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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: SUBJECT: Document Control Desk 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 (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: (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 S. J. Collins, NRC Resident Inspector, NRC S. Gray, DNR X047 .QV4?
Transcript
Page 1: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

Calvert Cliffs Nuclear Power Plant

Constellation Energy-Nuclear Generation Group

1650 Calvert Cliffs ParkwayLusby, Maryland 20657

December 3, 2008

U. S. Nuclear Regulatory CommissionWashington, DC 20555

ATTENTION:

SUBJECT:

Document Control Desk

Calvert Cliffs Nuclear Power PlantUnit No. 1; Docket No. 50-318Response to Request for Additional Information - 180 Day Report on the Spring2008 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 GeneratorReport

REFERENCES:

(b) Letter from Mr. D. V. Pickett (NRC) to Mr. J. A. Spina (CCNPP), datedOctober 15, 2008, Request for Additional Information Re: 180-Day Reporton the Spring 2008 Steam Generator Tube Inspection- Calvert CliffsNuclear Power Plant, Unit No. I (TAC No. MD9446)

In Reference (a), Calvert Cliffs Nuclear Power Plant submitted the 180 Day Report on the Spring 2008Unit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commissionrequested additional information to be submitted to support their review of the report. Our response tothis 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. FlahertyManager - Engineering Services

MDF/KLG/bjd

Attachment: (1) Response to Request for Additional Information -- Unit 1 180 Day SteamGenerator Report

cc: D. V. Pickett, NRCS. J. Collins, NRC

Resident Inspector, NRCS. Gray, DNR

X047.QV4?

Page 2: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1

180 DAY STEAM GENERATOR REPORT

Calvert Cliffs Nuclear Power Plant, Inc.December 3, 2008

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

RAI 1:

For each refueling outage since installation of the steam generators (SGs), please provide the cumulativeeffective 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 11and 12 had operated for 21.13 effective full power months (EFPM). As of the 2006 refueling outage, theyhad 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 theCalvert Cliffs Nuclear Power Plant Unit 1 SGs during the spring 2008 inspection; an increase ofapproximately 2/3fioom the 189 indications in 166 tubes identified during the 2004 inspection." Pleasedescribe any insights on the cause of the increase of FBW indications. Please also describe the sizedistribution of the new FBW indications found in the spring 2008 inspection in comparison to the sizedistribution of the FBW indications found in the 2004 inspection. If the size distribution of the newindications is comparable or more severe than the size distribution of the old indications, please discusswhether the conditions are becoming worse with time. Please also discuss what tubes are considered tobe 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, itwas expected that there would be new indications of FBW during the 2008 inspection. Fan bar wear iscaused by locally increased tube support clearances. These increased clearances may be the result of adifferent method of bundle support used during manufacturing, or the result of grid adjustments that weremade to improve manufacturability. These causes do not change with time, so the condition of the SGs isnot becoming worse with time. Indications of wear in new tube locations during the 2008 inspection wereseen because wear occurs over a spectrum of wear rates. Those locations with higher wear rates wereevident as wear indications during the first inspection in 2004. Areas with lower wear rates likely hadwear below the detectability threshold in 2004, and only after an additional two cycles of operation didthey show up as "new" wear in 2008. In all cases, the FBW rate is expected to slow dramatically afterwear is initiated. This was supported by the 2008 inspection results which revealed only a small growthrate of existing indications.

In addition the FBW indications, first reported in 2008, were generally shallower than those reported in2004, despite having been in service three times longer. This can be seen by the results presented inFigures 1 and 2 below. Figure 1 shows the FBW indications that were reported in 2004. Figure 2 showsthe indications that were first reported in 2008, which are, on average, shallower.

I

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

2004 Fan Bar Wear Indications35-

30- *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

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Sb.

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0

2008 New Fan Bar Wear Indications

*SG 11 ISG 12

I.. I All.lh1111 •l' 1 a,.I- ,E0 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 FBWindications that were first reported in 2004 (those values are shown in Figure 1). In comparing Figures 1and 3, one can see that little overall growth occurred between 2004 and 2008, which supports the analysisthat FBW growth slows over time. Based on the smaller size of new indications, and the very smallgrowth rate of existing indications, it is concluded that conditions are not becoming worse with time.

2

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

2008 Pre-Existing Fan Bar Wear35

3SG 11 uSG 1230 ,

o 25"am Z•0 20 ' ' 'C

o 15 -

E 10 fZ 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 thatFBW occurs at tubes with intermediate radii. This is confirmed by the following explanation provided bya B&W representative in an email response to Calvert Cliffs:

"It is recognized that achieving small clearances between tubes and supports is essential formitigation of wear. Within the susceptible region the tube to support clearances are somewhatvariable since the layers of tubes are capable of laterally shifting within their availableclearances. If a few layers within the susceptible region bunch up then larger clearances mayopen in other positions within the susceptible region thereby initiating tube wear. The smallerradius tubes are stiffer in their out-of-plane direction and have less cross flow therefore havebetter clearance control and are less susceptible to wear and consequently are not within thesusceptible region. Also the tubes closest to the external U-bend support structure are stiffer intheir out-of- plane direction since the support structure maintains a regular pitch pattern. Thisenhanced pitch control in the region closest to the support structure helps to control theclearances and therefore is less susceptible to wear."

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

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

3

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

were used to determine the "fan bar wear susceptible region." Figures 6 and 7 show the entire inspectionmaps for SGs 11 and 12 respectively, which include the bundle peripheries and a sample of the rest of thetube bundles. They also show all of the FBW indications detected in 2008.

Calvert Cliffs Unit 1Fan Bar Wear - Critical Area and Buffer Zone

GROUP TUBES9 S 12,1104 Wwu N

LI -31r JarWE Vlc- '~e _'c, C re -C -. r Be, 'Oeo CA 1 504

SUALE 60 (1534t X -Tue Jan 29 12:20 N 2M8LISIG I I

HOTPRI41ARY FACE

TOTAL IUBES, 3411SELETE.D TUBES 19MOUT OF SERVICE t#) NA

NOI/i F

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MANWAY

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

4

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

Calvert Cliffs Unit 1Fan Bar Wear - Critical Area and Buffer Zone

GROUP TUBESSG 12 2004 Wear 87

B Fan Ear Wear BJfw Zone 389C Fan Bar Wear CA 1605

S.G 12HOTPRIMARY FACE

TOTAL TUBES: 8471SELECTED TUBES: 1994OUT OF SERVICE (#): NA

SCALE: 0.067388 XTue Jan 29 12:09.19 2008

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,1 -3 1.• -

MANWAY

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

5

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR 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. 8471HOT SELECTED TUBES. 4261PRIMARY FACE OUT OF SERVICE (t) I SCALE 0,087388 X

Tue Mai 04 12 1 06 2008

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

6

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

GROUP IUBES-HI-L)- N0 Fo~Br BtWcon 144-0Calvert Cliffs Unit 1 C Ciuc.IArwou6 ,-.142

1 R1 8 Fan Bar Wear Tested•OutsideCA8Z 2242:•

S.G 12 TOTAL TUBES. 8471HOT SELECTED TUBES. 423tiPRIMARY FACE OUT OF SERVICE (3) 0 SCALE O W1388 X

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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.

