LIC-04-0040, (FCS) Steam Generator Eddy Current Test Report - 2003 Refueling Outage

(FCS) Steam Generator Eddy Current Test Report - 2003 Refueling Outage

ML040910288
Person / Time
Site:	Fort Calhoun
Issue date:	03/26/2004
From:	Phelps R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-04-0040
Download: ML040910288 (19)

Text

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Oraha Public Power Distct 444 South 16th Street Afall Omaha NE 68102-2247 March 26, 2004 LIC-04-0040 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Fort Calhoun Station (FCS) Steam Generator Eddy Current Test Report -

2003 Refueling Outage Pursuant to FCS Unit No. 1 Technical Specification 3.17(5)(ii), Omaha Public Power District (OPPD) submits the attached FCS Steam Generator Eddy Current Test Report which summarizes testing performed during the Fall 2003 Refueling Outage.

If you have any questions or require additional information, please contact Dr. R. L. Jaworski at (402) 533-6833. No commitments are made to the NRC in this letter.

Sincerly R. L. Phelps Division Manager Nuclear Engineering RLP/JKM/rrl

Attachment:

Fort Calhoun Station Steam Generator Eddy Current Test Report, 2003 Refueling Outage c: B. S. Mallett, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector Employment with Equal Opportunity

LIC-04-0040 Attachment Page 1 ATTACHMENT FORT CALHOUN STATION STEAM GENERATOR EDDY CURRENT TEST REPORT 2003 REFUELING OUTAGE

LIC-04-0040 Attachment Page 2 FORT CALHOUN STATION STEAM GENERATOR EDDY CURRENT TEST REPORT 2003 REFUELING OUTAGE INTRODUCTION This report summarizes steam generator eddy current test results obtained during the Fort Calhoun Station (FCS) 2003 Refueling Outage (RFO). Omaha Public Power District (OPPD) submitted summaries of results of the previous eddy current inspection to the NRC in the following documents:

1. Fort Calhoun Station (FCS) Steam Generator Eddy Current Test Report - 2002 Refueling Outage, dated December 3, 2002 (LIC-02-0139)

2. Fort Calhoun Station Steam Generator Report (TAC No. MB6954) Response to Request for Additional Information, dated July 30, 2003 (LIC-03-0100)

Description of FCS Steam Generators The Fort Calhoun Station is a two-loop Combustion Engineering design Nuclear Steam Supply System (NSSS). Each steam generator contains 5005 vertical tubes fabricated from Alloy 600 material. The tubes are nominally 0.750 inch outside diameter with a nominal tube wall thickness of 0.048 inches, and are installed in the tubesheet in a 1-inch pitch, triangular array. The tube to tubesheet joints are full tubesheet depth explosively expanded and are seal welded at the primary face of the tubesheet. The operating temperature (That) is 5930 F.

All tube supports in the FCS steam generators are carbon steel material. With the exception of the upper most support, all supports of the vertical tube run are of the eggcrate lattice type with drilled tube hole Drilled Support Plates at the 90 degree and 270 degree orientations. The upper most support at elevation 8 is a partial plate with drilled tube holes. Tube holes in drilled supports are 0.765-inch diameter (nominal) providing a nominal annular clearance around the tubes of 0.0075 inch. Drilled plate support segments include 0.25 inch drilled flow holes nominally in the center of each triangular array of three tubes. Of the 5005 tubes in each steam generator, 975 tubes pass through one or more one-inch thick drilled plate supports. The remainder is supported totally by eggcrate lattice support structures. The eggcrate structures are fabricated from interlocking 0.090-inch thick strips of alternating 2 inch and 1 inch widths. The eggcrate supports provide a robust structure, while at the same time providing an open configuration with minimum flow resistance.

Freedom of flow through the area adjacent to the tube increases the flushing capability to reduce potential for deposit loading.

The horizontal sections of the double 90-degree U-bends are supported by three vertical strips welded to diagonal strips, which pass nominally through the center of the 90-degree bends. The vertical and diagonal strip subassemblies serve as spacers between each line of tubes. The vertical and diagonal strips are 0.090 inch thick and 4 inches wide. The vertical strips are connected to three horizontal,

LIC-04-0040 Attachment Page 3 structural I-beams, which in turn are connected to the tube bundle shroud. Additionally, 1-inch thick horizontal scalloped bars pass between each row of tubes and interlock with the vertical strips to provide a rigid structure designed to resist postulated accident induced loads.

The FCS steam generators have operated for 30 years and accumulated 22.33 EFPY by the 03RFO outage. Before the 2003 Outage, 533 tubes had been plugged which is less than 5.4 % of the total number of original tubes.

FCS steam generator support notations referenced throughout this report can be found on Figure-1.

Scope of Examination Westinghouse conducted in-service nondestructive examinations of the steam generator (SG) tubing at Omaha Public Power District's Fort Calhoun Station Nuclear Power Plant in September and October of 2003. The examinations were performed to assess the condition of the Steam Generators, identify tubes requiring repair, and to provide the necessary information needed to fulfill Technical Specification requirements.

