wear indications were identified away from the fan bar supports.RAI 6: Please discuss whether any tubes were identified that were in close proximity.
"   The indications in tubes SGII R17C55, SG11 R115C125, and SGI 1 R137C83 were determined not to represent tube damage or degradation after inspection with a rotating probe coil.
CCNPP Response: There were no tubes identified via eddy current inspection that were in close proximity to one another.RAI 7: Please provide a list of all service induced indications including their location, orientation (if linear) and measured sizes.CCNPP Response: There have been no linear indications detected at Calvert Cliffs. All of the indications of degradation identified during the 2008 SG inspection were volumetric in nature. The details of the length and size of the indications are provided in Enclosure (1) (SG 11) and Enclosure (2) (SG 12).RAI 8: Please discuss whether a secondary side visual inspection was performed near the tubes attributed to foreign object wear (SG11 R126C1J4 and SG12 R106C134) to confirm the absence of a loose part. In 9 ATTACHMENT (1)RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION  
* The indications in tubes SG1 1 R78C94, SG12 R122C86, and SG12 R134C88 were determined to be wear caused by lattice support wear. Based on the low observed growth rate from the initial operation of the SGs to the 2008 inspection, it was concluded that these indications will not threaten tube integrity before the next scheduled inspection.
-- UNIT 1180 DAY STEAM GENERATOR REPORT addition, please discuss whether potential loose part indications (from the eddy current data) were visually inspected to identify and remove any loose parts. If any possible loose part indications were left in service without visual inspection, please discuss how it was confirmed that tube integrity would be maintained CCNPP Response: No secondary side inspection was performed near the two tubes with indications attributed for foreign object wear (SG1 I R126C1 14 and SG12 R106C134).
* The indications in tubes SGI 1 R126C 114 and SG12 R106C134 were determined to be caused by foreign objects. In both cases, no foreign objects remained adjacent to the tube. More information about the evaluation of these indications is provided in the response to RAI 8.
These indications were dispositioned based on eddy current results. For SGI I R126C 114 and SGI2 R106C134, 3-coil rotating probes were used in these tubes and in the bounding surrounding tubes (at least 1 tube deep) and no foreign object was found.Both of these indications were sized using the most conservative eddy current sizing technique for the condition involved (rotating probe technique 27903.1).No indications of potential loose parts were identified during this inspection other than the tube (SGl 1 R8C130) that was plugged and removed from service as discussed earlier. Since no objects remain adjacent to any of the remaining in service tubes (see Table I above) that have experienced foreign object wear there is no potential for continued, ongoing damage from this cause. The inspection also demonstrated that the wear caused to date is not a threat to the structural integrity of the tubes going forward. However, the potential for undetected foreign object wear and the development of new foreign object wear in each SG during ensuing operating intervals must be considered.
Table 1: Description of"Ambiguous" Bobbin Indications Foreign Steam                                           Offset   Maximum         Cause o     F Object     Plugged Generator     Row     Column       Elevation     (in)       Depth         Damae         POtent         and (in)     (%TW)           Damage       Potentially Stabilized Present 11         8         130         05H       -1.51         7       Foreign WearObject    Yes*       Yes 11         17         55         TSC       -0.13       N/A         No Damage         No         No 11         78         94         04H         0.51         11       Lattice Support     No           No Wear 11       115         125         F07       12.11       N/A         No Damage           No         No 11         126       114         TSH         0.95         26       Foreign Object     No         No Wear 11         137         83           F06       12.09       N/A         No Damage           No         No 12       106         134         TSH         7.12         30       Foreign Object     No         No Wear 12       122         86         07C         1.07         9       Lattice Support     No         No Wear 12       134         88         02H       -1.53         14       Lattice Support     No         No I                     I_                                         Wear Lattice support burr or small foreign object. Conservatively treated as foreign object.
It is difficult to predict if and when foreign object wear -a random and inherently unpredictable phenomenon  
8
-will occur.However, by examining the aggregate operating history of Calvert Cliffs Unit 1 SGs with respect to foreign object wear, a judgment of the risk was developed.
 
During the 2004 Unit I inspection, extensive secondary side examinations were performed along with an eddy current examination of all tubes in both SGs. These inspections revealed no foreign objects which could damage SG tubes and revealed no foreign object related tube damage. After two additional cycles of operation, the 2008 Unit 1 inspections, which included the entire bundle periphery two-to-four tubes deep, revealed no foreign object wear which challenged integrity performance criteria, and identified only one tube with an adjacent potential foreign object indication (the tube which was plugged during the 2008 inspection).
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT
 
===RAI 5===
Presumably,a number of new bobbin indications were identified near the fan bars. Of tlwse new bobbin indications,it does not appearthat all were inspectedwith rotatingprobes and that only those indications greater than 15% through-wall were inspected with a rotating probe. If the Nuclear Regulatory Commission staff's understanding is correct, discuss how the causal mechanismsfor these new bobbin indications were determined. Please discuss how wear attributedto tube-to-tube contact and loose parts was ruled out as the causal mechanism.
CCNPP Response:
A cutoff of 15% TW for inspecting with rotating probes was chosen to provide a reasonably large inspection population of large wear in order to confirm that the length of the new and pre-existing wear did not exceed the bounding value of length used in the Condition Monitoring / Operational Assessment report. During the 2004 inspection, all indications of FBW were inspected with a rotating probe coil.
Because there was very little growth of existing indications, it was determined that only the tubes with the largest wear needed to be inspected in 2008 in order to confirm that the wear had the same characteristics.
The plants that operate B&W replacement SGs share their experiences at an annual meeting and through interim phone calls. None of these plants have experienced foreign object wear in the fan bar region, and it is unlikely that a part small enough to work its way that high in the SG could cause significant damage.
Additionally, the fan bar supports have only two offset contact points with the tube, whereas the lattice supports have four contact points, which further decreases the likelihood of a loose part causing damage at a fan bar support rather than becoming stuck at a lattice support. Based on this information, the absence of loose part indications in the eddy current data was taken as reasonable assurance that the wear identified was not caused by loose parts. In addition, tube-to-tube contact was ruled out because FBW occurs only at the fan bar supports, while tube-to-tube contact occurs between supports. The fan bars are identifiable with eddy current by their unique signal, and no wear indications were identified away from the fan bar supports.
 
===RAI 6===
Pleasediscuss whether any tubes were identifiedthat were in close proximity.
CCNPP Response:
There were no tubes identified via eddy current inspection that were in close proximity to one another.
 
===RAI 7===
Pleaseprovide a list of all service induced indicationsincluding their location, orientation (if linear)and measuredsizes.
CCNPP Response:
There have been no linear indications detected at Calvert Cliffs. All of the indications of degradation identified during the 2008 SG inspection were volumetric in nature. The details of the length and size of the indications are provided in Enclosure (1) (SG 11) and Enclosure (2) (SG 12).
 
===RAI 8===
Please discuss whether a secondary side visual inspection was performed near the tubes attributedto foreign object wear (SG11 R126C1J4 and SG12 R106C134) to confirm the absence of a loose part. In 9
 
ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT addition, please discuss whether potential loose part indications (from the eddy current data) were visually inspected to identify and remove any loose parts. If any possible loose part indications were left in service without visual inspection, please discuss how it was confirmed that tube integrity would be maintained CCNPP Response:
No secondary side inspection was performed near the two tubes with indications attributed for foreign object wear (SG1 I R126C1 14 and SG12 R106C134). These indications were dispositioned based on eddy current results. For SGI I R126C 114 and SGI2 R106C134, 3-coil rotating probes were used in these tubes and in the bounding surrounding tubes (at least 1 tube deep) and no foreign object was found.
Both of these indications were sized using the most conservative eddy current sizing technique for the condition involved (rotating probe technique 27903.1).
No indications of potential loose parts were identified during this inspection other than the tube (SGl 1 R8C130) that was plugged and removed from service as discussed earlier. Since no objects remain adjacent to any of the remaining in service tubes (see Table I above) that have experienced foreign object wear there is no potential for continued, ongoing damage from this cause. The inspection also demonstrated that the wear caused to date is not a threat to the structural integrity of the tubes going forward. However, the potential for undetected foreign object wear and the development of new foreign object wear in each SG during ensuing operating intervals must be considered. It is difficult to predict if and when foreign object wear - a random and inherently unpredictable phenomenon - will occur.
However, by examining the aggregate operating history of Calvert Cliffs Unit 1 SGs with respect to foreign object wear, a judgment of the risk was developed. During the 2004 Unit I inspection, extensive secondary side examinations were performed along with an eddy current examination of all tubes in both SGs. These inspections revealed no foreign objects which could damage SG tubes and revealed no foreign object related tube damage. After two additional cycles of operation, the 2008 Unit 1 inspections, which included the entire bundle periphery two-to-four tubes deep, revealed no foreign object wear which challenged integrity performance criteria, and identified only one tube with an adjacent potential foreign object indication (the tube which was plugged during the 2008 inspection).
The two wear indications attributed to foreign objects which remain in service were caused by migratory foreign objects no longer present adjacent to the affected tubes. These objects were not located during this examination and have either moved out of the SGs through the blowdown system and are no longer capable of causing tube damage, or have moved to a new location within the tube bundle. Migratory objects are known to move in the direction of the flow, toward the interior of the tube bundle and toward areas of lower flow. Both affected tubes are located on the bundle periphery which is the area of maximum cross flow and therefore the area which poses the highest potential for developing deep foreign object wear. Yet in this location the objects did not cause structurally significant tube damage. If the objects remain in the bundle they have likely moved inboard to a region of the bundle with lower cross flow and lower potential to cause significant tube damage. Therefore, if they remain within the tube bundle, the objects are judged to be unlikely to pose a threat to tube integrity.
The two wear indications attributed to foreign objects which remain in service were caused by migratory foreign objects no longer present adjacent to the affected tubes. These objects were not located during this examination and have either moved out of the SGs through the blowdown system and are no longer capable of causing tube damage, or have moved to a new location within the tube bundle. Migratory objects are known to move in the direction of the flow, toward the interior of the tube bundle and toward areas of lower flow. Both affected tubes are located on the bundle periphery which is the area of maximum cross flow and therefore the area which poses the highest potential for developing deep foreign object wear. Yet in this location the objects did not cause structurally significant tube damage. If the objects remain in the bundle they have likely moved inboard to a region of the bundle with lower cross flow and lower potential to cause significant tube damage. Therefore, if they remain within the tube bundle, the objects are judged to be unlikely to pose a threat to tube integrity.
Based on these observations, there is reasonable assurance that foreign object wear will not result in damage that exceeds the structural
Based on these observations, there is reasonable assurance that foreign object wear will not result in damage that exceeds the structural performance criteria prior to the next SG inspection. Because no wear exceeding the structural criteria is expected, it is concluded that the operational leakage and accident leakage performance criteria will not be exceeded by foreign object wear.
10
 