CCNPP Response:

No secondary side inspections were performed during the 2008 SG inspection. This was based upon thefollowing: bobbin-probe eddy current was performed on 100% of the periphery and the no tube laneborder 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 supporton the hot side along with an indication that was most likely caused by a lattice bar burr. The surroundingtubes 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 sidedue to difficulty in reaching the location, the decision was made to conservatively treat the indication as aforeign 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 wearon tube SG 11 R8C 130 could not be investigated because of the difficulty in reaching that location, so asecondary 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 anextensive secondary side visual inspection. During this 2004 inspection no foreign objects were detected

7

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

in the Unit I SGs. Therefore it is believed that foreign material intrusion is not a significant problem forCalvert 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 FBWand required follow-up testing. There were six "ambiguous bobbin indications" on SG 11 and three onSG 12, as shown in Table I below. After inspection with a rotating probe coil, all of these indicationswere confidently classified as described below.

* SGlI R8C130 showed an indication of a lattice grid burr and was conservatively plugged asdescribed above.

" The indications in tubes SGII R17C55, SG11 R115C125, and SGI 1 R137C83 were determined notto 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 bewear caused by lattice support wear. Based on the low observed growth rate from the initialoperation of the SGs to the 2008 inspection, it was concluded that these indications will not threatentube integrity before the next scheduled inspection.

* The indications in tubes SGI 1 R126C 114 and SG12 R106C134 were determined to be caused byforeign objects. In both cases, no foreign objects remained adjacent to the tube. More informationabout the evaluation of these indications is provided in the response to RAI 8.

Table 1: Description of"Ambiguous" Bobbin IndicationsForeign

Steam Offset Maximum Cause o F Object PluggedGenerator Row Column Elevation (in) Depth Damae POtent and

(in) (%TW) Damage Potentially StabilizedPresent

11 8 130 05H -1.51 7 Foreign Object Yes* YesWear11 17 55 TSC -0.13 N/A No Damage No No

11 78 94 04H 0.51 11 Lattice Support No NoWear

11 115 125 F07 12.11 N/A No Damage No No

11 126 114 TSH 0.95 26 Foreign Object No NoWear11 137 83 F06 12.09 N/A No Damage No No

12 106 134 TSH 7.12 30 Foreign Object No NoWear

12 122 86 07C 1.07 9 Lattice Support No NoWear

12 134 88 02H -1.53 14 Lattice Support No NoI I_ Wear

Lattice support burr or small foreign object. Conservatively treated as foreign object.

8

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ATTACHMENT (1)

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -- UNIT 1180 DAY STEAMGENERATOR REPORT

RAI 5:

Presumably, a number of new bobbin indications were identified near the fan bars. Of tlwse new bobbinindications, it does not appear that all were inspected with rotating probes and that only those indicationsgreater 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 bobbinindications were determined. Please discuss how wear attributed to tube-to-tube contact and loose partswas ruled out as the causal mechanism.

CCNPP Response:

A cutoff of 15% TW for inspecting with rotating probes was chosen to provide a reasonably largeinspection population of large wear in order to confirm that the length of the new and pre-existing weardid not exceed the bounding value of length used in the Condition Monitoring / Operational Assessmentreport. 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 thelargest 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 throughinterim phone calls. None of these plants have experienced foreign object wear in the fan bar region, andit 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 latticesupports have four contact points, which further decreases the likelihood of a loose part causing damageat a fan bar support rather than becoming stuck at a lattice support. Based on this information, theabsence of loose part indications in the eddy current data was taken as reasonable assurance that the wearidentified was not caused by loose parts. In addition, tube-to-tube contact was ruled out because FBWoccurs only at the fan bar supports, while tube-to-tube contact occurs between supports. The fan bars areidentifiable with eddy current by their unique signal, and no wear indications were identified away fromthe fan bar supports.

RAI 6:

Please discuss whether any tubes were identified that 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:

Please provide a list of all service induced indications including their location, orientation (if linear) andmeasured sizes.

CCNPP Response:

There have been no linear indications detected at Calvert Cliffs. All of the indications of degradationidentified during the 2008 SG inspection were volumetric in nature. The details of the length and size ofthe 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 toforeign object wear (SG11 R126C1J4 and SG12 R106C134) to confirm the absence of a loose part. In

9

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ATTACHMENT (1)

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addition, please discuss whether potential loose part indications (from the eddy current data) werevisually 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 foreignobject wear (SG1 I R126C1 14 and SG12 R106C134). These indications were dispositioned based oneddy current results. For SGI I R126C 114 and SGI2 R106C134, 3-coil rotating probes were used inthese 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 1R8C130) that was plugged and removed from service as discussed earlier. Since no objects remainadjacent to any of the remaining in service tubes (see Table I above) that have experienced foreign objectwear 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 foreignobject wear in each SG during ensuing operating intervals must be considered. It is difficult to predict ifand 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 toforeign 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 bothSGs. These inspections revealed no foreign objects which could damage SG tubes and revealed noforeign 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 migratoryforeign 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 longercapable of causing tube damage, or have moved to a new location within the tube bundle. Migratoryobjects are known to move in the direction of the flow, toward the interior of the tube bundle and towardareas 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 foreignobject 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 crossflow and lower potential to cause significant tube damage. Therefore, if they remain within the tubebundle, 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 indamage that exceeds the structural performance criteria prior to the next SG inspection. Because no wearexceeding the structural criteria is expected, it is concluded that the operational leakage and accidentleakage performance criteria will not be exceeded by foreign object wear.

10

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ENCLOSURE (1)

Steam Generator 11 Indication Report

Calvert Cliffs Nuclear Power Plant, Inc.December 3, 2008

Page 14: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

ARVA NP IncCUtoeer Nam e; Calvert C1cfa3 Unit I

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R.OW COL VOLTS DEC CHI IND %TW LOCATION

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98 9099 6599 7999 8399 89100 78100 82100 84100 90101 75101 79

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102 78102 80102 86103 79

103 81103 83104 80104 82

0.250.130.140.170.160.130.160.090.210.100.120.160.110.100.110.130.140.110.120.110.180.220.120.100.110.200.130.120.130.160.130.140.100.130.140.080.080.120.120.130.110.120.110.220.190.090.140.090.120.140.100.120.220.130.150.130.130.120.180.120.190.200.150.100.160.160.160.180.260.110.110.090.110.240.280.160.060.160.180.29