The examination program included multi-frequency bobbin testing for indications of degradation or dents and motorized rotating probe coil (MRPC) Plus Point testing for axial and circumferential cracking and further evaluation of detected bobbin indications.

The eddy current data was acquired using the Westinghouse's ANSER Data acquisition software.

The data was reviewed by qualified data analysts (QDA) for data quality and converted to Zetec's Eddynet& format for final data analysis. The converted eddy current was transmitted from the site by T-1 data lines to the Westinghouse (primary analysis) data room at the Waltz Mill facility in Madison, PA and the Verner & James (secondary analysis) data room in Snoqualmie, WA where it was independently analyzed by these two groups of analysts. In addition to the primary and secondary analysis, Verner & James preformed a tertiary analysis on the Bobbin Data by using Computerized Data Screening (CDS). This third analysis was to screen for large indications which minimizes the possibility of missing a significant flaw due to human error. Analysis results were then transmitted to Fort Calhoun where discrepancies between the production analyses were resolved by two groups of Level III Resolution Analysts representing primary and secondary analysis groups.

All data analysts were certified to a minimum of ECT Level IIA, QDA certified (EPRI Qualified Data Analyst) and successfully passed a practical examination specific to Fort Calhoun Station steam generators. Data Analysts received familiarization training on the data during the Data Analyst Indoctrination, lessons learned from Comanche Peak were incorporated in the introduction. Optical disks with data from Fort Calhoun, similar CE plants, and Indian Point Unit 2 were also available for review. Data analysts were qualified by proficiency examination on Fort Calhoun data and supplementary data from Comanche Peak, Maine Yankee and Indian Point Unit 2 for damage mechanisms not detected to date at Fort Calhoun.

In addition to OPPD's Steam Generator Program Manager, OPPD was represented by two (2) ECT Level III, from MoreTech. They performed as Independent QDAs, who were not part of the Primary, Secondary, or Resolution analysis teams. These analysts were responsible for review, comments and

LIC-04-0040 Attachment Page 4 changes to the Analysis Procedure, and for review of all acquisition and analysis technique sheets.

The Independent QDAs reviewed all "I" codes which had been dispositioned to NDD by the Resolution team. They were also responsible for randomly sampling inspection results to ensure proper disposition of resolved indications, to ensure proper reporting, to review repairable indications, and to review and disposition calls which were contested by either the Primary or Secondary analysts. The functions of these Independent Level III's positions were in accordance with EPRI PWR Steam Generator Examination Guidelines, Revision 6.

In addition to the eddy current data acquisition and data analysis' personnel a Tube Integrity Engineer, a Condition Monitoring consulting Analyst, a data sizing analyst, and an Independent Technical Reviewer were part of the Steam Generator inspection team.

To aid in the disposition and characterization of eddy current signals ultrasonic testing was performed on 12 indications in 7 tubes.

The Inspection Plan listed below was developed from the Degradation Assessment (DA) for the 2003 Outage. The DA identified the following Existing Degradation Mechanisms at FCS: Tube Support Denting, Loose Part Wear, Volumetric Indications, Pitting, Circumferential, Outside Diameter Stress Corrosion Cracking (ODSCC) at; Expansion Transitions, Drilled Plate Supports, Axial ODSCC at; Top of Tubesheet (Sludge Collar), Drilled Support Plate Intersections, Dented Eggcrates, Free Span Critical Area, Free Span and Non-dented Eggcrates and Axial PWSCC at Tube Supports.

Potential Degradation Mechanisms include: Mechanical Wear at Tube Supports Axial ODSCC at Dings, U-Bend Cracking, ODSCC at 90 Degree Bends, PWSCC in Tubesheet Expansion Transitions, Tubesheet Crevices Cracking, and Cracking at the Tube Ends of Expanded Tubes.

Bobbin Probe:

100% of all open tubes were tested with a 0.560-inch diameter bobbin probe. Tubes restricted to the 0.560-inch diameter probe were tested from both hot and cold side as far as possible. The restricted region was tested with. Plus Point@. If the full length of a tube could not be completely inspected by a combination of the 0.560 bobbin probe and MRPC Plus Pointe it would have been plugged. No tubes required plugging for an incomplete inspection. Bobbin testing was conducted to detect:

Support Denting, Loose Part Wear, Volumetric Indications, Pitting, Axial ODSCC at Non-dented Eggcrates, Free Span, Top of Tubesheet (Sludge Collar), Dings < 5 Volts, Mechanical Wear at Tube Supports and Axial PWSCC at Supports.

Motorized Rotating Probe Coil (Plus Pointe):

100% of tubes at the Hot Leg Top of Tubesheet +3"/-7" were tested for; Circ ODSCC, Axial ODSCC, Volumetric, Mechanical Wear from loose parts, Circ PWSCC, and Axial PWSCC.

100% of Hot Leg drilled support intersections were tested for: Circ ODSCC, Axial ODSCC, Mechanical Wear from loose parts or support structure and Axial PWSCC.

LIC-04-0040 Attachment Page 5 100% of tubes in the Freespan Critical Area from H5 to DBH were tested for Axial ODSCC, Loose Part Wear.