ENCLOSURE (1)
Steam Generator 11 Indication Report Calvert Cliffs Nuclear Power Plant, Inc.
December 3, 2008
 
ARVA NP Inc                                        03/07/08 14:28:27 Unit I            Co*ponent: $1G 11                      Paqe 2 of 4 CUtoeer Nam e; Calvert C1cfa3 FE Near Indicatiors  (Sort by Row/Cal)
QCUE3Y: FB Near Indications by rev R.OWCOL VOLTS  DEC

Revision as of 10:31, 14 November 2019

Response to Request for Additional Information - 180 Day Report on the Spring 2008 Steam Generator Tube Inspection
ML083460010
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 12/03/2008
From: Flaherty M
Constellation Energy Group, Nuclear Generation Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MD9446
Download: ML083460010 (32)


Text

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 Constellation Energy-Nuclear Generation Group December 3, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 1; Docket No. 50-318 Response to Request for Additional Information - 180 Day Report on the Spring 2008 Steam Generator Tube Inspection

REFERENCES:

(a) Letter from Mr. M. D. Flaherty (CCNPP), to Document Control Desk (NRC), dated July 31, 2008, Spring 2008 - 180 Day Steam Generator Report (b) Letter from Mr. D. V. Pickett (NRC) to Mr. J. A. Spina (CCNPP), dated October 15, 2008, Request for Additional Information Re: 180-Day Report on the Spring 2008 Steam Generator Tube Inspection- Calvert Cliffs Nuclear Power Plant, Unit No. I (TAC No. MD9446)

In Reference (a), Calvert Cliffs Nuclear Power Plant submitted the 180 Day Report on the Spring 2008 Unit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted to support their review of the report. Our response to this request is attached.

Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410),495-5219.

Very truly yours, Mark D. Flaherty Manager - Engineering Services MDF/KLG/bjd

Attachment:

(1) Response to Request for Additional Information -- Unit 1 180 Day Steam Generator Report cc: D. V. Pickett, NRC Resident Inspector, NRC S. J. Collins, NRC S. Gray, DNR X047

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1 180 DAY STEAM GENERATOR REPORT Calvert Cliffs Nuclear Power Plant, Inc.

December 3, 2008

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT

RAI 1

For each refueling outage since installationof the steam generators(SGs), pleaseprovide the cumulative effective full power months that the SGs have operated.

CCNPP Response:

As of the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) Unit 1 2004 refueling outage, both SGs 11 and 12 had operated for 21.13 effective full power months (EFPM). As of the 2006 refueling outage, they had operated for 42.38 EFPM. As of the 2008 refueling outage, they have operated for 64.34 EFPM.

RAI 2

In the report, it is stated that "324fan bar wear (FBW) indications in 272 tubes were identified in the Calvert Cliffs Nuclear Power Plant Unit 1 SGs during the spring 2008 inspection; an increase of approximately 2/3fioom the 189 indicationsin 166 tubes identified during the 2004 inspection." Please describe any insights on the cause of the increase of FBW indications. Please also describe the size distribution of the new FBW indicationsfound in the spring 2008 inspection in comparison to the size distribution of the FBW indicationsfound in the 2004 inspection. If the size distribution of the new indications is comparableor more severe than the size distribution of the old indications,please discuss whether the conditions are becoming worse with time. Please also discuss what tubes are consideredto be in the "'pre-definedfanbar wear susceptible region" andwhy it appearsto differ between the two SGs.

CCNPP Response:

Based on the known degradation mechanism of FBW in Babcock and Wilcox (B&W) replacement SGs, it was expected that there would be new indications of FBW during the 2008 inspection. Fan bar wear is caused by locally increased tube support clearances. These increased clearances may be the result of a different method of bundle support used during manufacturing, or the result of grid adjustments that were made to improve manufacturability. These causes do not change with time, so the condition of the SGs is not becoming worse with time. Indications of wear in new tube locations during the 2008 inspection were seen because wear occurs over a spectrum of wear rates. Those locations with higher wear rates were evident as wear indications during the first inspection in 2004. Areas with lower wear rates likely had wear below the detectability threshold in 2004, and only after an additional two cycles of operation did they show up as "new" wear in 2008. In all cases, the FBW rate is expected to slow dramatically after wear is initiated. This was supported by the 2008 inspection results which revealed only a small growth rate of existing indications.

In addition the FBW indications, first reported in 2008, were generally shallower than those reported in 2004, despite having been in service three times longer. This can be seen by the results presented in Figures 1 and 2 below. Figure 1 shows the FBW indications that were reported in 2004. Figure 2 shows the indications that were first reported in 2008, which are, on average, shallower.

I

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT 2004 Fan Bar Wear Indications 35-30- *SG 11 ESG 12 o 25 0 20 .

Lo 15-E 10 -

z 0

L..:

lih,. . .U 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (%Through-Wall)

Figure 1: 2004 Fan Bar Wear Indications 2008 New Fan Bar Wear Indications 35

  • SG 11 ISG 12 30 o 25 20 Sb.

o 15 1..

E 10 z

5 0

I..I All.lh1111*l' 1a,.I- ,E 0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (%Through-Wall)

Figure 2: Fan Bar Wear Indications First Reported in 2008 To show the growth rate of wear from 2004 to 2008, Figure 3 shows the depth in 2008 of FBW indications that were first reported in 2004 (those values are shown in Figure 1). In comparing Figures 1 and 3, one can see that little overall growth occurred between 2004 and 2008, which supports the analysis that FBW growth slows over time. Based on the smaller size of new indications, and the very small growth rate of existing indications, it is concluded that conditions are not becoming worse with time.

2

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT 2008 Pre-Existing Fan Bar Wear 35 3SG 11 uSG 12 30 ,

o 25 "am Z*

0 20 ' ' '

C o 15 -

E 10 f Z 5 -l a

0 2 4 6 8 10 12 14 16 18 20 22 24 Wear Depth (%Through-Wall)

Figure 3: 2008 Distribution of Fan Bar Wear Indications First Reported in 2004 Regarding the "Pre-Defined Fan Bar Wear Susceptible Region," it is known from industry experience that FBW occurs at tubes with intermediate radii. This is confirmed by the following explanation provided by a B&W representative in an email response to Calvert Cliffs:

"It is recognized that achieving small clearances between tubes and supports is essentialfor mitigation of wear. Within the susceptible region the tube to support clearancesare somewhat variable since the layers of tubes are capable of laterally shifting within their available clearances. If a few layers within the susceptible region bunch up then larger clearances may open in other positions within the susceptible region thereby initiating tube wear. The smaller radius tubes are stiffer in their out-of-plane direction and have less cross flow therefore have better clearance control and are less susceptible to wear and consequently are not within the susceptible region. Also the tubes closest to the external U-bend support structure are stiffer in their out-of- plane direction since the support structure maintains a regularpitch pattern. This enhanced pitch control in the region closest to the support structure helps to control the clearances and therefore is less susceptible to wear."

The "fan bar wear susceptible region" was not defined to encompass every region that could possibly experience fan bar wear; rather it was defined to bound the location of the 2004 FBW indications, and therefore the region where higher growth rate wear is more likely. The possibility exists for less significant FBW to occur outside the defined susceptible region, and a sample of tubes was inspected throughout the rest of the SG to find any such wear. Between the two SGs, only 1 FBW indication was seen outside the "fan bar wear susceptible region."

In SG 12, the susceptible region was slightly larger because a single indication was identified in 2004 that was located away from the location of the other indications. Because this was a single indication, the main FBW susceptible region was left unchanged, but a conservative buffer of 60 tubes around this one tube was included in the buffer zone. The shaded regions of Figures 4 and 5 show the FBW susceptible region for SGs 11 and 12, respectively. Also shown are the FBW indications identified in 2004, which 3

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT were used to determine the "fan bar wear susceptible region." Figures 6 and 7 show the entire inspection maps for SGs 11 and 12 respectively, which include the bundle peripheries and a sample of the rest of the tube bundles. They also show all of the FBW indications detected in 2008.

GROUP TUBES 9 S12,1104 Wwu N Calvert Cliffs Unit 1 LI -31r JarWE Vlc- '~e_'c, Cre -

Fan Bar Wear - Critical Area and Buffer Zone C -. r Be, 'Oeo CA 1504 SUALE 60(1534t X -

SIG I I TOTALIUBES, 3411 HOT SELETE.D TUBES 19M Tue Jan 29 12:20 N 2M8LI PRI41ARYFACE OUT OF SERVICE t#) NA NOI/i F

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I...I MANWAY Figure 4: Fan Bar Wear Susceptible Region for Steam Generator 11 4

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP TUBES SG 12 2004 Wear 87 Calvert Cliffs Unit 1 B Fan Ear Wear BJfw Zone 389 C Fan Bar Wear CA 1605 Fan Bar Wear - Critical Area and Buffer Zone SCALE: 0.067388 X S.G 12 TOTAL TUBES: 8471 Tue Jan 29 12:09.19 2008 HOT SELECTED TUBES: 1994 PRIMARY FACE OUT OF SERVICE (#): NA NOZZLE

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MANWAY Figure 5: Fan Bar Wear Susceptible Region for Steam Generator 12 5

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP TUBES-HIDDEN Calvert Cliffs Unit 1 C 16M -125 1R18 Fan Bar Wear TestC, ... CA.BZ 238.-0 SO I I TOTAL TUBES. 8471 HOT SELECTED TUBES. 4261 PRIMARY FACE OUT OF SERVICE (t) I SCALE 0,087388 X Tue Mai 04 12 1 06 2008 NOZZLE

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-As MANWVAY Figure 6: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 11 6

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT GROUP IUBES-HI-L)- N 0 Fo~Br 144-0 Calvert Cliffs Unit 1 BtWcon C Ciuc.IArwou6 ,-.142 1R1 8 Fan Bar Wear Tested*OutsideCA8Z 2242:*

S.G 12 TOTAL TUBES. 8471 HOT SELECTED TUBES. 423ti PRIMARY FACE OUT OF SERVICE (3) 0 SCALE O W1388 X 1u.J M., U4 12 010 _1J 0M NOZZLE

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iN t MANWAY Figure 7: 2008 Inspection Map and Fan Bar Wear Indications for Steam Generator 12

RAI 3

Pleasedescribe the scope and results of any secondaryside inspections.