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121 P3 TWO 8103 P3 TWD 7112 P3 TWO 7125 P3 TWO 6114 P3 TWO 980 P3 TWD 6120 P3 TWD 10115 P3 TWO 10125 P3 TWD129 P3 TWD 6130 P3 TWO 8134 P3 TWO 8129 P3 TWO 8102 P3 TWO 9111 23 TWO 13135 P3 TWO S140 P3 TWD 5126 P3 TWO 5137 23 TWO 6121 t3 TWO 12133 P3 TWO 1401 ?3 TwO 6137 P3 TWO 1117 P3 TWO 8113 P3 TWO 9135 P3 TWO 15

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41.48+1.71+0.90-1.14-0.80-0.90+1.47-1.29+1.53+0.72+0.83+1.78+0.70+0.65+1.69+0.75+1.46+1.72-0.74+0.76+1.82+1.81+0.63+0.76+1.79+1.75+1.69+1.68+0.50-0.90-1.92+0.77+0.76+1.71+0.77-1.87-1.92+0.75-0.54+0.77+0.65+0.70+0.82+1.04-0.55+0.78+0.77-0.92+0.85+0.74+1.77+1.83+0.79+0.76+1.68+0.83+1.76+1.14+1.76+0.55+0.71-1.86+0.66+1.72+1.73+1.79+1.77-0.74-0.59+0.68-1.83-1.80+0.76+1.70+1.72-0.75-1.87-0.57+0.83+0.90

EXT EXT

TEC TEETEC TEETEC TERTEC TEETIC TERTEC TERTEC TEETEC T•ETEC TEETEC TERTEC TEETIC TERTIC TEETEC TERT3C TERTEC TERTEC TERTEC TEETEC TERTEC TEETEC TERTEC TEETEC TERTIC TERTIC TEETEC TERTEC TERTEC TERTEC TERTEC TERTEC TEETEC TEETEC TEETEC TEETEC TERTEC TESTEC TEETEC TEETIC TEETEC TEETIC TEETIC TERTEC TERTEC TEETEC TERTEC TEETEC TERTEC TEETEC TEETIC TEETEC TEETEC TEETEC TERTEC TERTEC TERTEC TEATIC TEETEC TEETEC TEETEC TERTEC TEETEC TERTEC TEETEC TEETEC TEETIC TEITEC TERTEC TERTEC TEETEC TERTEC TIETEC TEETEC TERTIC TEETEC TERTEC TERTIC TEETEC TEETEC TERTEC TER

OTIL I OTIL 2 CAL I

42LAR 11

16LAR 11

512

LA. 11171115

6LAR 11

16LA. 1IILAR 11

12LAR 11

11121411

LAP. 11LAR 6LAR 6LA.R 11

15LAP, 11LAP 6

S

1113131111114315

LAR 6141412

LAP. 514512131111151312

LAP. 14121212421611543

L.AE. 11LAP. 11

6431312126111112121211

LAP 1111

LAP. 51112

LEG

HOTHOTHOTHOTSOTSOTDOTSOTROTHOTSOTHOTHOTHOTHOTHOTHOTNOTNOTHOTHOTHOTROTROTHOTHOTHOTPOTHOTROTPOTEOTHOTHOTHOTHOTHOTHOTHOTHOTSOTHOTSOTSOTHOTHOTHOTPOTPOTHOTHOTHOTHOTHOTHOTROTHOTSOTHOTHOTSOTHOTHOTSOTPOTHOTROTHOTHOTHOTHOTHOTROTHOTHOTROTROTSOTHOTHOT

PROBE

6200!6200!6200162001.6200L6200!6200L6200!620UL6200L620UL62010L62005620016200!620!L6200!620016200!6200L620016200L62001.6201L6200L6200!6200L6200L6200U,62001.6200!62001620CL62001620016200L6200!620016200L620UL620C7L6200!6200562CUL6200!620!L6200!6200C620UL6200C62C0UL62 CL62CU!62CU!620U!6200!6200!620016200!.62C!.62CCL62 CL6200L6200!6200!6200!6200!.6200U6200L620016200L6200L62001620'L6200!62001.62CUL62CCL62CU!62CUL

Page 15: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP IncCustomer Name: Calvert Cliffs Unit 1

03/07/08 14:28:27Component: 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

104 88105 75105 79

105 85105 89106 78

106 80106 82106 86106 88107 79107 83107 85107 87107 89108 78108 84

108 88109 79109 83

109 87110 76110 78

111 79111 87111 89112 76112 78112 80113 79113 83113 85113 89114 74114 76114 78114 80114 82115 75115 79115 85115 87

115 91116 72116 78116 86

117 79

117 83117 87117 99118 78

120 82

120 88

121 79123 81125 81127 81127 91

0.120.110.150.330.120.120.280.170.150.110.160.230.170.110.340.140.170.140.160.130.140.120.140.130.170.120.160.140.150.220.230.120.100.130.170.180.270.140.080.120.120.130.220.180.190.120.150.110.170.120.110.180.100.230.150.250.570.120.110.120.110.140.430.200.110.120.100.140.100.190.120.15

139 P3135 P3127 P3131 P3142 P3102 P3124 P3127 P3130 P3114 P3135 P3127 P3129 P3123 13120 P3108 P3118 P3147 P3131 P3131 P3114 P3108 P3121 P3129 P3119 P3108 P3105 P3125 P3116 P3129 P3103 P5133 P3117 P3136 P398 P3128 P3131 P3131 P3122 P3141 P385 P3117 P3141 P3134 P3118 P3134 P3123 P3137 P3131 P3138 P3135 P3127 P3134 P3134 P3125 P3124 P3125 P3117 P3141 P399 P3128 P3100 P3123 P3137 P3III P392 P3130 P3145 P3130 P3129 P3132 P3136 P3

TWO 5TwO 5TWO 7TwO 16TWO 6TOD 5TWO 15TWO 9TWO 8TWo 6TWD 8TWO 12TWD 10TWO 5TWO 16TWO 7TWO 9TWO, 7TWO 8Two 7TWO 8TWO 6TWD 7TWD 7TWD 9TWD 6TWO 8TWO 6TWO 8TWO 11TWO 9TWO 6TWO 5TWo 7TWO 8TWO 9TWo 13TWO 7TWO 2TWO 7TWO 5TWD 6TWo 11TWO 9TWO 10TWO 5TWO 8TWO 6TWO 9TWO 6TWD 6TWD 8TWO 4TWO 12TWO 8TWO 12TWO 23TWO 6TWO 5TWO 6TWO 6TWo 7TWO 20TWO 10TWO 6TWO 6TWO 5TWD 7TWO 5TWoD 10TWO 7TWO 9