100% of Hot Leg eggcrate supports with dents >3 volts were tested for Circ ODSCC, Axial ODSCC, Mechanical Wear from lose parts or support structure and Axial PWSCC.

100% of Vertical Supports VI, V2, V3, and DBH and DBC with dents > 3 volts were tested for Circ ODSCC, Axial ODSCC, Mechanical Wear from support structure and Axial PWSCC.

100% of Hot Leg square bends in Critical Area were tested for Axial ODSCC at 900 Bends.

100% of Rows 1-2 U-bends were tested with a high frequency Plus Pointg for: Circ PWSCC and Axial PWSCC.

20% of Rows 1-4 U-bends were tested with medium frequency Plus Point for: Circ ODSCC, Axial ODSCC, and Axial PWSCC.

100% of Hot Leg Freespan Dings > 5 volts, were tested for: Circ ODSCC, and Axial ODSCC.

100% of all Bobbin I-codes were tested for: Loose Parts Wear; Volumetric Indications, Pitting, and ODSCC at Expansion Transitions, Drilled Plate Supports, Axial ODSCC at Top of Tubesheet (Sludge Collar), Drilled Support Plate Intersections, Dented Eggcrates, Free Span Critical Area, Free Span and Non-dented Eggcrates and Axial PWSCC at Tube Supports.

20% of indications dispositioned by Plus Point history for confirmation of the validity of Dispositioned by History (DBH) of bobbin calls that have not changed.

Inspection Plan Expansions A 25 tube expansion to the Freespan Critical Area of S/G RC-2A was examined because of an indication in a tube at the edge of the critical area. This expansion met the EPRI Rev. 6 requirement to maintain a buffer zone to a Critical Area as described in section 3.6.2.

A 20% sample of all open tubes that pass through the Cold Leg 8th Drilled support intersection in S/G RC-2B were tested because of Circumferential Indications at the 8 th Drilled support intersection on the Hot Leg side. This expansion was a conservative decision by FCS to insure that the hot leg mechanism was not present on the cold leg.

Inspection Equipment and Techniques Westinghouse Electric Company performed the nondestructive examination (NDE) of the steam generator (SG) tubes. The following components are required to perform eddy current testing: an eddy current tester, a remote positioning device, and an eddy current probe drive control system. The state-of-the-art equipment used at OPPD during the 2003 outage for the eddy current testing (ECT) included the Zetec MIZ-70V digital ECT tester. The Flat Rail GENESIS robot manipulator equipped

LIC-04-0040 Attachment Page 6 with the Vision Tube Locating system is used to position the probe at the tubes. Probes are inserted and withdrawn using a Zetec IOD probe pusher equipped with a Westinghouse probe encoders and the Westinghouse Single Probe Pusher Control (SPPC) system. The software that was used for acquisition was the Westinghouse's ANSER Data Acquisition software. The raw data was converted to Zetec's Eddynet980 for data analyst and interpretation.

The ECT probes used included a standard bobbin probe (A56OMIULC), beaded combo probe (A560 M/IJLC/C) and spring flex bobbin probes (A560SFRM) for the full-length and partial length inspections. Due to the support denting that occurred in the initial few cycles of operation downsized bobbin probes are used for the examination. A 0.560 inch diameter probe has been used for approximately 97% of the tubes which provides a fill factor of 73%. In past outages a .540 inch diameter probe was used for the remaining bobbin exams. Because the diameter of the probe is reduced there is inherently more probe wobble which produces a horizontal signal response that can mask small amplitude dents. The 3 volt reporting threshold was selected in 1998 as that level at which a dent could be reliably differentiated from probe wobble. This outage only .560 inch diameter probes were used at FCS as described in Reference 2 (LIC-03-01 00).

The frequencies used for the bobbin examination are as follows:

400 kHz differential and absolute 200 kHz differential and absolute 100 kHz differential and absolute 35 kHz differential and absolute 400/100 kHz differential support ring mix 400/100 kHz absolute support ring mix The primary frequency of 400 kHz satisfies the requirements of the ASME Boiler and Pressure Vessel Code for the examination of nonferromagnetic steam generator tubing. A technique using the differential support mix and a voltage base of 2.75 volts on the 20% outer diameter (OD) ASME signal was used to perform dent sizing consistent with current industry techniques. The 100 kHz is provided for the confirmation of flaw indications and as a frequency used in the mixes to eliminate support and OD deposit signals. The 100 kHz absolute detects gradual wall thickness variations.

The 200 kHz frequency is for confirmation of flaw indications. The 35 kHz is provided to facilitate locating the probe position in the steam generator. The 400/100 kHz differential mix is used to eliminate the tube support signal and OD tube deposits. The 400/100 absolute mix is used to detect gradual wall loss. Bobbin exams were conducted to conform to EPRI Rev. 6 Appendix H ETSS #s 96008.1 Rev. 13, 96005.2 Rev. 8, 96012.1 Rev.9, 96004.1 Rev.9 and Westinghouse document # SG-99-03-005, Appendix H, Certification of Bobbin Coil Detection Performance in Freespan Dings South Texas Project, dated March 1999.