CCNPP Response:

No secondary side inspections were performed during the 2008 SG inspection. This was based upon the following: bobbin-probe eddy current was performed on 100% of the periphery and the no tube lane border to look for loose parts (see inspection map in Figures 6 and 7) and none were detected. One tube (SG1 1 R8C130) contained a small indication of wear [7% through-wall (TW)] at the 5th lattice support on the hot side along with an indication that was most likely caused by a lattice bar burr. The surrounding tubes were examined with rotating probes and no foreign object or wear indications were identified.

Because the wear conditions in SG1 1 R8C 130 could not be visually investigated on the secondary side due to difficulty in reaching the location, the decision was made to conservatively treat the indication as a foreign object and to preventively stabilize and plug the tube.

A secondary side visual inspection was a planned contingency with equipment and personnel available.

An inspection would have been performed if conditions required it. However, as stated above, the wear on tube SG 11 R8C 130 could not be investigated because of the difficulty in reaching that location, so a secondary side inspection was not conducted for that indication.

It should also be noted that the 2004 Unit 1 SG inspection consisted of a 100% bobbin inspection and an extensive secondary side visual inspection. During this 2004 inspection no foreign objects were detected 7

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT in the Unit I SGs. Therefore it is believed that foreign material intrusion is not a significant problem for Calvert Cliffs Unit I SGs.

RAT 4:

Please discuss the natureof the "ambiguousbobbin indications."

CCNPP Response:

The term "ambiguous bobbin indication" was used to refer to any indication that was not caused by FBW and required follow-up testing. There were six "ambiguous bobbin indications" on SG 11 and three on SG 12, as shown in Table I below. After inspection with a rotating probe coil, all of these indications were confidently classified as described below.

  • SGlI R8C130 showed an indication of a lattice grid burr and was conservatively plugged as described above.

" The indications in tubes SGII R17C55, SG11 R115C125, and SGI 1 R137C83 were determined not to represent tube damage or degradation after inspection with a rotating probe coil.

  • The indications in tubes SG1 1 R78C94, SG12 R122C86, and SG12 R134C88 were determined to be wear caused by lattice support wear. Based on the low observed growth rate from the initial operation of the SGs to the 2008 inspection, it was concluded that these indications will not threaten tube integrity before the next scheduled inspection.
  • The indications in tubes SGI 1 R126C 114 and SG12 R106C134 were determined to be caused by foreign objects. In both cases, no foreign objects remained adjacent to the tube. More information about the evaluation of these indications is provided in the response to RAI 8.

Table 1: Description of"Ambiguous" Bobbin Indications Foreign Steam Offset Maximum Cause o F Object Plugged Generator Row Column Elevation (in) Depth Damae POtent and (in) (%TW) Damage Potentially Stabilized Present 11 8 130 05H -1.51 7 Foreign WearObject Yes* Yes 11 17 55 TSC -0.13 N/A No Damage No No 11 78 94 04H 0.51 11 Lattice Support No No Wear 11 115 125 F07 12.11 N/A No Damage No No 11 126 114 TSH 0.95 26 Foreign Object No No Wear 11 137 83 F06 12.09 N/A No Damage No No 12 106 134 TSH 7.12 30 Foreign Object No No Wear 12 122 86 07C 1.07 9 Lattice Support No No Wear 12 134 88 02H -1.53 14 Lattice Support No No I I_ Wear Lattice support burr or small foreign object. Conservatively treated as foreign object.

8

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT

RAI 5

Presumably,a number of new bobbin indications were identified near the fan bars. Of tlwse new bobbin indications,it does not appearthat all were inspectedwith rotatingprobes and that only those indications greater than 15% through-wall were inspected with a rotating probe. If the Nuclear Regulatory Commission staff's understanding is correct, discuss how the causal mechanismsfor these new bobbin indications were determined. Please discuss how wear attributedto tube-to-tube contact and loose parts was ruled out as the causal mechanism.

CCNPP Response:

A cutoff of 15% TW for inspecting with rotating probes was chosen to provide a reasonably large inspection population of large wear in order to confirm that the length of the new and pre-existing wear did not exceed the bounding value of length used in the Condition Monitoring / Operational Assessment report. During the 2004 inspection, all indications of FBW were inspected with a rotating probe coil.

Because there was very little growth of existing indications, it was determined that only the tubes with the largest wear needed to be inspected in 2008 in order to confirm that the wear had the same characteristics.

The plants that operate B&W replacement SGs share their experiences at an annual meeting and through interim phone calls. None of these plants have experienced foreign object wear in the fan bar region, and it is unlikely that a part small enough to work its way that high in the SG could cause significant damage.

Additionally, the fan bar supports have only two offset contact points with the tube, whereas the lattice supports have four contact points, which further decreases the likelihood of a loose part causing damage at a fan bar support rather than becoming stuck at a lattice support. Based on this information, the absence of loose part indications in the eddy current data was taken as reasonable assurance that the wear identified was not caused by loose parts. In addition, tube-to-tube contact was ruled out because FBW occurs only at the fan bar supports, while tube-to-tube contact occurs between supports. The fan bars are identifiable with eddy current by their unique signal, and no wear indications were identified away from the fan bar supports.

RAI 6

Pleasediscuss whether any tubes were identifiedthat were in close proximity.

CCNPP Response:

There were no tubes identified via eddy current inspection that were in close proximity to one another.

RAI 7

Pleaseprovide a list of all service induced indicationsincluding their location, orientation (if linear)and measuredsizes.

CCNPP Response:

There have been no linear indications detected at Calvert Cliffs. All of the indications of degradation identified during the 2008 SG inspection were volumetric in nature. The details of the length and size of the indications are provided in Enclosure (1) (SG 11) and Enclosure (2) (SG 12).

RAI 8

Please discuss whether a secondary side visual inspection was performed near the tubes attributedto foreign object wear (SG11 R126C1J4 and SG12 R106C134) to confirm the absence of a loose part. In 9

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAM GENERATOR REPORT addition, please discuss whether potential loose part indications (from the eddy current data) were visually inspected to identify and remove any loose parts. If any possible loose part indications were left in service without visual inspection, please discuss how it was confirmed that tube integrity would be maintained CCNPP Response:

No secondary side inspection was performed near the two tubes with indications attributed for foreign object wear (SG1 I R126C1 14 and SG12 R106C134). These indications were dispositioned based on eddy current results. For SGI I R126C 114 and SGI2 R106C134, 3-coil rotating probes were used in these tubes and in the bounding surrounding tubes (at least 1 tube deep) and no foreign object was found.

Both of these indications were sized using the most conservative eddy current sizing technique for the condition involved (rotating probe technique 27903.1).

No indications of potential loose parts were identified during this inspection other than the tube (SGl 1 R8C130) that was plugged and removed from service as discussed earlier. Since no objects remain adjacent to any of the remaining in service tubes (see Table I above) that have experienced foreign object wear there is no potential for continued, ongoing damage from this cause. The inspection also demonstrated that the wear caused to date is not a threat to the structural integrity of the tubes going forward. However, the potential for undetected foreign object wear and the development of new foreign object wear in each SG during ensuing operating intervals must be considered. It is difficult to predict if and when foreign object wear - a random and inherently unpredictable phenomenon - will occur.

However, by examining the aggregate operating history of Calvert Cliffs Unit 1 SGs with respect to foreign object wear, a judgment of the risk was developed. During the 2004 Unit I inspection, extensive secondary side examinations were performed along with an eddy current examination of all tubes in both SGs. These inspections revealed no foreign objects which could damage SG tubes and revealed no foreign object related tube damage. After two additional cycles of operation, the 2008 Unit 1 inspections, which included the entire bundle periphery two-to-four tubes deep, revealed no foreign object wear which challenged integrity performance criteria, and identified only one tube with an adjacent potential foreign object indication (the tube which was plugged during the 2008 inspection).

The two wear indications attributed to foreign objects which remain in service were caused by migratory foreign objects no longer present adjacent to the affected tubes. These objects were not located during this examination and have either moved out of the SGs through the blowdown system and are no longer capable of causing tube damage, or have moved to a new location within the tube bundle. Migratory objects are known to move in the direction of the flow, toward the interior of the tube bundle and toward areas of lower flow. Both affected tubes are located on the bundle periphery which is the area of maximum cross flow and therefore the area which poses the highest potential for developing deep foreign object wear. Yet in this location the objects did not cause structurally significant tube damage. If the objects remain in the bundle they have likely moved inboard to a region of the bundle with lower cross flow and lower potential to cause significant tube damage. Therefore, if they remain within the tube bundle, the objects are judged to be unlikely to pose a threat to tube integrity.

Based on these observations, there is reasonable assurance that foreign object wear will not result in damage that exceeds the structural performance criteria prior to the next SG inspection. Because no wear exceeding the structural criteria is expected, it is concluded that the operational leakage and accident leakage performance criteria will not be exceeded by foreign object wear.

10

ENCLOSURE (1)

Steam Generator 11 Indication Report Calvert Cliffs Nuclear Power Plant, Inc.

December 3, 2008

ARVA NP Inc 03/07/08 14:28:27 Unit I Co*ponent: $1G 11 Paqe 2 of 4 CUtoeer Nam e; Calvert C1cfa3 FE Near Indicatiors (Sort by Row/Cal)

QCUE3Y: FB Near Indications by rev R.OWCOL VOLTS DEC CHI IND %TW LOCATION EXT EXT OTIL I OTIL 2 CAL I LEG PROBE 89 0.25 110 P3 TWD 14 FOB 41.48 TEC TEE 42 HOT 6200!

57 +1.71 6200!

s8 82 0.13 132 P3 TWO 6 P07 TEC TEE LAR 11 HOT 60 68 0.14 142 P3 TWO 7 r07 +0.90 TEC TER 16 HOT 62001 68 54 0.17 131 P3 TWO 9 F07 -1.14 TEC TEE LAR 11 HOT 62001.

68 84 0.16 133 P3 TWO 8 T06 -0.80 TIC TER 5 SOT 6200L 79 0.13 133 P3 TTD 7 T07 -0.90 TEC TER 12 SOT 6200!

69 0.16 141 P3 TWO 8 T07 +1.47 TEC TEE LA. 11 DOT 6200L 72 86 SOT 107 0.09 74 P3 TWO 6 707 -1.29 TEC T*E 17 6200!

73 86 0.21 108 P3 TWO 11 F07 +1.53 TEC TEE 11 ROT 620UL 76 15 HOT 98 P3 Two 5 roe +0.72 TEC TER 6200L 77 69 0.10 84 0.12 11 P3 TWD 7 F08 +0.83 TEC TEE 6 SOT 620UL 78 86 13C P3 TWO 8 r07 +1.78 TIC TER LAR 11 HOT 62010L 80 0.16 108 P3 TWO 5 P08 +0.70 TIC TEE HOT 62005 0.11 roe HOT 62001 69 0.10 129 P3 TWO 5 +0.65 TEC TER 16 83 83 79 0.11 134 P3 TWD 5 Fos r07 +1.69 T3C TER LA. 1II HOT 6200!