P06F06F07F07F06F07P07F07F06F07F07107

P08r07r07P07E06T077087071706P06F06r08

P07F06706P07F07F06F09F07F07F07

707106F06F0710?r07r70

F06707707r07

F07r06707707TO?r07F06r07F07F06r077o06'07r07r0EF07F06

7'06704

7"06r07F07FOBF06F09

F06

-1.69-0.74+1.74+1.76-0.76+0.75+0.83+0.78-1.74+0.74+0.84+1.67-0.78-1.89-0.55+0.72-1.88+0.78-1.23+1.75-0.85-0.78-0.80-0.55+0.46+0.48+1.61+0.78+0.80-1.73+1.16+0.61+0.74+0.77+0.73+1.67-0.76-0.55+0.82+0.70-1.90+0.81+0.82+0.76+0.76+1.72-0.77+0.72+0.72-1.9040.85+1.69+0.75+1.69-0.79+1.69-0.80-0.55+0.75+0.76+0.80-1.79+1.48+0.84+1.80-0.80+1.60+1.69+0.65-1.47+1.7240.89

TEC TENTEC TEETEC TERTEC TERTEC TERTEC TERTEC TEETEC TERTEC TERTEC TERTEC TENTEC TERTEC TERTEC TERTEC TEETEd TEETEC TERTEC TERTEC TEETEC TEETEC TEETEC TERTEC TENTEC TERTEC TEETLC TEETEC TEETEC TENTEC TEETEC TENTEC TENTEC TERTEC TENTEC TENTEC TENTEC TENTEC TERTEC TENTEC TENTEC TERTEC TERTEC TENTEC TENTEC TERTEC TENTEC TERTEC TENTEC TENTEC TEETEC TEETEd TENTEC TEETEC TENTEC TENTEC TENTEC TERTEC TENTEC TENTEC TENTEC TENTEC TENTEC TERTEC TERTEC TENTEC TERTEC TENTEC TERTLC TEETEC TENTEC TENTEC TENTEC TER

11431312121142121212121242115121243116643126

LAR 6LAR 6

11141212

LAR 111243131111

12LAR 5

1142141412121214

LAR 1112121242141111

LAR 1112

LAR 12LAR 6

11181212

LAR 11LANR 11

4343121112

LAR 114242

HOTPOTHOTHOTNOTNOTNOTHOTNOTNOTNOTHOTHOTSOTSOTHOTROTROTHOTNOTHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTROTNOTHOTPOTHOTHOTHOTHOTHOTNOTROTHOTHOTHOTNOTSOTHOTNOTHOTHOTHOTHOTSOTHOTHOTSOTSOTROTHOTHOTNOTNOTHOTHOTNOTNOTHOTROT

62CUL62C0L62CDL62CUL620CL6200L6200L620UL620UL6200L620UL620016200L6200L620UL6209L620UL620UL620UL620UL620UL620UL6200L620UL620UL6200L6200L620DL620UL6200L6207L6200L6200162001620UL620CL6200L6207L6203L6203L620UL6200L6200L6209L6207L6200L6203L6203L6203L6207L62071L6207L620JL6203L6203L620n16207L620DL6203L6203L6207L6207L6201L6207L6207L6207L620"CL62073L6207L620rL620UL620UL

Total Tubes : 128Total Records: 152

Page 16: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP IncCustomer Name: Calvert Cliffs Unit I

03/07/08 14:28:27Component; 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.. . ...

575860686869727376777880

8383

838485868787

88

888989899091929292

92939394949494959595969696979797989898

9899999999100100100100101101

101101

102102102103

103103104104

89 0.2582 0.1368 0.1454 0.1784 0.1679 0.1386 0.16107 0.0986 0.2169 0.1084 0.1286 0.16

0.1169 0.1079 0.11

0.1387 0.1486 0.1181 0.1280 0.1175 0.1879 0.22

0.1284 0.10

0.1186 0.2069 0.1381 0.1283 0.1384 0.1881 0.1374 0.1476 0.1078 0.13

0.140.08

88 0.0869 0.1283 0.1274 0.1376 0.1182 0.1284 0.1175 0.2283 0.1985 0.0974 0.148o 0.0982 0.1265 0.1475 0.1079 0.1274 0.2280 0.1382 0.15

0.1390 0.1365 0.1279 0.1883 0.1289 0.1978 0.2082 0.1584 0.1090 0.1675 0.1679 0.16

0.1883 0.2687 0.11

0.1178 0.0980 0.1186 0.2479 0.28

0.1681 0.0683 0.1680 0.1082 0.29

110 P3132 P3142 P3131 P3133 P3133 P3141 P374 P3108 2398 P3117 P3130 P3108 P3129 P3134 P3133 P3128 P359 P314C P313( P312C P31le P313( P385 2372 P313C P311S P3131 P375 P3117 P3146 P3145 P3117 P3140 P3143 P313f: P376 P3130 P388 P3103 P3126 P390 P3132 P3124 P394 P399 P3121 P3156 P3138 P360 P3123 P3106 P3112 P3I18 P3121 P3103 P3112 P3125 P3114 P388 P3120 P3115 P3125 P3129 P3130 P3134 P3129 P3102 P3lI1 I 3135 P3140 P3124 P3137 P3121 P3133 P381 P3137 13117 P3113 P3135 P3

TWO 14Two 6TWD 7TWO 9TWO 8TWO 7TWO 8TWO 6TWO 11TWD 5TWO 7TWO 8TWO 5TWO 5TWO 5TWD 6TWO 7TWD 5Two 5TWO 6TWO 8TWO 12TWO 5Two 6TWO 6TWO 10TWD 7TWO 5TWO 7TWO 9TWO 6TWO 7TWO 5Two 6TWO 7TOD 2TWO 4TWD 6TWO 6TWO 6TWO 5TWO 6Two 6TWO 10Two 10TWD 5TWO 7TWD 4TWO 5Two 7TWO 5TWO 6TWO 10TWO 7TWO 0TWD 7TWO 7TWO 6TWO 9TWO 6TWO 10Two 10TWO 8TWO 6TWD 8Two 8TWO 8TWO 9TWO 13TWO 5TWO 5TWO 5TWO 6TWD 12TWO 14TWO 8TWO 1TWO 8TWO 9TOD 15

T08P0770?F07F06707707707707r08F08707r08r08

07F08F07F07F06F09F07707r08F08F07r07F07707706F10707707r07r08707F06r08r08r08V07F07707r08F07707707707706r07F07r07707r07707F08707F07F07F07706F07F06F06F07707707707r06707707P06F06708F07r07706T0?F07F07707

+1.48+1.71+0.90-1.14-0.80-0.90+1.47-1.29+1.53+0.72+0.83+1.78+0.70+0.65+1.69+0.75+1.46+1,72-0.74+0.76+1.82+1.81+0.63+0.76+1.79+1.75+1.69+1.68+0.50-0.90-1.92+0.77+0.76+1.71+0.77-1.87-1.92+0.75-0.54+0.77+0.85+0.70+0.82+1.84-0.55+0.78+0.77-0.92+0.85+0.74+1.77+1.83+0.79+0.76+1.88+0.83+1.76+1.14+1.76+0.55+0.71-1.86+0.66+1.72+1.73+1.79+1.77-0.74-0.59+0.68-1.83-1.80+0.76+1.70+1.72-0.75-1.87-0.57+0.83+0.90