Three coil motorized rotating coils were used at the hot leg top-of-tubesheet and to investigate bobbin indications. Various versions of the rotating coil probe were used to inspect the vertical runs, horizontal runs, and square bend sections as required. Low row U-bends were also inspected with rotating coil technology.

LIC-04-0040 Attachment Page 7 Top-of-Tubesheet examinations were conducted to conform to EPRI Rev. 6 Appendix H ETSS #s 21409.1 Rev.2, 21410.1 Rev.3, 20510.1 Rev.4, and 20511.1 Rev. 6. The frequencies used for the three coil (P1 15A, PPI lA, P080B), Top-of-Tubesheet examinations are as follows:

400 kHz Pancake, Mid-Freq. Plus Point coil, and High-Freq. Pancake coil 300 kHz Pancake, and Mid-Freq. Plus Point coil 100 kHz Pancake, and Mid-Freq. Plus Point)coil 700 kHz High-Freq. Pancake coil 20 kHz Pancake, and Mid-Freq. Plus Point Coil Plus Point exams were conducted to conform to EPRI Rev. 6 Appendix H ETSS #s 21409.1 Rev.2, 21998.1 Rev. 2, 22841.3 Rev. 3, 22842.3 Rev. 3, and 96703.1 Rev. 13. The frequencies for the two coil (2-PP 1lA) modular probe were as follows:

400 kHz High-Freq. Plus Pointcoil 300 kHz High-Freq. Plus Pointcoil 100 kHz High-Freq. Plus Pointcoil 20 kHz High-Freq. Plus Pointcoil Plus Point exams were conducted to conform to EPRI Rev. 6 Appendix H ETSS #s 21409.1 Rev.2, 21998.1 Rev. 2, 22841.3 Rev. 3, 22842.3 Rev. 3 and 96703.1 Rev. 13. The frequencies for the 2 coil (P1 15A, PPI lA) Flex probe MRPC examinations were as follows:

400 kHz Pancake, and Mid-Freq. Plus Point coil 300 kHz Pancake, and Mid-Freq. Plus Point Coil 200 kHz Pancake, and Mid-Freq. Plus Point coil 100 kHz Pancake, and Mid-Freq. Plus Point coil 20 kHz Pancake, and Mid-Freq. Plus Point Coil Plus Point exams were conducted to conform to EPRI Rev. 6 Appendix H ETSS #s 96511.1, 96511.2 Rev. 13. The frequencies used for the single coil (PP11A) mid-frequency U-bend examinations were as follows:

400 kHz Mid-Freq. Plus Point coil 300 kHz Mid-Freq. Plus Point coil 200 kHz Mid-Freq. Plus Point coil 100 kHz Mid-Freq. Plus Point coil 20 kHz Mid-Freq. Plus Point coil Plus Point exams were conducted to conform to EPRI Rev. 6 Appendix H ETSS # 99997.1 Rev. 7.

The frequencies used for the single coil (PP9A) high frequency U-bend examinations were as follows:

800 kHz High-Freq. Plus Point coil 600 kHz High-Freq. Plus Point coil

LIC-04-0040 Attachment Page 8 400 kHz High-Freq. Plus Pointy coil 300 kHz High-Freq. Plus PointV coil The recorded multi-frequency eddy current data is analyzed by two independent teams of data analysts for the presence of flaw indications and dents. Discrepancies between the two sets of evaluation results are reviewed and dispositioned by the resolution analysts. Primary and secondary analyst feedback was accomplished through the use of the Analyst Performance Tracking Software.

The primary and secondary analysts were required to review all missed calls and a sample of overcalls. If there were any calls which were dispositioned as requiring no further action by the resolution team which the primary or secondary analyst felt should have remained, that analyst could appeal the call and the appeal was then assigned to the independent Level III QDA for final disposition.

The bobbin probe is used primarily as a screening tool to flag indications for further evaluation by means of historical reviews and/or additional testing with rotating coil technology. All of the data for all examined regions was analyzed. Indications left in service have been determined to be either non-reportable or manufacturing related through the use of diagnostic testing and historical reviews.

Indications were not left in service based on depth sizing estimates.

Bobbin testing was performed mainly from the outlet side of each S/G. Bobbin test speeds ranged from 12" to 36" per second and varied depending on presence of dents or low row diameter restrictions. Bobbin test sampling rates were within the requirements of the EPRI Appendix H approved techniques. The .560 diameter probe was used on all open tubes; some tubes could not be tested full length with the bobbin coil because of restrictions (dents). Any tube with a restriction was tested to the extent possible from both, outlet and inlet sides, any area that could not pass the bobbin coil was tested with Plus Point& MRPC probe.

MRPC test speeds also varied depending on test location and probe type. Test speeds were from .1" to .7"/second axially with the sampling rate adjusted in accordance with EPRI Appendix H Qualified Techniques as detailed in analysis procedure.

Inspection Results The #s and locations of each type of indication found are summarized in Table 1. Definitions of indication acronyms can be found in the Appendix. All pluggable indications are reported in Tables 2 and 3. Depth estimates were made only on pluggable indications for the purpose of providing input to assessments of overall steam generator condition. No tubes were left in service on the basis of sizing.