133 P3 TWO 6 Fos +0.75 TEC TER LAR 11 HOT 620!L 0.13 HOT 6200!

128 P3 TWD 7 F07 +1.46 TEC TER 12 83 87 0.14 62001 59 P3 TO'D 5 r07 +1.72 TEC TEE LAR 11 NOT 84 86 0.11 11 NOT 6200!

85 81 0.12 140 P3 TWO 5 F06 -0.74 TEC TER F09 +0.76 TEC TEE 12 HOT 6200L 86 80 0.11 136 P3 TWO 6 75 r07 +1.82 TEC TER 14 HOT 62001 87 0.18 120 P3 TWO 8 HOT r07 +1.81 TEC TEE 11 6200L 87 79 0.22 118 P3 TWD 12 roe +0.63 TEC TER LAP. 11 ROT 62001.

0.12 136 P3 TWD 5 6201L P3 TWOD 6 FOB +0.76 TIC TER LAR 6 ROT 88 84 0.10 85 F07 +1.79 TIC TEE LAR 6 HOT 6200L 0.11 72 P3 TWD 6 F07 +1.75 TEC TER LA.R 11 HOT 6200!

88 86 0.20 130 P3 TWO 10 6200L P07 +1.69 TEC TER 15 HOT 89 69 0.13 119 P3 TWD 7 POT 6200L P07 +1.68 TEC TER LAP, 11 89 81 0.12 131 P3 TOD 5 F06 +0.50 TEC TER LAP 6 HOT 6200U, 89 83 0.13 75 P3 TWO 7 S 62001.

PlO -0.90 TEC TER ROT 90 84 0.16 117 P3 TWO 9 F07 POT 6200!

-1.92 TEC TEE 11 91 81 0.13 146 P3 TWO 6 F07 13 EOT 62001 92 74 0.14 14! P3 TWO 7 F07 +0.77 TEC TEE

+0.76 TEC TEE 13 HOT 620CL 92 76 0.10 11 P3 TWD 5 HOT 62001 P08 +1.71 TEC TEE 11 92 78 0.13 14C P3 TWD 6 r07 11 HOT 62001 0.14 143 P3 TWO 7 P06 +0.77 TEC TER 11

-1.87 TEC TES HOT 6200L 0.08 138 P3 TWO 2 F08 43 HOT 6200!

0.08 76 P3 TWO 4 -1.92 TEC TEE 92 88 F08 15 HOT 62001 93 69 0.12 13C P3 TWO 6 +0.75 TEC TEE ro8 -0.54 TIC TEE LAR 6 HOT 6200L 93 93 0.12 88 P3 TWO 6 r07 14 HOT 620UL 0.13 103 P3 TWO 6 F07 +0.77 TEC TEE 94 74 14 SOT 620C7L 94 76 0.11 12f P3 TWO 5 o07 +0.65 TIC TEE TIC TER 12 HOT 6200!

94 82 0.12 90 P3 TWO 6 F08 +0.70 62005

+0.82 TEC TER LAP. 5 SOT 94 84 0.11 132 P3 TWO 6 14 SOT 62CUL 0.22 124 P3 TWD 10 r07 +1.04 TEC TEE 95 *75 TEC TER 5 HOT 6200!

95 83 0.19 94 P3 TWO 10 F07 -0.55 TEC TEE 12 HOT 620!L 95 85 0.09 99 P3 TWO 5 r07 +0.78

+0.77 TEC TER 13 HOT 6200!

96 74 0.14 121 P3 TWO 7 F07 POT 6200C P06 -0.92 TEC TEE 11 96 80 0.09 156 P3 TWO 4 11 POT 620UL 96 82 0.12 138 P3 TWO 5 r07 +0.85 TEC TEE TIC TEE 15 HOT 6200C 97 65 0.14 60 P3 TWO 7 F07 +0.74 TEC TEE 13 HOT 62C0UL 97 75 0.10 123 P3 TWO 5 P07 +1.77

+1.83 TEC TEE 12 HOT 62 CL 97 79 0.12 106 P3 TWO 6 F07 HOT 62CU!

112 P3 TWO 10 F07 +0.79 TEC TER LAP. 14 98 74 0.22 12 HOT 62CU!

0.13 i18 P3 Two 7 F07 +0.76 TEC TER 98 80 TEC TER 12 HOT 620U!

0.15 121 P3 TWO 8 r07 +1.68 98 82 TEC TEA 12 ROT 6200!

0.13 103 P3 TWD 7 F07 +0.83 TIC TEE 42 HOT 6200!

98 90 0.13 112 P3 TWO 7 F07 +1.76 TEC TEE 16 SOT 62001 99 65 0.12 125 P3 TWO 6 F07 +1.14

+1.76 TEC TEE 11 HOT 6200!.

99 79 0.18 114 P3 TWO 9 F07 62C!.

TEC TER 5 HOT 99 83 0.12 80 P3 TWD 6 F07 +0.55 SOT 62CCL

+0.71 TEC TEE 43 99 89 0.19 120 P3 TWD 10 HOT 62 CL P06 -1.86 TEC TER L.AE. 11 100 78 0.20 115 P3 TWO 10 HOT 6200L P06 +0.66 TEC TEE LAP. 11 100 82 0.15 125 P3 TWD F07 6 SOT 6200!

129 P3 TWD 6 +1.72 TEC TEE 100 84 0.10 P07 43 POT 6200!

0.16 130 P3 TWO 8 +1.73 TEC TEE 100 90 F07 13 HOT 6200!

134 P3 TWO 8 +1.79 TIC TEI 101 75 0.16 r07 12 ROT 6200!.

129 P3 TWO 8 +1.77 TEC TER 101 79 0.16 r0 6 12 HOT 6200U 0.18 102 P3 TWO 9 -0.74 TEC TER F07 TEC TEE 6 HOT 6200L 101 83 0.26 111 23 TWO 13 -0.59 P07 TEC TER 11 HOT 62001 101 87 0.11 135 P3 TWO S +0.68 HOT 6200L F06 -1.83 TEC TIE 11 0.11 140 P3 TWD 5 12 HOT 6200L P3 TWO 5 -1.80 TEC TEE 102 78 0.09 126 F08 ROT 62001 23 TWO 6 +0.76 TEC TER 12 102 80 0.11 137 rO0 12 HOT 620'L 121 t3 TWO 12 +1.70 TIC TEE 102 86 0.24 r07 TEC TER 11 HOT 6200!

103 79 0.28 133 P3 TWO 14 r07 +1.72 TEC TER LAP 11 ROT 62001.

0.16 01 ?3 TwO 6 o07 -0.75 62CUL TIC TEE 11 ROT 103 81 0.06 137 P3 TWO 1 r07 -1.87 SOT 62CCL 117 P3 TWO 8 -0.57 TEC TEE LAP. 5 103 83 0.16 r07 11 HOT 62CU!

113 P3 TWO 9 +0.83 TEC TER 104 80 0.18 F07 TEC TER 12 HOT 62CUL 104 82 0.29 135 P3 TWO 15 +0.90

AREVA NP Inc 03/07/08 14:28:27 Customer Name: Calvert Cliffs Unit 1 Component: S/G 11 Page 3 of 4 FB Wear Indications (Sort by Row/Col)

QUERY: FB Wear Indications by rov.qry ROW COL VOLTS DEG CH rND %TW LOCATION EXT EXT UTIL I OUTL 2 CAL # LEG PROBE 0.12 139 P3 TWO 5 P06 -1.69 TEC TEN 11 HOT 62CUL 104 88 0.11 135 P3 TwO 5 F06 -0.74 TEC TEE 43 POT 62C0L 105 75 0.15 127 P3 TWO 7 F07 +1.74 TEC TER 13 HOT 62CDL 105 79 0.33 131 P3 TwO 16 F07 +1.76 TEC TER 12 HOT 62CUL 0.12 142 P3 TWO 6 F06 -0.76 TEC TER 12 NOT 620CL 105 85 0.12 102 P3 TOD 5 F07 +0.75 TEC TER 11 NOT 6200L 105 89 0.28 124 P3 TWO 15 P07 +0.83 TEC TEE 42 NOT 6200L 106 78 0.17 127 P3 TWO 9 F07 +0.78 TEC TER 12 HOT 620UL 0.15 130 P3 TWO 8 F06 -1.74 TEC TER 12 NOT 620UL 106 80 0.11 114 P3 TWo 6 F07 +0.74 TEC TER 12 NOT 6200L 106 82 0.16 135 P3 TWD 8 F07 +0.84 TEC TEN 12 NOT 620UL 106 86 0.23 127 P3 TWO 12 107 +1.67 TEC TER 12 HOT 62001 106 88 0.17 129 P3 TWD 10 P08 -0.78 TEC TER 42 HOT 6200L 107 79 0.11 123 13 TWO 5 r07 -1.89 TEC TER 11 SOT 6200L 107 83 0.34 120 P3 TWO 16 r07 -0.55 TEC TEE 5 SOT 620UL 107 85 0.14 108 P3 TWO 7 P07 +0.72 TEd TEE 12 HOT 6209L 107 87 0.17 118 P3 TWO 9 E06 -1.88 TEC TER 12 ROT 620UL 107 89 0.14 147 P3 TWO, 7 T07 +0.78 TEC TER 43 ROT 620UL 0.16 131 P3 TWO 8 708 -1.23 TEC TEE 11 HOT 620UL 108 78 0.13 131 P3 Two 7 707 +1.75 TEC TEE 6 NOT 620UL 108 84 TWO 8 1706 -0.85 TEC TEE 6 HOT 620UL 0.14 114 P3 108 TWO 6 P06 -0.78 TEC TER 43 HOT 620UL 108 88 0.12 P3 F06 109 79 0.14 121 P3 TWD 7 -0.80 TEC TEN 12 HOT 6200L r08 620UL 109 83 0.13 129 P3 TWD 7 -0.55 TEC TER 6 HOT 0.17 119 P3 TWD 9 P07 +0.46 TEC TEE LAR 6 HOT 620UL F06 0.12 108 P3 TWD 6 +0.48 TLC TEE LAR 6 HOT 6200L 706 109 87 0.16 105 P3 TWO 8 +1.61 TEC TEE 11 HOT 6200L P07 110 76 0.14 125 P3 TWO 6 F07 +0.78 TEC TEN 14 HOT 620DL 110 78 0.15 116 P3 TWO 8 +0.80 TEC TEE 12 HOT 620UL F06 0.22 129 P3 TWO 11 -1.73 TEC TEN 12 HOT 6200L F09 6207L 111 79 0.23 103 P5 TWO 9 +1.16 TEC TEN LAR 11 HOT F07 6200L 0.12 133 P3 TWO 6 +0.61 TEC TER 12 HOT 111 87 F07 111 89 0.10 117 P3 TWO 5 +0.74 TEC TEN 43 HOT 62001 F07 62001 112 76 0.13 136 P3 TWo 7 +0.77 TEC TEN 13 HOT 707 +0.73 TEC TEN 11 ROT 620UL 112 78 0.17 98 P3 TWO 8 11 0.18 128 P3 TWO 9 106 +1.67 TEC TEN NOT 620CL 112 80 F06 0.27 131 P3 TWo 13 -0.76 TEC TER 12 HOT 6200L 113 79 F07 0.14 131 P3 TWO 7 r70 -0.55 TEC TEN LAR 5 POT 6207L 113 83 10?