EXT EXT

TEC TERTEC TEETEC TERTEC TERTEC TERTEC TERTEC TERTEC TEETEC TERTEEC TERTEC TENTEC TERTEC TERTEC TENTEC TENTEC TEETEC TERTEC TERTEC TENTEC TEETEC TEETEC TEETEC TEETEC TENTEC TEETEC TENTEC TERTEC TERTEC TERTEC TENTEC TENTEC TERTEC TEHTEC TENTEC TERTEC TENTEC TENTEC TENTEC TERTEC TEETEC TENTEC TENTEC TENTEC TEETEC TENTEC TERTEC TERTEC TERTEC TENTEC TEETEC TENTEC TEETEC TERTEC TERTEC TERTEC TENTEC TERTEC TERTEC TEHTEC TEETEC TEETEC TENTEC TENTEC TENTEC.TEHTEC TERTEC TENTEC TERTEC TENTEC TENTEC TENTEC TEETEC TENTEC TERTEC TERTEC TERTEC TENTEC TERTEC TENTEC TER

UTIL 1 UTIL 2 CAL # LEG PROBE

42LAR 11

16LAR 11

512

LAR 111711156

LAR 11LAR 11

16LAR 11LAN 11

12LAR 11

11121411

LAR 11LAN 6LAN 6LMN 11

15LANR 11LAR 6

51133131111114315

LAR 6141412

LAR 514512131111151312

LAN 14121212421611543

LAR 11LAR 11

643131212611

11121212

11LAN 1

11

1111

HOTHOTNOTHOTSOTNOTSOTHOTHOTSOTHOTHOTHOTHOTHOTHOTNOTNOTHOTROTROTHOTNOTHOTNOTHOTHOTHOTROTPOTROTPOTNOTHOTROTNOT

HOTHOTHOTHOTHOTHOTROTHOTHOTLOTROTHOTHOTHOTNOTNOTHOTHOTHOTROTHOTROTNOTNOTHOTHOTHOTROEHOTHOTHOTHOTHOTHOTHOTHOTHOTHOTNOTEDTHOTHOTHOTHOT

6200L6203L6207L6200L6200L620UL6200L6200L6200L6200L620016200L6200L620UL6200L620CL6200L6200L6200L6200C6200C6200L6200L62C0L62COL62C0T,62COL62(0U62CU062C0162C0L62CCL62C062CuL62CM062M0162C0L6201L6200L62C0L6200L62COL6200U620016200L620U0L620UL6200L6200L6200L6200L6200L620056200L6200L6200L6200L6200L6200L620016200L6200L6200L620UL6200L620M6200=16200L6200162001620016200n620016200L6200L6200L620016200L620016200L

Page 17: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA VP Inc 03/07/08 14:27:48Customer Name: Calvert Cliffs Unit 1 Cozponent: S/G 11 Page 2 of 2

Lattice Support Wear indications

CUERY: TSP Wear Indications

ROW COL 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 : 1Total Records: I

Page 18: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

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 : 1Total Records: 1

Page 19: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP Inc 03/07108 14:30:50Customer Nlame: Calvert Cliffs Unit 1 Component: SIG 11 Page 2 of 2

DTI IndLcations

QUERY: DTI Indications

ROW COL VOLTS DEG CNN IND %TW LOCATION 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 : 1Total Records: I

Page 20: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP Inc 03/07/08 14:30:15Customer 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 MTW LOCATION EXT EXT OTIL 1 UTIL 2 CAL # LE5 PRO3E.. ....... * w........ ~ n .- .l m .. .* ...........

115 125 5.75 141 5 NQ1 r07 +212.11 TEC TEH DBP LAR 5 HOT 620UL126 114 0.12 127 P1 NQ0 TSH 40.95 TFC TEH LAR 2 HOT 6200L

Total Tubes : 2Total Records: 2

Page 21: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

ARZVA NP Inc 03/07/08 14:29:56Customer Name: Calvert Cliffs Unit I Component: S/C 11 Page 2 of 2

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 : 1Total Records: 1

Page 22: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AAREVA NP IncCustomer Name; Calvert Cliffs Unit I

03/07/08 14:28:07Coaponent: 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

8 130 0.16 111 P4 WAR 05H -1.50 05H 05H 778 94 0.15 78 P4 WAR 04H +0.61 04H 04H 8105 79 0.29 105 PS WAR F07 +1.84 r07 F07 22107 83 0.26 107 PS WAR F07 -0.50 F07 F07 20117 79 0.36 102 PS WAR r06 -0.83 F06 F06 25120 82 0.23 88 P5 WAR F06 +1.55 F06 F06 18126 114 0.07 72 P4 WAR TSH +0.85 TSH 018 3

CAL 4 LEG

41 HOT54 HOT40 HOT40 HOT40 HOT40 HOT41 HOT

PEZBE

6101?

5(0PP50OPP5(0PP

610PP

Total Tubes : 7Total Records: 7

Page 23: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP Inc 03/07/08 14:31:04Cust•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 6200L114 38 2.32 191 P1 DNG F06 +4.42 TEC TER 8 HOT 620UL114 68 14.41 181 P1 DNG 02C -2.62 TEC TER 15 ROT 620UL

Total Tubes : 3Total Records: 3

Page 24: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

ENCLOSURE (2)

Steam Generator 12 Indication Report

Calvert Cliffs Nuclear Power Plant, Inc.December 3, 2008

Page 25: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA HP IncCustomer Name: Calvert Cliffs Unit I

3/7/2008 2:18:33 FmComponent: S/G 12 Page 2 of 4

FB Wear Indications (Sort by Row/Col)

QUERY: FB Wear

ROW COL VOLTS

40 16 0.16

41 45 0.2661 85 0.1663 59 0.1466 94 0.11

0.1067 89 0.1668 92 0.1076 90 0.1276 92 0.1283 87 0.1883 91 0.1084 88 0.1284 92 0.2085 59 0.2585 75 0.1385 89 0.1285 91 0.1686 90 0.1387 75 0.1987 77 0.1487 83 0.1288 92 0.16

0.1489 79 0.1589 83 0.1489 91 0.14

0.160.19

90 92 0.1291 75 0.1192 78 0.1992 90 0.12

0.3292 92 0.1292 94 0.1193 71 0.1793 83 0.1893 91 0.1293 95 0.1493 107 0.1694 76 0.13

0.1394 82 0.1294 90 0.1394 92 0.12

0.1595 79 0.1495 81 0.1895 83 0.1796 88 0.1296 90 0.1397 81 0.1497 63 0.19

0.1297 91 0.1698 72 0.1598 76 0.1498 82 0.1498 84 0.1098 90 0.1399 75 0.1299 79 0.1599 83 0.09