As a result of the inspection, several conclusions can be derived as follows:

Single Axial Indications (SAI) and Multiple Axial Indications (MAI) are linear indications that are parallel to the length of the tube or axially oriented. There were 112 SAI (45 in S/G RC-2A and 67 in S/G RC-2B) and 2 MAI (both in S/G RC-2B) reported by the data analyst at various elevations of both steam generators. 67 of the indications were "freespan" (FS) or between supports, 20

LIC-04-0040 Attachment Page 9 indications were at Drilled Support Plates (DSP), 17 indications at Eggcrate (EC) supports structures and 8 indications were within 2 inches of the top of the hot leg tubesheet (HTS). The majority of the indications reside between H5 and H8 in the critical area where the partial tube support plates are superpositioned. Most of these indications were transparent to the bobbin coil and were detected with the more sensitive rotating Plus Point coil. The deepest indication which was not detected by the bobbin coil was 55% as sized by Plus Point amplitude. This indication was at a dent where bobbin performance is degraded from liftoff. The deepest indication missed by the bobbin coil where no denting is present was 46%. Historical data reviews from the RFO-02 inspection were conducted by the senior analyst during the course of the RFO-03 examination. Of the 114 indications all were reviewed to determine whether the flaw was present and if so, did it appear to grow. 58 indications showed no growth, 23 showed growth, 13 showed marginal growths. 20 indications which were detected by the Plus Point coil only, could not be reviewed because that area of the tube had not been tested by Plus Point in 2001 or 2002. The number of indications reported in documents, like the Condition Monitoring Assessment (report number SG-SGDA-03-041) and Operational Assessment for Cycle 22 (report number SG-SGDA-04-02), were adjusted; if the ECT graphics indicated that indications were close together axially and co-linear, then they were considered one indication with a size that enveloped the multiple ECT indications.

Single Circumferential Indications (SCI's) are linear indications perpendicular to the length of the tube or circumferentially oriented. 25 SCI indications were reported, (10 in S/G RC-2A and 15 in S/G RC-2B). Two (2) of the indications were at the top of the hot leg tubesheet (HTS), both were in S/G RC-2A. One indication was at the 7th eggcrate support structure in S/G RC-2B. Four (4) indications in S/G RC-2B are considered freespan because they are not encompassed by a support structure. The remaining indications were at various hot leg drilled support plates. Several circumferential indications in S/G B at the 8th drilled support plates appeared to be a series of parallel circumferential cracks over an axial distance nearly the length of the support thickness. The maximum circumferential extent of the HTS indications was 40 degrees and the maximum indicated depth by Plus Point phase analysis was 75% through-wall. The maximum circumferential extent of the drilled support plate indications was 137 degrees and the maximum indicated depth by Plus Point phase analysis was 71% through-wall. Of the 18 SCI indications reported at drilled supports, 14 are associated with a dent from the bobbin coil. The dent voltages range from 3.40 volts to 120.7 volts. Several of the indications showed growth from the last cycle.

Single Volumetric Indications (SVI) are band or patch like indications. 3 SVI's were reported (1 in S/G RC-2A and 2 in S/G RC-2B). All three indications were freespan and showed no change from 2002 data. The indication in S/G RC-2A was located above the fifth hot leg support structure and the two indications in S/G RC-2B were located above the sixth hot leg support structure. This is the region where axial ODSCC occurs and the damage mechanism which produced the ECT indications is presumed to be a patch of inter-granular attack (IGA).

Loose Part With Indication (LPI) is a flaw indication associated with a loose part. 2 tubes in S/G RC-2A were plugged because of wear from loose part like indications.

All of the tubes with the above indications were repaired by plugging. Tubes with circumferential indications were stabilized as well. A total of 42 tubes were plugged in S/G RC-2A and 65 tubes

LIC-04-0040 Attachment Page 10 were plugged in S/G RC-2B, there were 4 additional tubes plugged in both steam generators to facilitate future use of the flat-rail system. A total of 115 tubes were plugged this outage.

In-Situ Pressure Test and Results Insitu pressure testing was performed on one (1) tube in SG RC-2B (Row 94, Line 65, at the H8 Support). The test was performed due to the eddy current detection of multiple layer cracking. One of the indication layers measured 1.07 volts which exceeded initial the leak test screening threshold of 1.0 volts. The tested area withstood the required pressure with no leakage, thereby assuring that the condition monitoring criteria were satisfied. The test was performed in accordance with procedure STD-400-173 titled "Checkout and Operation of the Steam Generator Tube In Situ Pressure Test System" and traveler CFTC1-SG-004 titled "In Situ Pressure Test Using the Computerized Data Acquisition System". Table 4 is a summary of the test and target pressures.

Conclusions Based on the results of the extensive eddy current examination and the in-situ pressure tests performed, OPPD has reached the conclusion that the steam generator tube performance criteria were met for the entire previous operating cycle, and the requirements for conditioning monitoring were fulfilled.

All tubes with identified degradation were plugged. Tubes with circumferential indications were stabilized. No tubes were repaired by sleeving. To date, S/G RC-2A has a total of 308 tubes plugged (6.16%), and S/G RC-2B has a total of 340 tubes plugged (6.8%).