122 P3 TWO 2 +0.82 TEC TEN 11 HOT 6203L 113 85 0.08 r07 0.12 141 P3 TWO 7 +0.70 TEC TER 42 HOT 6203L 113 89 F06 620UL 114 74 0.12 85 P3 TWO 5 -1.90 TEC TER 14 HOT 707 14 HOT 6200L 114 76 0.13 117 P3 TWD 6 707 +0.81 TEC TEN 141 P3 TWo 11 +0.82 TEC TEN 12 HOT 6200L 114 78 0.22 r07 134 P3 TWO 9 +0.76 TEC TER 12 NOT 6209L 114 80 0.18 TWO 10 +0.76 TEC TEN 12 ROT 6207L 114 82 0.19 118 P3 F07 P3 TWO 5 +1.72 TEC TER 14 HOT 6200L 115 75 0.12 134 r06 123 P3 TWO 8 -0.77 TEC TEN LAR 11 HOT 6203L 115 79 0.15 707 6203L 137 P3 TWO 6 +0.72 TEC TEN 12 HOT 115 85 0.11 707 TWO 9 +0.72 TEC TEE 12 NOT 6203L 115 87 0.17 131 P3 TO?

TWO 6 -1.90 TEC TEE 12 SOT 6207L 0.12 138 P3 r07 0.11 135 P3 TWD 6 40.85 TEd TEN 42 HOT 62071L 115 91 F06 14 NOT 6207L 116 72 0.18 127 P3 TWD 8 r07 +1.69 TEC TEE TEC TEN 11 HOT 620JL 116 78 0.10 134 P3 TWO 4 F07 +0.75

+1.69 TEC TEN 11 HOT 6203L 116 86 0.23 134 P3 TWO 12 F06 TWO 8 -0.79 TEC TEN LAR 11 HOT 6203L 0.15 125 P3 r07 TWO 12 +1.69 TEC TER 12 HOT 620n1 117 79 0.25 124 P3 7o06 TWO 23 -0.80 TEC TEN LAR 12 SOT 6207L 0.57 125 P3 '07 117 P3 TWO 6 -0.55 TEC TEN LAR 6 HOT 620DL 117 83 0.12 r07 TWO 5 +0.75 TEC TEN 11 HOT 6203L 117 87 0.11 141 P3 r0E 99 P3 TWO 6 +0.76 TEC TEN 18 SOT 6203L 117 99 0.12 F07 SOT 6207L 0.11 128 P3 TWO 6 +0.80 TEC TEN 12 118 78 F06 12 ROT 6207L 0.14 100 P3 TWo 7 -1.79 TEC TER 0.43 123 P3 TWO 20 7'06 +1.48 TEC TER LAR 11 HOT 6201L 120 82 704 6207L 137 P3 TWO 10 +0.84 TEC TEN LANR 11 HOT 0.20 6207L 0.11 III P3 TWO 6 +1.80 TEC TER 43 NOT 120 88 7"06 NOT 6207L 0.12 92 P3 TWO 6 -0.80 TEC TEN 43 r07 12 HOT 620"CL 121 79 0.10 130 P3 TWO 5 F07 +1.60 TEC TER TWD 7 +1.69 TLC TEE 11 HOT 62073L 123 81 0.14 145 P3 FOB 6207L 130 P3 TWO 5 +0.65 TEC TEN 12 NOT 125 81 0.10 F06 620rL 129 P3 TWoD10 -1.47 TEC TEN LAR 11 NOT 127 81 0.19 F09 620UL 132 P3 TWO 7 +1.72 TEC TEN 42 HOT 127 91 0.12 620UL 136 P3 TWO 9 F06 40.89 TEC TER 42 ROT 0.15 Total Tubes  : 128 Total Records: 152

AREVA NP Inc 03/07/08 14:28:27 Customer Name: Calvert Cliffs Unit I Component; S/C 11 Page 2 of 4 PH Wear Indications (SoXt by RowICol)

QOUERY: 7B Wear Indications by row ROW COL VOLTS DEG CHN INO %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE

.. . ...

57 89 0.25 110 P3 TWO 14 T08 +1.48 TEC TER 42 HOT 6200L 58 82 0.13 132 P3 Two 6 P07 +1.71 TEC TEE LAR 11 HOT 6203L 60 68 0.14 142 P3 TWD 7 70? +0.90 TEC TER 16 NOT 6207L 68 54 0.17 131 P3 TWO 9 F07 -1.14 TEC TER LAR 11 HOT 6200L 68 84 0.16 133 P3 TWO 8 F06 -0.80 TEC TER 5 SOT 6200L 69 79 0.13 133 P3 TWO 7 707 -0.90 TEC TER 12 NOT 620UL TEC TER LAR 11 SOT 6200L 72 86 0.16 141 P3 TWO 8 707 +1.47 73 107 0.09 74 P3 TWO 6 707 -1.29 TEC TEE 17 HOT 6200L 76 86 0.21 108 23 TWO 11 707 +1.53 TEC TER 11 HOT 6200L 77 69 0.10 98 P3 TWD 5 r08 +0.72 TEECTER 15 SOT 6200L 78 84 0.12 117 P3 TWO 7 F08 +0.83 TEC TEN 6 HOT 62001 80 86 0.16 130 P3 TWO 8 707 +1.78 TEC TER LAR 11 HOT 6200L 0.11 108 P3 TWO 5 r08 +0.70 TEC TER LAR 11 HOT 6200L 83 69 0.10 129 P3 TWO 5 r08 +0.65 TEC TEN 16 HOT 620UL 83 79 0.11 134 P3 TWO 5 07 +1.69 TEC TEN LAR 11 HOT 6200L 0.13 133 P3 TWD 6 F08 +0.75 TEC TEE LAN 11 HOT 620CL 83 87 0.14 128 P3 TWO 7 F07 +1.46 TEC TER 12 NOT 6200L 84 86 0.11 59 P3 TWD 5 F07 +1,72 TEC TER LAR 11 NOT 6200L 85 81 0.12 14C P3 Two 5 F06 -0.74 TEC TEN 11 HOT 6200L 13( P3 TWO 6 F09 +0.76 TEC TEE 12 ROT 6200C 86 80 0.11 F07 +1.82 TEC TEE 14 ROT 6200C 87 75 0.18 12C P3 TWO 8 HOT 6200L 87 79 0.22 1le P3 TWO 12 707 +1.81 TEC TEE 11 0.12 13( P3 TWO 5 r08 +0.63 TEC TEE LAR 11 NOT 6200L 85 23 Two 6 F08 +0.76 TEC TEN LAN 6 HOT 62C0L 88 84 0.10 0.11 72 P3 TWO 6 F07 +1.79 TEC TEE LAN 6 NOT 62COL 86 0.20 13C P3 TWO 10 r07 +1.75 TEC TEN LMN 11 HOT 62C0T, 88 11S P3 TWD 7 F07 +1.69 TEC TER 15 HOT 62COL 89 69 0.13 0.12 131 P3 TWO 5 707 +1.68 TEC TER LANR 11 HOT 62(0U 89 81 83 0.13 75 P3 TWO 7 706 +0.50 TEC TER LAR 6 ROT 62CU0 89 117 P3 TWO 9 F10 -0.90 TEC TEN 5 POT 62C01 90 84 0.18 81 0.13 146 P3 TWO 6 707 -1.92 TEC TEN 11 ROT 62C0L 91 62CCL 74 0.14 145 P3 TWO 7 707 +0.77 TEC TER 33 POT 92 NOT 62C0 92 76 0.10 117 P3 TWO 5 r07 +0.76 TEC TEH 13 140 P3 Two 6 r08 +1.71 TEC TEN 11 HOT 62CuL 92 78 0.13 143 P3 TWO 7 707 +0.77 TEC TER 11 ROT 62CM0 0.14 NOT P3 TOD 2 F06 -1.87 TEC TEN 11 62M01 0.08 13f:

r08 -1.92 TEC TEN 43 HOT 62C0L 92 88 0.08 76 P3 TWO 4 6201L r08 +0.75 TEC TEN 15 HOT 93 69 0.12 130 P3 TWD 6 r08 -0.54 TEC TER LAR 6 HOT 6200L 93 83 0.12 88 P3 TWO 6 V07 +0.77 TEC TEE 14 HOT 62C0L 94 74 0.13 103 P3 TWO 6 F07 +0.85 TEC TEN 14 HOT 6200L 94 76 0.11 126 P3 TWO 5 62COL 90 P3 TWO 6 707 +0.70 TEC TEN 12 HOT 94 82 0.12 ROT 6200U 132 P3 Two 6 r08 +0.82 TEC TEN LAR 5 94 84 0.11 14 HOT 62001 95 75 0.22 124 P3 TWO 10 F07 +1.84 TEC TEE 707 -0.55 TEC TEN 5 HOT 6200L 95 83 0.19 94 P3 Two 10 99 P3 TWD 5 707 +0.78 TEC TER 12 LOT 620U0L 95 85 0.09 13 ROT 620UL 96 74 0.14 121 P3 TWO 7 707 +0.77 TEC TER 706 -0.92 TEC TER 11 HOT 6200L 96 8o 0.09 156 P3 TWD 4 r07 +0.85 TEC TEN 11 HOT 6200L 96 82 0.12 138 P3 TWO 5 6200L 60 P3 Two 7 F07 +0.74 TEC TEE 15 HOT 97 65 0.14 123 P3 TWO 5 r07 +1.77 TEC TEN 13 NOT 6200L 97 75 0.10 NOT 6200L 79 0.12 106 P3 TWO 6 707 +1.83 TEC TEE 12 97 14 HOT 62005 74 0.22 112 P3 TWO 10 r07 +0.79 TEC TER LAN 98 12 HOT 6200L 98 80 0.13 I18 P3 TWO 7 707 +0.76 TEC TER F08 +1.88 TEC TER 12 HOT 6200L 98 82 0.15 121 P3 TWO 0 707 +0.83 TEC TEN 12 ROT 6200L 0.13 103 P3 TWD7 F07 +1.76 TEC TER 42 HOT 6200L 98 90 0.13 112 P3 TWO 7 ROT 6200L 125 P3 TWO 6 F07 +1.14 TEC TER 16 99 65 0.12 11 NOT 6200L 99 79 0.18 114 P3 TWO 9 F07 +1.76 TEC TEH 706 +0.55 TEC TEE 5 NOT 62001 99 83 0.12 88 P3 TWO 6 F07 +0.71 TEC TEE 43 HOT 6200L 99 89 0.19 120 P3 TWO 10 6200L F06 -1.86 TEC TEN LAR 11 HOT 100 78 0.20 115 P3 Two 10 F06 +0.66 TEC TEN LAR 11 HOT 6200L 100 82 0.15 125 P3 TWO 8 620UL F07 +1.72 TEC TEN 6 ROE 100 84 0.10 129 P3 TWO 6 6200L 707 +1.73 TEC.TEH 43 HOT 100 90 0.16 130 P3 TWD 8 HOT 620M 134 707 +1.79 TEC TER 13 101 75 0.16 P3 Two 8 TEC TEN 6200=1 707 +1.77 12 HOT 101 79 0.16 129 P3 TWO 8 6200L r06 -0.74 TEC TER 12 HOT 0.18 102 P3 TWO 9 62001 707 -0.59 TEC TEN 6 HOT 101 83 0.26 lI1I 3 TWO 13 11 HOT 62001 101 87 0.11 135 P3 TWO 5 707 +0.68 TEC TEN P06 -1.83 TEC TEN 11 HOT 62001 0.11 140 P3 TWO 5 6200n F06 -1.80 TEC TEE 12 HOT 102 78 0.09 124 P3 TWO 5 62001 708 +0.76 TEC TEN 12 HOT 102 80 0.11 137 P3 TWO 6 12 F07 +1.70 TEC TER HOT 6200L 102 86 0.24 121 P3 TWD12 r07 +1.72 TEC TER 11 NOT 6200L 103 79 0.28 133 P3 TWO 14 6200L 706 -0.75 TEC TER LAN 1 EDT 0.16 81 P3 TWO 8 62001 137 13 TWO 1 T0? -1.87 TEC TEN 11 HOT 103 81 0.06 HOT 6200L 103 83 0.16 117 P3 TWO 8 F07 -0.57 TEC TER 11 F07 +0.83 TEC TEN HOT 62001 104 80 0.10 113 P3 TWO 9 11 HOT 6200L 104 82 0.29 135 P3 TOD 15 707 +0.90 TEC TER

AREVA VP Inc 03/07/08 14:27:48 Customer Name: Calvert Cliffs Unit 1 Cozponent: S/G 11 Page 2 of 2 Lattice Support Wear indications CUERY: TSP Wear Indications ROWCOL VOLTS DE. CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROSE 78 94 0.19 126 P3 TWD 11 04H +0.51 TIC TER LAR 42 HOT 6203L Total Tubes  : 1 Total Records: I

PZVA NP Inc 03/07/08 14:30:31 Customer Fame: Calvert Cliffs Onit 1 Component: S/G 11 Page : of 2 DSX Indications QUERY: DSI Indications ROW COL VOLTS DEG CHN M*D %TW LOCATION EXT EXT (TIL 1 OTIL 2 CAL # LEG PPRO13 8 130 0.13 68 PI OSI 05H -1.51 TEC TER LAP. 31 ROT IOUL Total Tubes  : 1 Total Records: 1

AREVA NP Inc 03/07108 14:30:50 Customer Nlame: Calvert Cliffs Unit 1 Component: SIG 11 Page 2 of 2 DTI IndLcations QUERY: DTI Indications ROW COL VOLTS DEG CNN IND %TWLOCATION EXT LXT UTIL 1 UTIL 2 CAL # LEG PROBZ 17 55 3.84 110 P4 DTI TSC -0.13 TEC TEH LAR 50 NOT 620DL Total Tubes : 1 Total Records: I

AREVA NP Inc 03/07/08 14:30:15 Customer Na1se: Calve:t Cliffs Unit 1 Component: S/C 11 Page 2 of 2 NQI Indications OUERY: NQ! Indications ROw COL VOLTS DEG CIN ISO MTWLOCATION EXT EXT OTIL 1 UTIL 2 CAL # LE5 PRO3E

.. .......

  • w........ ~

.-.l.. .* n

........... m 115 125 5.75 141 5 NQ1 r07 +212.11 TEC TEH DBP LAR 5 HOT 620UL 126 114 0.12 127 P1 NQ0 TSH 40.95 TFC TEH LAR 2 HOT 6200L Total Tubes : 2 Total Records: 2

ARZVA NP Inc 03/07/08 14:29:56 Component: S/C 11 Page 2 of 2 Customer Name: Calvert Cliffs Unit I PLP Indications OUERY: PLP rndica=ion$

ROW COL VOLTS DEG C014 Z4D ITW LOCATION EXT EXT UTIL 1 OTIL 2 CAL # L!G PROBE 8 130 0.73 265 10 PLP 05H -1.54 05H 05H LA, 41 HOT 610FP Total Tubes : 1 Total Records: 1

AAREVA NP Inc 03/07/08 14:28:07 Customer Name; Calvert Cliffs Unit I Coaponent: Sf0 11 Page 2 of 2 wAR indications QUERY: WAR Indications ROW COL VOLTS DEG CHN X8D %TN LOCATION EXT EXT OTIL 1 UTIL 2 CAL 4 LEG PEZBE 8 130 0.16 111 P4 WAR 05H -1.50 05H 05H 7 41 HOT 6101?

78 94 0.15 78 P4 WAR 04H +0.61 04H 04H 8 54 HOT 105 79 0.29 105 PS WAR F07 +1.84 r07 F07 22 40 HOT 5(0PP 107 83 0.26 107 PS WAR F07 -0.50 F07 F07 20 40 HOT 50OPP 117 79 0.36 102 PS WAR r06 -0.83 F06 F06 25 40 HOT 5(0PP 120 82 0.23 88 P5 WAR F06 +1.55 F06 F06 18 40 HOT 126 114 0.07 72 P4 WAR TSH +0.85 TSH 018 3 41 HOT 610PP Total Tubes  : 7 Total Records: 7

AREVA NP Inc 03/07/08 14:31:04 Cust*mer Name: Calvert Cliffs Unit I Component: S/G 11 Page 2 of 2 DNG Indications Q7ERY: DNG Indications ROW COL VOLTS DEG CNN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL f LEG PIROBE 48 160 23.40 180 PI DUG F04 +1.17 TEC TER 4 ROT 6200L 114 38 2.32 191 P1 DNG F06 +4.42 TEC TER 8 HOT 620UL 114 68 14.41 181 P1 DNG 02C -2.62 TEC TER 15 ROT 620UL Total Tubes : 3 Total Records: 3

ENCLOSURE (2)

Steam Generator 12 Indication Report Calvert Cliffs Nuclear Power Plant, Inc.

December 3, 2008

AREVA HP Inc 3/7/2008 2:18:33 Fm Customer Name: Calvert Cliffs Unit I Component: S/G 12 Page 2 of 4 FB Wear Indications (Sort by Row/Col)

QUERY: FB Wear Indications by row ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT 0TIL 1 CTEL 2 CAL # LEG PROBE m - -

40 16 0.16 99 P3 TWO 15 P06 +0.71 TEC TER 9 HOT 6200U 41 45 0.26 116 P3 TWO 12 r07 -1.22 TEC TER 46 HOT 61 85 0.16 98 P3 TWD 8 F09 -1.03 TEC TEE 16 HOT 6200L 0 P3 TWO 6 Flo +2.65 TEC TER 10 NOT 62001 63 59 0.14 66 94 0.11 132 P3 TWD 11 r07 +1.94 TEC TEE LAR 17 NOT 620UL 109 P3 TWO 10 F`07 +0.88 TEC TER LAR 17 HOT 62001 0.10 92 P3 TWO 7 F07 +1.30 TEC TER 19 HOT 620UL 67 89 0.16 62001 68 92 0.10 87 P3 TWO 6 r08 +0.74 TEC TEE 18 HOT 137 P3 TWO 6 -1.95 TEC TER 19 ROT 62001 76 90 0.12 73 P3 TWO 7 F07 +0.78 TEC TEI 18 ROT 62001 76 92 0.12 P08 TWo 8 +1.77 TEC TEE 19 NOT 6200L 83 87 0.18 129 P3 129 P3 TWO 10 -0.91 TEC TEH LAR 17 HOT 6200L 83 91 0.10 620UL 84 88 0.12 85 P3 TWO 6 r07 -1.93 TEC TER 19 NOT 16 P3 TWO 11 Fro +0.78 TEC TEI 18 ROT 620CL 84 92 0.20

+1.36 TEC TEE 9 HOT 620CL 85 59 0.25 102 P3 T*oD 19 F07 TWO 6 FOB +0.78 TEC TEE 14 NOT 6200L 85 75 0.13 60 P3 F11 +2.22 TIC TEH 19 NOT 620CL 85 89 0.12 110 P3 TWD 6 58 P3 TWO 9 F05 -0.76 TIC TER 18 NOT 620CL 85 91 0.16 620CL 113 P3 TWO 6 F07 -1.95 TEC TER 19 NOT 86 90 0.13 6200L TWD 16 F07 +1.74 TEC TER 13 NOT 87 75 0.19 131 P3 620CL 137 P3 TWO 13 r07 +1.71 TIC TER 13 NOT 87 77 0.14 620C1 0 P3 TWO, 12 Fo6 +0.48 TEC TER LAR 5 NOT 87 83 0.12 620CL 44 P3 TWO 9 F08 +0.76 TEC TEI 18 HOT 88 92 0.16 0.14 49 P3 TWo 8 r07 +1.88 TEC TER 18 ROT 620CL 118 P3 TWO 6 F08 +0.74 TEC TEI 14 HOT 620CL 89 79 0.15 620CL 0 P3 TWO 7 P05 +0.44 TEC TER 6 NOT 89 83 0.14 P08 620CL TWO 8 +1.84 TEC TER 18 NOT 89 91 0.14 94 P3 620CL 54 P3 TWO 9 P07 +0.73 TEC TEN 18 NOT 0.16 620Th 0.19 95 P3 TWD 11 F06 -1.82 TIC TER 18 H0o" 620t'L 90 92 0.12 104 P3 TWO 11 P08 -1.91 TEC TER LAR 17 nOT 620VL TWO 10 F07 +1.76 TEC TEI 13 ROT 91 75 0.11 127 P3 620CL 123 P3 TWO 8 F0.7 -1.82 TEC TEI 14 NOT 92 78 0.19 P0.7 19 sOT 620VL 90 0.12 142 P3 TWD 6 -1.88 TEC TEI 92 620VL 0.32 121 P5 TWO 10 70.7 roe