0.120.12

99 87 0.1299 89 0.17

0.1299 93 0.1299 95 0.15100 78 0.16100 90 0.18101 75 0.14101 83 0.18101 91 0.13

0.1310o 93 0.17102 76 0.17102 78 0.12

Indications by row

DEG CHN

99 P3

116 P398 P30 P3132 P3109 P392 P387 P3137 P373 P3129 P3129 P385 P316 P3102 P360 P3110 P358 P3113 P3131 P3137 P30 P344 P349 P3118 P30 P394 P354 P395 P3104 P3127 P3123 P3142 P3121 P533 P353 P3125 P30 P3107 P390 P3158 P3103 P3128 P3128 P395 P3108 P3107 P3129 P3131 P30 P3111 P385 P3141 P30 P30 P396 P3131 P384 P3100 P30 P3120 P3118 P3120 P30 P30 P30 P3141 P3122 P380 P3117 P3127 P3111 P3122 P3121 830 P349 P349 P3122 F399 P3113 P3

IND %TW

TWO 15TWO 12TWD 8TWO 6TWD 11TWO 10TWO 7TWO 6TWO 6TWO 7TWo 8TWO 10TWO 6TWO 11T•oD 19TWO 6TWD 6TWO 9TWO 6TWD 16TWO 13TWO, 12TWO 9TWo 8TWO 6TWO 7TWO 8TWO 9TWD 11TWO 11TWO 10TWO 8TWD 6TWO 10TWO 7TWO 6TWO 14Two 9TWo 7TWO 8TWO 13TWo 6TWD 6TWO 5TWO 6TWD 6TWO 8TWD 13TWO 15TWO 15TWD 6TWD 6TweD 6TWO 9TWD 6TrD 9TWO 13TWO 6TWO 6TWO 10TWO 6TWO 11TWO 14TWO 10TWO 12TWD 12TWO 6TWO 8TWO 6TWO 12TWO 13TWO 7TWO 8TWO 6TWV 9TWO 8TWO 8TWO 10TWO 7TWO 11

LOCATION EXT EXT 0TIL 1m - -

P06r07F09Flor07F`07F07r08

F07P08

r07FroF07FOBF11F05F07F07r07Fo6F08r07F08P05P08P07F06P08F07F0.7P0.770.7roeP0?

F07F06r08707F07

r07

F06r06F0?708F07P07107F06F07F07F07To?

F07F06F07F07r06r07FosT07F06707

708F07F07r06r06F07r07F06

Fos

107r07

F07106F07F06F06

+0.71-1.22-1.03+2.65+1.94+0.88+1.30+0.74-1.95+0.78+1.77-0.91-1.93+0.78+1.36+0.78+2.22-0.76-1.95+1.74+1.71+0.48+0.76+1.88+0.74+0.44+1.84+0.73-1.82-1.91+1.76-1.82-1.88+1.25+0.78+1.84-1.79+0.46+1.77+0.82+0.11+0.72-1.76-1.87-1.94+0.80+1.94+1.7841.78+0.44+1.79-1.92+1.7540.4840.39+0.76-1.94-1.8040.70-1.93-1.95,1.76+1.76+0.51-0.60-0.66+0.71-1.39+0.78+0.87-1.89-1.84-1.90+1.80+0.44+0.69-1.84+0.82-1.89-1.82

TEC TERTEC TERTEC TEETEC TERTEC TEETEC TERTEC TERTEC TEETEC TERTEC TEITEC TEETEC TEHTEC TERTEC TEITEC TEETEC TEETIC TEHTIC TERTEC TERTEC TERTIC TERTEC TERTEC TEITEC TERTEC TEITEC TERTEC TERTEC TENTIC TERTEC TERTEC TEITEC TEITEC TEITEC TEETEC TEITSC TEITEC TEITEC TENTEC TERTEC TENTEC TERTEC TERTIC TEITEC TEITEC TERTEC TEHTEC TEITEC TERTEC TINTEC TENTEC TEITEC TEETEC TERTEC TERTIC TENTEC TEITEC TERTEC TEITEC TERTEC TEITEC TERTEC TEITEC TEITEC TERTEC TEHTEC TERTEC TEITEC TERTEC TEITEC TERTEC TENTEC TEITEC TEITEC TERTEC TEITEC TEITEC TEITEC TERTEC TERTEC TER

CTEL 2 CAL # LEG

9 HOT46 HOT16 HOT10 NOT

LAR 17 NOTLAR 17 HOT

19 HOT18 HOT19 ROT18 ROT19 NOT

LAR 17 HOT19 NOT18 ROT9 HOT14 NOT19 NOT18 NOT19 NOT13 NOT13 NOT

LAR 5 NOT18 HOT18 ROT14 HOT6 NOT18 NOT18 NOT18 H0o"

LAR 17 nOT13 ROT14 NOT19 sOT19 HOT18 HOT18 BOT

LAR 11 nOT6 NOT18 NOT18 ROT

LAR 15 NOT14 NOT14 NOT14 NOT19 HOT39 NOT39 HOT13 HOT13 NOT5 ROT19 HOT19 ROT14 HOT6 NOT6 HOT18 ROT

LAR 11 NOT14 HOT14 NOT

LAR 5 HOT19 NOT

LAR 13 HOTLAR 13 NOTLAR 5 HOTLAR 5 HOTLAR 5 HOT

19 HOT19 NOT19 NOT

LAR 17 HOTLAR 17 HOT

14 NOT19 NOT14 HOT6 HOT18 HOT18 NOT

LA 18 NOT14 HOT

LA. 13 HOT

PROBE

6200U

6200L62001620UL62001620UL6200162001620016200L6200L620UL620CL620CL6200L620CL620CL620CL6200L620CL620C1620CL620CL620CL620CL620CL620CL620Th620t'L620VL620CL620VL620VL620EtL620VL620UL620UL620VL620CL620UL6201CL62CUL620CL620UL620UL620UL620UL620UL620UL620UL620UL620UL620UL620UL620UL6201L620UL6201CL62001L620UL6203162OUL,6201L620316207L6201L62031620:16203162031620316203L62001620T16203L6201L6201L6201L62071

Page 26: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

A w Inc 3/7/2008 2:18:33 PH

Customer Name: Calvert Cliffs Unit 1 Component: S/G 12 Page 3 of 4

FB Wear Indications (Sort by Row/Col)

OCERY: F3 Wear Indications by rov.qry

ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL 4 LEG FROSE

102 82 0.24 139 P3 TWO 10 P06 -1.79 TEC TEE 14 SOT 620UL

102 86 0.12 125 P3 TWO 6 r06 -0.76 TEC TER 19 HOT 620tL

102 88 0.15 108 P3 TWD 14 F06 +0.72 TEC TER 39 HOT 620UL

103 73 0.11 141 P3 TWO 10 r07 +1.61 TEC TEN 11 HOT 62001L

103 75 0.17 129 P3 TWO 15 r07 +1.72 TEC TEE LAP 13 ROT 620VL

103 '9 0.22 141 P3 TWO 18 F07 41.69 TEC TER 13 HOT 620V5

0.23 133 P3 TWo 18 P06 -0.89 TEC TEE 13 HOT 620VL

103 81 0.35 128 P3 TWD 23 F07 +1.87 TEC TER LAR 13 HOT 620CL

0.11 127 P3 TWD 10 F06 -0.80 TEC TER LAP 13 SOT 6200'7

103 83 0.24 0 P3 TWD 19 P06 +0.42 TEC TER 5 HOT 62007.