LIC-04-0040 Attachment Page 11 Steam Generator

________ Indication Listin Zby Location____

__ _ _ _ _ _ _ S/G RC-2A __ _ _ _ _ _ S/G RC-2B _ __ _ _

Location SAlI MAT SCI SVI LPI VOL SAI MAI SCI SVI LPI VOL Totals HTS 6 2 2 ____ 2 _ _ 12 HTS+ 1'.- I HI 5 3 5 1 _ _ 14 H2 __ _ _ _ _ _ _ _ _ _ _ _3 1 _ _ 4 H12+ '-0 H3 __ _ _ _ _ _ _ _ _ _2 2 H13+  : _ _ _ _ _ _ _ _ _

H4 __ _ _ _ _ _ _ _2 1 _ _ 3

,1H 4--' _ _ _ __ __ _ _ -2 , _ _ 2  :

115 1 _ _ _ _ _ 7 8 H6 4 2 _ _ 6 _ _ _ _ 12 HA6w+ 3 1 1  ! :__

16 H7 5 2 __ _ _ _ _3 2 __ _ 12 H17+ :15 I*' '9 /2 26~

H8 _ __ _ _ 1 _ _ 6 9 __ _ _ 16 H18+ ,--2 ~ 9 2'

'__ 'A DBH __ _ _ __ _ _ _ 0 V II -'

V2 _ ___ _ 0 V 3 __ _ _ _ _ _ _ _ _ _ _ _ _ 0

'V3+ '.'0 DBC _ _ _ _ __ _ _ _ __ _ _ 0

DBC- -' __ 0 C 8+ _ _ _ _ ___ _ _ _ __ _ _ 0 C7+ _ _ _ _ __ _ __ _ _ 0 C6+ __ _ _ _ __ _ __ _ _ 0 C 5+ _ _ _ _ __ ___ _ _ _ _ 0 C4+ __ _ _ _ __ _ _0 C 3+ _ _ _ _ ___ ___ __ _ _ 0 C3 -- , - '-._ _ __ _ _

C2+ __ _ _ _0 C2 - " ' ' _

.C1+ __ 0 CTS+ ___0 Totals 45 /0 10 1 2 0 67/2 15 2 0 0 144

_____SAT / MAI -SC SVI LPI VOL SATI/MAT SCI SVI LPI V L ___

LIC-04-0040 Attachment Page 12 Table 2 Fall 2003 Outage SIG RC-2A Plug List Page I of 2 Row ILine 2003 Bobbin call PI Call 2003 MRPC call Volts Deg  % Circ Deg Axial Sup 02 MRPC Data 03 Dent 1 3 144 TBP Flat Rail 7_l l_

2 3 58 TBP Flat Rail 3 9 94 NDD SCI HTS + 0.18 0.16 87 63 28 HTS No Change None 4 11 130 NDD SCI HTS + 0.09 0.14 89 75 40 1HTS No Change None 5 15 44 TBP Flat Rail = =