+1.25 TEC TEE 19 HOT

+0.78 TEC TEI 18 HOT 620EtL 92 92 0.12 33 P3 TWO 7 P0? 620VL TWO 6 +1.84 TSC TEI 18 BOT 92 94 0.11 53 P3 620UL 93 71 0.17 125 P3 TWO 14 F07 F06 -1.79 TEC TEI LAR 11 nOT 620UL r07 +0.46 TEC TEN 6 NOT 93 83 0.18 0 P3 Two 9 r08 620VL TWo 7 +1.77 TEC TER 18 NOT 93 91 0.12 107 P3 707 620CL

+0.82 TEC TEN 18 ROT 93 95 0.14 90 P3 TWO 8 F07 620UL TWO 13 +0.11 TEC TER LAR 15 NOT 93 107 0.16 158 P3 14 NOT 6201CL 94 76 0.13 103 P3 TWo 6 F06 +0.72 TEC TER

-1.76 TIC TEI 14 NOT 62CUL 0.13 128 P3 TWD 6 r06 620CL

-1.87 TEC TEI 14 NOT 94 82 0.12 128 P3 TWO 5 F0? 620UL TWO 6 -1.94 TEC TER 19 HOT 94 90 0.13 95 P3 708 620UL

+0.80 TEC TEH 39 NOT 94 92 0.12 108 P3 TWD 6 F07 620UL

+1.94 TEC TEI 39 HOT 0.15 107 P3 TWO 8 P07 620UL TWD 13 107 +1.78 TEC TER 13 HOT 95 79 0.14 129 P3 620UL 41.78 TEC TIN 13 NOT 95 81 0.18 131 P3 TWO 15 F06 620UL

+0.44 TEC TEN 5 ROT 95 83 0.17 0 P3 TWO 15 F07 19 HOT 620UL 96 88 0.12 111 P3 TWD 6 To? +1.79 TEC TEI F07 TEC TEE 19 ROT 620UL 96 90 0.13 85 P3 TWD 6 F07 -1.92

+1.75 TEC TER 14 HOT 620UL 97 81 0.14 141 P3 TweD6 F07 620UL TWO 9 40.48 TEC TER 6 NOT 97 63 0.19 0 P3 F06 620UL 40.39 TIC TEN 6 HOT 0.12 0 P3 TWD 6 F07 18 ROT 620UL 96 P3 TrD 9 +0.76 TEC TEI 97 91 0.16 F07 LAR 11 NOT 6201L TWO13 r06 -1.94 TEC TER 98 72 0.15 131 P3 14 HOT 620UL 84 P3 TWO 6 -1.80 TEC TEI 98 76 0.14 r07 14 NOT 6201CL 100 P3 TWO 6 40.70 TEC TER 98 82 0.14 Fos LAR 5 HOT 62001L 0 P3 TWO 10 T07 -1.93 TEC TEI 98 84 0.10 19 NOT 620UL 90 0.13 120 P3 TWO 6 -1.95 TEC TER 98 F06 LAR 13 HOT 62031 99 75 0.12 118 P3 TWO 11 707 ,1.76 TEC TEI

+1.76 TEC TEI LAR 13 NOT 62OUL, 99 79 0.15 120 P3 TWO 14 6201L

+0.51 TEC TER LAR 5 HOT 99 83 0.09 0 P3 TWO 10 F07 62031

-0.60 TEC TEH LAR 5 HOT 0.12 0 P3 TWO 12 F07 5 HOT 6207L LAR 0.12 0 P3 TWD 12 708 r06 -0.66 TEC TER 19 HOT 6201L 99 87 0.12 141 P3 TWO 6 +0.71 TEC TEI r06 TEC 19 NOT 62031 99 89 0.17 122 P3 TWO8 F07 -1.39 TER 620:1 0.12 80 P3 TWO 6 Fos r07 +0.78 TEC TEI 19 NOT

+0.87 TEC TER LAR 17 HOT 62031 99 93 0.12 117 P3 TWO 12 F06 62031

-1.89 TEC TEN LAR 17 HOT 99 95 0.15 127 P3 TWO 13 14 NOT 62031 111 P3 TWO 7 -1.84 TEC TEI 100 78 0.16 107 19 NOT 6203L 122 P3 TWO 8 -1.90 TEC TEI 100 90 0.18 r07 14 HOT 62001 101 75 0.14 121 83 TWO 6 +1.80 TEC TER

+0.44 TEC TEI 6 HOT 620T1 101 83 0.18 0 P3 TWV 9 F07 18 HOT 6203L 101 91 0.13 49 P3 TWO 8 106 +0.69 TEC TEI

-1.84 TEC TEI 18 NOT 6201L 0.13 49 P3 TWO 8 F07 6201L TWO 10 F06 +0.82 TEC TER LA 18 NOT 10o 93 0.17 122 F3 14 HOT 6201L 99 P3 TWO 7 F06 -1.89 TEC TER 102 76 0.17 LA. 13 HOT 62071 113 P3 TWO 11 -1.82 TEC TER 102 78 0.12

A w Inc 3/7/2008 2:18:33 PH Component: S/G 12 Page 3 of 4 Customer Name: Calvert Cliffs Unit 1 FB Wear Indications (Sort by Row/Col)

OCERY: F3 Wear Indications by rov.qry EXT EXT UTIL 1 UTIL 2 CAL 4 LEG FROSE ROW COL VOLTS DEG CHN IND %TW LOCATION 0.24 139 P3 TWO 10 P06 -1.79 TEC TEE 14 SOT 620UL 102 82 125 P3 TWO 6 r06 -0.76 TEC TER 19 HOT 620tL 102 86 0.12 P3 TWD 14 F06 +0.72 TEC TER 39 HOT 620UL 102 88 0.15 108 0.11 141 P3 TWO 10 r07 +1.61 TEC TEN 11 HOT 62001L 103 73 129 P3 TWO 15 r07 +1.72 TEC TEE LAP 13 ROT 620VL 103 75 0.17 103 '9 0.22 141 P3 TWO 18 F07 41.69 TEC TER 13 HOT 620V5 P3 TWo 18 P06 -0.89 TEC TEE 13 HOT 620VL 0.23 133 P3 TWD 23 F07 +1.87 TEC TER LAR 13 HOT 620CL 103 81 0.35 128 P3 TWD 10 F06 -0.80 TEC TER LAP 13 SOT 6200'7 0.11 127 TWD 19 P06 +0.42 TEC TER 5 HOT 62007.

103 83 0.24 0 P3 TWD 13 r07 -0.87 TEC TEE LAR 15 NOT 620v1.

103 85 0.16 145 P3 108 P3 TWD 7 P07 +0.76 TEC TEN 19 ROT 620UL 103 89 0.16 P3 TWD 13 P07 +0.74 TEC TEN LAIR 17 HOT 620UL 103 91 0.15 134 0.19 102 P3 TWD 16 F06 -1.95 TEC TER LAR 17 ROT 620VL 116 P3 TWO 6 P06 -1.65 TEC TEN 12 HOT 620UL 104 72 0.13 141 P3 TD 13 P06 -1.85 TEC TEE 13 ROT 620VL 104 76 0.14 134 P3 TWO 9 F07 +0.71 TEC TEE 14 HOT 6200L 104 78 0.20 P3 TWO 13 P06 -1.78 TEC TEE 13 HOT 620UL 104 80 0.14 141 TWO 11 r06 -1.91 TEC TER LAR 13 HOT 620U0 104 82 0.12 118 P3 P3 TWO 12 P06 +1.23 TEC TER LAR 6 HOT 620UL 104 84 0.26 0 P3 TWO 8 F07 -1.95 TEC TEE 19 HOT 620UL 104 88 0.19 127 TWO 9 F07 -1.86 TEC TER 19 HOT 620UL 104 90 0.19 135 P3 105 P3 TWO 9 F07 +1.99 TEC TEE 18 HOT 620UL 104 94 0.16 0 P3 TWO 13 F07 -0.57 TEC TEE 6 HOT 620UL 105 83 0.27 0.27 0 P3 TWD 13 F06 -0.59 TEC TEE 6 ROT 6200UL 111 P3 TWO 9 P07 +0.69 TEC TEE 16 NOT 620UL 105 85 0.19 0.09 60 P3 TWO 5 F06 -1.82 TEC TEE 16 ROT 620UL 114 P3 TWD 9 r07 +0.67 TEC TER 19 HOT 62007 105 87 0.19 TWO 21 F07 +1.30 TEC TER LAR 19 ROT 62001L 105 89 0.57 136 P3 P3 TWO 8 P07 +0.73 TEC TEN 18 HOT 6201.L 105 91 0.14 83 68 P3 TWO 9 F06 -1.92 TEC TEH 18 HOT 620UL 0.16 TWO 8 F07 +0.82 TEC TEN 18 ROT 620UL 105 93 0.13 53 P3 128 P3 TWO 9 r07 +0.69 TEC TER 14 HOT 620U0 106 76 0.22 P3 TWO 12 F07 +0.74 TEC TER 13 NOT 620UL 106 78 0.13 138 TWo 8 F07 +0.63 TEC TEE 14 HOT 620UL 106 82 0.19 114 P3 TWD 6 P06 -1.93 TEC TEB 14 HOT 620u0 0.14 117 P3 F06 -0.80 TEC TEE LAR 5 HOT 620UL 106 84 0.09 0 P3 TWD 10

-1.86 TEC TEE 19 HOT 620UL 106 88 0.12 132 P3 TWO 6 P07

-1.86 TEC TEE 19 ROT 620UL 106 90 0.12 121 P3 TWO 6 P07

+1.86 TEC TEN 38 HOT 620UL 106 94 0.08 106 P3 TWO 9 P07 F06 -0.74 TEC TER 13 HOT 620UL 107 77 0.21 127 P3 TWO 17

-0.59 TEC TEE 5 ROT 620UL 107 83 0.19 0 P3 TWO 16 F07 P3 Two 22 706 +0.46 TEC TER LAR 5 NOT 6201.L 0.31 0

-1.50 TEC TEN LA.R 15 HOT 620U1 107 85 0.29 146 P5 TWO 11 F07 F07 +0.76 TEC TER 19 HOT 620UL 107 89 0.16 120 P3 TWO 7

+0.72 TEC TEE 13 HOT 620UL 108 82 0.17 140 P3 TWO 15 r07

-1.93 TEC TEE 13 ROT 620U0 0.20 144 P3 T7" 16 P06

-0.75 TEC TEN 6 SOT 620UL 108 84 0.13 0 P3 TWO 6 P06 620UL P3 TWO 10 r07 +1.59 TEC TEE LAR 6 NOT 0.21 0 706 +1.21 TEC TER LAR 6 HOT 620UL 0.20 0 P3 TWo 10 F05 -1.32 TEC TER 19 HOT 620UL 108 86 0.31 117 P5 TWD 10

-1.82 TEC TER 19 NOT 62001 108 88 0.15 121 P3 TWo 7 r07 F06 -0.82 TEC TEN 19 HOT 620WL 0.18 120 P3 TWO 8 F06 -0.80 TEC TEN 14 HOT 6200L 109 79 0.18 130 P3 TWO 0

+0.45 TEC TEE 6 HOT 62071 109 83 0.13 0 P3 TWO 7 P06 F0? +0.76 TEC TEE 19 SOT 6203L 109 89 0.18 133 P3 TWD 8 F07 +0.74 TEC TEN 13 HOT 6201L 110 78 0.13 59 P3 TWO 12

+1.77 FEC TER 19 HOT 6207L 110 86 0.19 121 P3 TWO 9 F0?