103 85 0.16 145 P3 TWD 13 r07 -0.87 TEC TEE LAR 15 NOT 620v1.

103 89 0.16 108 P3 TWD 7 P07 +0.76 TEC TEN 19 ROT 620UL

103 91 0.15 134 P3 TWD 13 P07 +0.74 TEC TEN LAIR 17 HOT 620UL

0.19 102 P3 TWD 16 F06 -1.95 TEC TER LAR 17 ROT 620VL

104 72 0.13 116 P3 TWO 6 P06 -1.65 TEC TEN 12 HOT 620UL

104 76 0.14 141 P3 TD 13 P06 -1.85 TEC TEE 13 ROT 620VL

104 78 0.20 134 P3 TWO 9 F07 +0.71 TEC TEE 14 HOT 6200L

104 80 0.14 141 P3 TWO 13 P06 -1.78 TEC TEE 13 HOT 620UL

104 82 0.12 118 P3 TWO 11 r06 -1.91 TEC TER LAR 13 HOT 620U0

104 84 0.26 0 P3 TWO 12 P06 +1.23 TEC TER LAR 6 HOT 620UL

104 88 0.19 127 P3 TWO 8 F07 -1.95 TEC TEE 19 HOT 620UL

104 90 0.19 135 P3 TWO 9 F07 -1.86 TEC TER 19 HOT 620UL

104 94 0.16 105 P3 TWO 9 F07 +1.99 TEC TEE 18 HOT 620UL

105 83 0.27 0 P3 TWO 13 F07 -0.57 TEC TEE 6 HOT 620UL

0.27 0 P3 TWD 13 F06 -0.59 TEC TEE 6 ROT 6200UL

105 85 0.19 111 P3 TWO 9 P07 +0.69 TEC TEE 16 NOT 620UL

0.09 60 P3 TWO 5 F06 -1.82 TEC TEE 16 ROT 620UL

105 87 0.19 114 P3 TWD 9 r07 +0.67 TEC TER 19 HOT 62007

105 89 0.57 136 P3 TWO 21 F07 +1.30 TEC TER LAR 19 ROT 62001L

105 91 0.14 83 P3 TWO 8 P07 +0.73 TEC TEN 18 HOT 6201.L

0.16 68 P3 TWO 9 F06 -1.92 TEC TEH 18 HOT 620UL

105 93 0.13 53 P3 TWO 8 F07 +0.82 TEC TEN 18 ROT 620UL

106 76 0.22 128 P3 TWO 9 r07 +0.69 TEC TER 14 HOT 620U0

106 78 0.13 138 P3 TWO 12 F07 +0.74 TEC TER 13 NOT 620UL

106 82 0.19 114 P3 TWo 8 F07 +0.63 TEC TEE 14 HOT 620UL

0.14 117 P3 TWD 6 P06 -1.93 TEC TEB 14 HOT 620u0

106 84 0.09 0 P3 TWD 10 F06 -0.80 TEC TEE LAR 5 HOT 620UL

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

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

106 94 0.08 106 P3 TWO 9 P07 +1.86 TEC TEN 38 HOT 620UL

107 77 0.21 127 P3 TWO 17 F06 -0.74 TEC TER 13 HOT 620UL

107 83 0.19 0 P3 TWO 16 F07 -0.59 TEC TEE 5 ROT 620UL

0.31 0 P3 Two 22 706 +0.46 TEC TER LAR 5 NOT 6201.L

107 85 0.29 146 P5 TWO 11 F07 -1.50 TEC TEN LA.R 15 HOT 620U1

107 89 0.16 120 P3 TWO 7 F07 +0.76 TEC TER 19 HOT 620UL

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

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

108 84 0.13 0 P3 TWO 6 P06 -0.75 TEC TEN 6 SOT 620UL

0.21 0 P3 TWO 10 r07 +1.59 TEC TEE LAR 6 NOT 620UL

0.20 0 P3 TWo 10 706 +1.21 TEC TER LAR 6 HOT 620UL

108 86 0.31 117 P5 TWD 10 F05 -1.32 TEC TER 19 HOT 620UL

108 88 0.15 121 P3 TWo 7 r07 -1.82 TEC TER 19 NOT 62001

0.18 120 P3 TWO 8 F06 -0.82 TEC TEN 19 HOT 620WL

109 79 0.18 130 P3 TWO 0 F06 -0.80 TEC TEN 14 HOT 6200L

109 83 0.13 0 P3 TWO 7 P06 +0.45 TEC TEE 6 HOT 62071

109 89 0.18 133 P3 TWD 8 F0? +0.76 TEC TEE 19 SOT 6203L

110 78 0.13 59 P3 TWO 12 F07 +0.74 TEC TEN 13 HOT 6201L

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

0.40 118 P3 TWO 16 F06 -0.76 TEC TEN 19 HOT 6207L

110 88 0.17 102 P3 TWO 8 F07 +1.86 TEC TER 19 HOT 6207L

110 90 0.16 140 P3 TWO 7 P07 -1.43 TEC TEN 19 HOT 62071L

110 92 0.16 128 P3 TWD 8 F06 -0.87 TEC TEE 39 ROT 6207L

111 79 0.14 127 ?3 TWD 13 F07 +1.78 TEC TEE LAR 13 ROT 62077.

0.16 140 P3 TWO 14 F06 -0.87 TEC TEE LAP 13 HOT 62037

111 85 0.17 122 P3 TWO 14 F07 +0.72 TEC TEN LAP 15 SOT 6203L

I11 87 0.22 110 P3 TWO 10 F07 +0.69 TEC TER 19 HOT 6203L

111 89 0.64 129 P3 TWO 23 F07 +1.23 TEC TER LAR 19 HOT 62077L

112 78 0.12 123 P3 TWO 5 207 +0.74 TEC TEE 14 ROT 62077.

112 90 0.19 151 P5 TWO 6 F05 +1.17 TEC TER 19 HOT 62071L

113 83 0.17 0 P3 TWO 15 F06 40.42 TEC TEH 5 ROT 6203L

113 67 0.13 90 P3 TWO 6 P07 +0.76 TEC TEN 19 HOT 6203L

114 76 0.10 99 P3 TWO 4 706 -1.75 TEC TER 14 ROT 62071

114 80 0.15 100 P3 TwO 7 706 -1.89 TEC TER 14 NOT 62071L

114 92 0.08 90 P3 TWO 8 PO6 +1.71 TEC TEE 38 HOT 62071.