6 15 58 TBP Flat Rail 7 16 63 NDD SAI IITS + 0.28 0.17 83 25 0.14 HTS Change None 8 23 58 NDD SAI HTS + 0.49 0.2 101 30 0.32 HTS No Change None 9 25 56 NDD SAI TITS + 0.81 0.16 111 24 0.2 HTS No Change None 10 30 73 NDD SA1 HTS + 1.70 0.22 102 28 0.26 HTS Change None I 1 33 74 NDD SAI HTS + 1.55 0.23 1132 31 I 0.26 HTS No Change None 12 35 74 NDD SAI HTS + 1.73 0.15 127 26 0.19 FS No Change None 13 56 81 NDD SAI H6 + 0.32 0.42 119 39 _ 0.42 EC No History 4.44 V 14 61 50 NDD SAI 117 + 0.10 0.39 87 40 0.2 EC No History 9.07 V 15 81 62 NDD SAI H1 - 0.59 0.23 109 31 _ 0.61 FS No Change 54.09 V 16 85 68 NDD SA 115 + 37.97 0.17 85 21 0.17 FS No Change None 17 86 47 NDD SAI H7 + 10.18 0.19 121 28 0.29 FS No Change None I NDD SAI H7 +11.05 0.16 114 26 1 2.25 FS No Change None 18 87 156 NDD SAI H5 + 36.24 0.11 106 24 1 0.26 FS No Change None 19 87 60 NDD SAI 115 + 37.22 0.14 92 25 1 0.22 FS Change None 20 90 55 NDD SA 117+ 11.54 0.16 125 29 0.58 FS Change None NDD SA1 117 + 14.57 0.27 94 36 0.88 FS Change None NDD SAI 117 + 1.61 0.13 124 16 0.51 FS No Change None NDD SAI H7 + 10.81 0.26 106 26 1.27 FS No Change None DBH +4.83 0.43V I0ID SAI H7 +3.52 0.15 127 17 0.4 FS No Change None NDD SAI H7 + 9.91 0.55 113 42 1 0.46 FS No Change None 21 90 59 NDD SAI H6 - 0.92 0.28 121 34 0.35 FS Change 34.63 V NDD SAI 116 - 0.23 0.68 119 52 0.41 DSP No Change 34.63 V 22 90 63 NDD SA1117+ 12.76 0.15 90 28 0.9 FS No Change None 23 90 71 NDD SAI H7 +9.18 0.21 138 30 0.21 FS No Change None 24 90 77 NDD SCI HI - 0.15 0.33 100 53 70 DSP No Change 34.13 V 25 91 58 NDD SAT 116+0.1 0.76 1116 54 0.72 DSP No Change 53.83 V 26 91 64 NDD SA 115 +35.59 0.28 112 34 _ 0.74 FS No Change None 27 93 58 DSI H8 + 0.05 3.15V 38D SCI I18 - 0.24 0.24 105 53 33 DSP No Change 6.13 V 28 93 76 NDD SAI H7 - 0.22 0.21 89 28 1 0.22 DSP No Change None 29 93 82 INR HI +0.47 1.25V 54D SAI H1 +1.42 0.16 79 24 0.43 DSP Marginal Change 6.35V 30 94 41 NDD LPI JITS + 3.12 0.32 108 26 34 0.56 FS No Change None 31 94 61 NDD SAI 116 + 18.74 0.15 93 25 0.33 FS No Change None NDD SAI H6 + 21.43 0.12 III 23 0.79 FS No Change None NDD SAX 117 + 2.65 0.34 123 43 4.06 FS No Change None 32 94 83 NDD SAI HI + 1.42 0.26 117 27 0.51 DSP No Change None 33 95 42 DFI HTS + 2.64 0.53V 115D LPI HTS + 2.51 0.19 132 19 32 0.39 FS No Change None 34 96 41 NDD SVI H5 +32.01 0.12 132 16 29 0.19 FS No Change None NDD SVI H5 + 32.07 0.25 121 22 33 0.59 FS No Change None 35 96 55 NDD SA 117 + 9.99 0.07 97 26 0.18 FS No Change None 36 96 67 NDD SAI H5 + 0.26 0.25 114 33 0.22 DSP No Change None 37 96 71 NDD SAI H77+13.94 0.17 111 28 0.33 FS No Change None NDD SAI H7+ 13.92 0.1 119 23 0.15 FS No Change None NDD SAI H7 + 15.37 0.18 104 29 10.36 FS No Change None

LIC-04-0040 Attachment Page 13 Table 2 (cont)

Fall 2003 Outage S/G RC-2A Plug List Page 2 of 2 Row Line 2003 Bobbin call PI Call 2003 MRPC call Volts Deg % Circ Deg Axial Sup 02 MRPC Data 03 Dent 37 96 71 NDD SAI H7 + 16.34 0.18 107 29 0.27 FS No Change None 38 97 46 NDD SAI H7 + 0.01 0.28 113 33 0.17 DSP No Change 3.09 V 39 97 50 NDD SAI H7 + 0.01 0.53 130 46 0.43 DSP No Change None 40 97 68 NDD SAI H6 + 13.51 0.19 113 31 0.34 FS No Change None 41 98 59 NDD SCI HI + 0.27 0.35 107 50 70 DSP Marginal Change 12.57 V 42 98 71 NDD SCI H6 + 0.19 0.36 108 20 125 DSP No Change 3.57 V 43 100 69 NDD SAI HI + 0.03 0.23 112 36 0.52 DSP No Change None 44 101 70 DSI HI -0.09 L.OOV 39D SAI H1 +0.00 0.16 103 26 0.52 DSP Marginal Change None NDD SCI H7 + 0.00 0.2 77 62 71 DSP Marginal Change None NDD SCI H6 - 0.07 0.31 83 62 105 - DSP No Change None 45 102 55 NDD SAI H8 + 11.18 0.13 116 18 0.23 FS No Change None DFI H8 +16.0 0.16V I IID SAI H8 + 15.61 0.15 81 25 0.19 FS No Change None

= NDD SCI H7 + 0.12 0.34 114 34 42 DSP No Change None 46 103 64 INR HI +0.43 1.06V 105D SCI HI + 0.00 0.23 119 27 64 DSP No Change 13.25 V

LIC-04-0040 Attachment Page 14 Table 3 Fall 2003 Outage S/G RC-2B Plug List Page 1 of 2 Row Line 2003 Bobbin call PI Call 2003 MRPC call Volts Deg  % Circ Deg Axial Sup 02 MRPC Data 03 Dent 1 3 44 TBP Flat Rail _ _

2 3 58 TBP Flat Rail 3 9 72 NDD SAI HTS + 0.21 0.4 93 43 0.28 HTS No Change None I NDD SAT HTS + 0.45 0.14 118 35 0.24 HTS No Change None 4 15 44 TBP Flat Rail _ .