-0.76 TEC TEN 19 HOT 6207L 0.40 118 P3 TWO 16 F06 6207L F07 +1.86 TEC TER 19 HOT 110 88 0.17 102 P3 TWO 8 62071L TWO 7 P07 -1.43 TEC TEN 19 HOT 110 90 0.16 140 P3 6207L TWD 8 F06 -0.87 TEC TEE 39 ROT 110 92 0.16 128 P3

+1.78 TEC TEE LAR 13 ROT 62077.

111 79 0.14 127 ?3 TWD 13 F07 F06 -0.87 TEC TEE LAP 13 HOT 62037 0.16 140 P3 TWO 14

+0.72 TEC TEN LAP 15 SOT 6203L 111 85 0.17 122 P3 TWO 14 F07 6203L P3 TWO 10 F07 +0.69 TEC TER 19 HOT I11 87 0.22 110 62077L TWO 23 F07 +1.23 TEC TER LAR 19 HOT 111 89 0.64 129 P3 62077.

P3 TWO 5 207 +0.74 TEC TEE 14 ROT 112 78 0.12 123 62071L P5 TWO 6 F05 +1.17 TEC TER 19 HOT 112 90 0.19 151 ROT 6203L P3 TWO 15 F06 40.42 TEC TEH 5 113 83 0.17 0 6203L P3 TWO 6 P07 +0.76 TEC TEN 19 HOT 113 67 0.13 90 62071 P3 TWO 4 706 -1.75 TEC TER 14 ROT 114 76 0.10 99 62071L P3 TwO 7 706 -1.89 TEC TER 14 NOT 114 80 0.15 100 HOT 62071.

90 P3 TWO 8 PO6 +1.71 TEC TEE 38 114 92 0.08 6200L TWD 12 P06 +0.48 TEC TEE 5 HOT 115 83 0.13 0 P3

+0.69 TEC TER LAR 15 HOT 620UL 115 85 0.16 105 P3 TWO 13 Po7 P07 +0.71 TEC TEE 19 ROT 620UL 115 87 0.18 98 P3 TWO 8

+1.61 TEC TEE LAR 5 HOT 620UL 116 84 0.12 0 P3 TWD 12 F07

-0.78 TEC TFE LAR 5 HOT 620UL 0.14 0 P3 TWO 13 F06

+1.73 TEC TER 19 HOT 620UL 116 86 0.17 113 P3 TWO8 F07

AREVX NP Inc 3/7/2008 2:18: :34 P4 CuStomer NaMe: Calvert Cliffs Unit 1 Component: S/G ; 12 Paqe 4 of 4 FB Wear Indications (Sort by Row/Col)

QUERY: FB Wear Indications by row.qry ROW COL VOLTS DEG CdN IWNO%TWLOCATION EXT EXT UTIL I UTIL 2 CAL 0 LEG 620U-,

0.19 98 23 TWO 9 F06 -0.76 TEC TER 19 HOT 620m 116 88 0.16 112 23 TWO 7 F06 -0.82 TEC TER 19 HOT 116 92 0.17 92 P3 TWO 10 F06 +1.77 TEC TEE LAP. 18 HOT 620OZ 117 79 0.11 136 P3 TWO 5 F07 +1.78 TEC TEE 14 NOT 620U1 117 89 0.17 135 73 TWO 8 F07 +0.67 TLC TER 19 HOT 6200L 118 76 0.13 117 P3 TWD 6 F06 -1.84 TEC TER 14 HOT 620M.

120 80 0.19 138 P3 TWo 16 r07 -1.80 TEC TEE LAR 13 HOT 62001 120 84 0.15 0 P3 TWO 14 F06 -0.86 TEC TEE 5 ROT 620V.

121 85 0.26 114 P3 TWO 12 E06 -1.93 TEC TEE 26 HOT 6200*

121 87 0.12 121 P3 TWO 6 F07 +0.72 TEC TEE 19 HOT 6200L 123 87 0.10 153 P3 TWD 5 F07 +0.72 TEC TEE 19 ROT 620U'.

128 80 0.20 137 P5 TWO 7 F06 -1.39 TEC TER 13 HOT 620CU Total Tubes  : 144 Total Records: 172

9 AREV1 NP Inc 3/712008 2:19:04 PM Customer N~ame: Cal7ert Cliffs Unit I Component: S/G 12 Paqe 2 of 2 Lattice Support Wear Indications QUERY: TSP Wear Indications ROW COL VOLTS DEC CIO INO %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBEK 122 86 0.20 129 P3 Two 9 07C +1.07 TEC TER LAR 19 ROT 62OUL 134 68 0.15 118 P3 TWO 14 02H -1.53 TEC TER LAR 1 ROT 62011L Total Tubes : 2 Total Records: 2

hREvA tP Inc 3/7/2008 2:17:15 PM Customer Name: Calvert Cliffs Unit 1 Component: S/c 12 Page 2 of 2 NOI Indications QUERY: NQI Indications ROW COL VOLTS DEG C824IND ITW LOCATION EXT EXT UTIL I UTIL 2 CAL # LEG PROB-E 106 134 0.64 68 5 NQO: TSH +7.12 TEC TER LAP 2 HOT 620CIL Total Tubes  : 1 Total Records: 1

ARMV nP Inc 3/7/2008 2:19:55 PM Customer Name: Calvert Cliffs Unit 1 Component: S/G 12 Page 2 of 2 DFS/DFH indications QUERY: DFrHDYS Indications ROW COL VOLTS DFO C.HNflD %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG KOBE 22 46 0.34 99 5 DFS 03C +14.47 TEC TEE LAR 45 HOT 620UL 60 74 0.26 152 5 DFS 05 +32.78 TEC TER LAR 13 HOT 620UL 79 139 0.30 153 5 DFH 0lC +9.55 TEC TE. LAR 41 HOT 620UL Total Tubes  : 3 Total Records: 3

AREVA NP Inc 3/7/2008 2:19:33 PH Customer Name: Calvert Cliffs Unit I Component: S/G 12 Page 2 of 2 WAR Indications QUERY: WAR Zndication3 ROW COL VOLTS DEG CHN IND %TWLOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PRO13E 85 59 0.25 77 P5 WAR F07 +1.46 F07 to7 22 34 HOT 56072 87 75 0.18 111 P5 WAR r07 +1.83 r07 F07 17 34 HOT 560??

103 79 0.21 108 P5 WAR F06 -0.79 F07 F06 19 34 HOT 560?P 0.21 108 P5 WAR r07 +1.80 P07 F06 19 34 HOT 5602P 103 81 0.29 100 PS WAR r07 +1.87 F07 F07 24 34 HOT 560??

103 83 0.20 107 P5 WAR FOG 40.49 F06 F06 18 34 HOT 5602?

103 91 0.21 100 P5 WAR F06 -1.75 r07 F03 19 34 HOT 5607P 105 89 0.31 106 P5 WAR F07 +0.98 r07 F07 25 34 HOT 5602P 106 134 0.14 71 P4 WAR TSH +7.18 TSH 01R 10 37 HOT 610?P 107 77 0.22 103 P5 WAR F06 -0.71 T06 F06 20 34 BOT 560?P 107 83 0.19 103 P5 WAR F06 +0.21 r0o F06 18 34 HOT 560?P 0.23 106 P5 WAR F07 -0.50 r08 F06 20 34 HOT 560?P 108 82 0.19 119 P5 WAR F06 -1.80 F06 F06 18 34 HOT 560?P 110 86 0.28 107 P5 WAR F06 -0.87 F06 P06 24 34 HOT 560?P 111 89 0.39 102 P5 WAR F07 +1.01 r07 r07 29 34 HOT 5607?

120 80 0.19 83 P5 WAR F07 -1.83 P07 V07 18 34 HOT. 560?P 122 86 0.14 85 PS WAR 07C +1.08 07C 07C 14 34 HOT 560?P 134 88 0.18 82 P4 WAR 02H -1.54 01H 02H 13 37 HOT 6107P 86 WAR 02B -1.55 01R 03H 12 36 HOT 610?P 0.18 P4 Total Taube  : 16 Total Records: 19

AREVA NP Znc 3/7/2008 2:16:27 PM Customer Name: CalveOt Cliffs Unit 1 Corponent: S/G 12 Page 2 of 2 DNG Indications QUERY: DNG IndLcations ROW COL VOLTS DEG CHN IND %TW LOCAT ION EXT EXT UTIL 1 UTIL 2 CAL# LEC PR03E 18 164 5.48 186 P1 DNG t0. 40.46 TEC TEE HR 4 ROT 620"L 38 86 1.00 185 PI ONG 05H +22.77 TEC TEE 47 HOT 62037 102 28 5.22 181 P1 DNG rlo -0.90 TEC TER 8 HOT 620UL 3.72 183 P1 DNG -1.18 TEC TEE 6 HOT 620UL 117 41 F09 2.16 183 P1 DNG F07 -1.29 TEC TER 6 HOT 6201!L PI -0.83 TEC TEE 8 HOT 6200L 120 44 2.92 181 DXG F07 Total Tubes  : 5 Total Records: 6