115 83 0.13 0 P3 TWD 12 P06 +0.48 TEC TEE 5 HOT 6200L

115 85 0.16 105 P3 TWO 13 Po7 +0.69 TEC TER LAR 15 HOT 620UL

115 87 0.18 98 P3 TWO 8 P07 +0.71 TEC TEE 19 ROT 620UL

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

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

116 86 0.17 113 P3 TWO 8 F07 +1.73 TEC TER 19 HOT 620UL

Page 27: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVX NP Inc 3/7/2008 2:18:CuStomer NaMe: Calvert Cliffs Unit 1 Component: S/G

FB Wear Indications (Sort by Row/Col)

QUERY: FB Wear Indications by row.qry

ROW COL VOLTS DEG CdN IWNO %TW LOCATION EXT EXT UTIL I

0.19 98 23 TWO 9 F06 -0.76 TEC TER116 88 0.16 112 23 TWO 7 F06 -0.82 TEC TER116 92 0.17 92 P3 TWO 10 F06 +1.77 TEC TEE117 79 0.11 136 P3 TWO 5 F07 +1.78 TEC TEE117 89 0.17 135 73 TWO 8 F07 +0.67 TLC TER118 76 0.13 117 P3 TWD 6 F06 -1.84 TEC TER120 80 0.19 138 P3 TWo 16 r07 -1.80 TEC TEE120 84 0.15 0 P3 TWO 14 F06 -0.86 TEC TEE121 85 0.26 114 P3 TWO 12 E06 -1.93 TEC TEE121 87 0.12 121 P3 TWO 6 F07 +0.72 TEC TEE123 87 0.10 153 P3 TWD 5 F07 +0.72 TEC TEE128 80 0.20 137 P5 TWO 7 F06 -1.39 TEC TER

:34 P4; 12 Paqe 4 of 4

UTIL 2 CAL 0 LEG

19 HOT19 HOT

LAP. 18 HOT14 NOT19 HOT14 HOT

LAR 13 HOT5 ROT26 HOT19 HOT19 ROT13 HOT

620U-,620m

620OZ620U16200L620M.62001620V.6200•6200L620U'.620CU

Total Tubes : 144Total Records: 172

Page 28: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

9

AREV1 NP IncCustomer N~ame: Cal7ert Cliffs Unit I

3/712008 2:19:04 PMComponent: S/G 12 Paqe 2 of 2

Lattice Support Wear Indications

QUERY: TSP Wear Indications

ROW COL VOLTS DEC CIO INO %TW

122 86 0.20 129 P3 Two 9134 68 0.15 118 P3 TWO 14

LOCATION

07C +1.0702H -1.53

EXT EXT UTIL 1 UTIL 2 CAL I LEG

TEC TER LAR 19 ROTTEC TER LAR 1 ROT

PROBEK

62OUL62011L

Total Tubes : 2Total Records: 2

Page 29: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

hREvA tP Inc 3/7/2008 2:17:15 PMCustomer Name: Calvert Cliffs Unit 1 Component: S/c 12 Page 2 of 2

NOI Indications

QUERY: NQI Indications

ROW COL VOLTS DEG C824 IND 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 : 1Total Records: 1

Page 30: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

ARMV nP Inc 3/7/2008 2:19:55 PMCustomer Name: Calvert Cliffs Unit 1 Component: S/G 12 Page 2 of 2

DFS/DFH indications

QUERY: DFrHDYS Indications

ROW COL VOLTS DFO C.HN flD %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 620UL60 74 0.26 152 5 DFS 05 +32.78 TEC TER LAR 13 HOT 620UL79 139 0.30 153 5 DFH 0lC +9.55 TEC TE. LAR 41 HOT 620UL

Total Tubes : 3Total Records: 3

Page 31: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP IncCustomer Name: Calvert Cliffs Unit I

3/7/2008 2:19:33 PHComponent: S/G 12 Page 2 of 2

WAR Indications

QUERY: WAR Zndication3

ROW COL VOLTS DEG CHN IND

85 59 0.25 77 P5 WAR87 75 0.18 111 P5 WAR103 79 0.21 108 P5 WAR

0.21 108 P5 WAR103 81 0.29 100 PS WAR103 83 0.20 107 P5 WAR103 91 0.21 100 P5 WAR105 89 0.31 106 P5 WAR106 134 0.14 71 P4 WAR107 77 0.22 103 P5 WAR107 83 0.19 103 P5 WAR

0.23 106 P5 WAR108 82 0.19 119 P5 WAR110 86 0.28 107 P5 WAR111 89 0.39 102 P5 WAR120 80 0.19 83 P5 WAR122 86 0.14 85 PS WAR134 88 0.18 82 P4 WAR

0.18 86 P4 WAR

%TW LOCATION EXT EXT UTIL 1 UTIL 2

F07 +1.46 F07 to7 22r07 +1.83 r07 F07 17F06 -0.79 F07 F06 19r07 +1.80 P07 F06 19r07 +1.87 F07 F07 24FOG 40.49 F06 F06 18F06 -1.75 r07 F03 19F07 +0.98 r07 F07 25TSH +7.18 TSH 01R 10F06 -0.71 T06 F06 20F06 +0.21 r0o F06 18F07 -0.50 r08 F06 20F06 -1.80 F06 F06 18

F06 -0.87 F06 P06 24F07 +1.01 r07 r07 29F07 -1.83 P07 V07 1807C +1.08 07C 07C 1402H -1.54 01H 02H 1302B -1.55 01R 03H 12

CAL I LEG

34 HOT34 HOT34 HOT34 HOT34 HOT34 HOT34 HOT34 HOT37 HOT34 BOT34 HOT34 HOT34 HOT34 HOT34 HOT34 HOT.34 HOT37 HOT36 HOT

PRO13E

56072560??560?P5602P560??5602?5607P5602P610?P560?P560?P560?P560?P560?P5607?560?P560?P6107P610?P

Total Taube : 16Total Records: 19

Page 32: Constellation Energy- Nuclear Generation GroupUnit I Steam Generator Tube Inspection. In Reference (b), the Nuclear Regulatory Commission requested additional information to be submitted

AREVA NP ZncCustomer Name: CalveOt Cliffs Unit 1

DNG Indications

QUERY: DNG IndLcations

ROW COL VOLTS DEG CHN IND %TW LOCAT

18 164 5.48 186 P1 DNG t0.38 86 1.00 185 PI ONG 05H102 28 5.22 181 P1 DNG rlo117 41 3.72 183 P1 DNG F09

2.16 183 P1 DNG F07120 44 2.92 181 PI DXG F07

3/7/2008 2:16:27 PMCorponent: S/G 12 Page 2 of 2

ION EXT EXT UTIL 1 UTIL 2 CAL# LEC

40.46 TEC TEE HR 4 ROT+22.77 TEC TEE 47 HOT-0.90 TEC TER 8 HOT-1.18 TEC TEE 6 HOT-1.29 TEC TER 6 HOT-0.83 TEC TEE 8 HOT

PR03E

620"L62037620UL620UL6201!L6200L

Total Tubes : 5Total Records: 6


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