5 15 58 TBP Flat Rail _ _

6 16 73 NDD SAI 115 + 1.68 0.18 103 23 0.24 FS No History None 7 20 55 NDD SAI H5 - 0.45 0.27 107 34 0.25 EC No History 10.33 V 8 23 22 NDD SAI HI + 0.40 0.57 114 46 0.47 EC No Change 14.60 V 9 23 44 NDD SAI H6 + 0.43 0.63 109 45 0.31 EC Change 14.76 V 10 23 62 NDD SAI H5 + 2.69 0.32 123 34 0.48 FS Change 5.58 V 11 23 112 NDD SAI H5 - 0.34 0.28 125 36 0.21 EC No History 8.57 V 12 25 70 NDD SAI H6 + 0.58 0.59 112 49 0.23 EC No History 23.11 V 13 27 114 NDD SAI H5 +1.24 0.27 111 30 0.54 FS No History None 14 28 33 NDD SAI H4 - 0.08 0.4 112 39 0.4 EC No History 4.96V 15 31 46 NDD SAT H5 + 0.25 0.49 105 44 0.2 EC No Change 7.81 V 16 36 33 NDD SAI H2 + 0.64 0.55 112 41 0.12 EC Marginal Change 11.19 V 17 47 116 NDD SAI V2 +4.75 0.39 119 39 0.28 FS No History None 18 48 39 NDD SAT H4 + 5.22 0.29 125 33 0.44 FS No History None 19 54 51 NDD SAI H6 + 1.15 0.69 86 51 0.17 FS No History 7.55 V 20 55 70 NDD SAI V2 + 3.92 0.25 121 29 0.32 FS No History None 21 55 74 NDD SAI V2 - 3.62 0.27 127 30 1.24 FS No History None 22 56 79 NDD SAI 116 - 0.34 0.45 128 36 0.64 EC No History 7.01 V 23 63 60 SAI V2 + 12.74 0.39 145 42 0.85 FS No History None DFI V2 + 11.3 0.40V 84D SAI V2 +10.90 0.53 143 44 0.68 FS No History None 24 66 53 DSI HI - 0.31 1.03V 70D SAI H1- 0.31 0.45 122 50 0.47 EC No History None 25 68 69 NDD SCI H2 + 0.28 0.46 112 38 112 DSP Change 120.7 V 26 70 59 NDD SAI H6 - 0.40 0.3 97 31 0.48 EC No History 8.23 V 27 71 26 NDD SAI H5 - 1.40 0.38 79 30 0.19 EC NoHistory 10.93 V 28 71 76 NDD SAI 115 + 0.81 0.7 132 55 0.7 EC No History 4.28 V 29 76 43 NDD SAT 118 - 0.02 0.28 92 32 0.35 DSP Change None 30 76 39 NDD SAT H8 + 0.16 0.23 108 29 0.27 DSP Change None 31 76 81 NDD SAI H2 + 0.22 0.57 117 41 0.57 EC Change 13.38 V 32 78 61 NDD SAIHI -0.57 0.31 116 35 0.63 FS NoChange None 33 79 68 NDD SAI H2 + 0.00 0.22 100 29 0.51 DSP No Change None 34 80 59 NDD SAI H6 + 20.60 0.22 76 30 0.44 FS Change None NDD SAI H6 + 21.57 0.21 117 29 0.22 FS NoChange None 35 81 84 NDD SAI}ITS+ 2.89 0.11 113 21 0.41 FS NoChange None 36 83 58 NDD SAT H4 + 2.89 0.23 121 33 0.25 FS No Change None 37 84 37 NDD SCI H8 + 0.17 0.23 89 62 49 DSP Marginal

.43 14 92 141 0.7 8 I 1 h nChange eN 32.65 nV 138184 57 NDD 38184 S~l H5 5 7 D D SAI 34. 69 11 ++34.69 0.43 92 0.78 I F No Change None

LIC-04-0040 Attachment Page 15 Table 3 (Cont.)

Fall 2003 Outage S/G RC-2B Plug List Page 2 of 2 Row Line 2003 Bobbin call PI Call 2003 MRPC call Volts Deg  % Circ Deg Axial Sup 02 MRPC Data 03 Dent 39 84 73 NDD SCI H7-4.61 0.19 101 49 27 FS No Change None NDD SCI H7-1.16 0.4 95 57 79 EC No Change 5.32 V NDD SVI H7-2.40 0.21 87 29 FS No Change None NDD SVI H7 -4.93 0.22 110 29 - FS No Change None 40 84 75 NDD SAI H14-1.40 0.78 110 51 0.56 EC Change 9.29V 41 86 67 NDD SAI H8 +0.00 0.39 73 40 0.34 DSP No Change 16.72 V 42 87 52 NDD SCI114-1.10 0.27 109 33 21 FS Marginal Change 6.30 V 43 87 62 NDD SAT H17+2.85 0.22 97 28 0.4 FS No Change None 44 89 70 NDD SAI H8+1.26 0.35 128 38 0.81 FS No Change 7.76V NDD SAI H8+3.46 0.2 128 32 0.51 FS No Change None 45 90 61 NDD SCI 118 + 0.36 0.45 84 71 34 DSP No Change 45.45 V 46 90 77 NDD SCI HlI - 0.03 0.29 126 30 51 DSP Marginal Change None 47 91 52 NDD SAI 117+0.73 0.42 100 36 0.84 FS Change 14.5V 48 91 54 NDD SAI 113+0.15 0.31 122 35 0.25 DSP No Change None 49 91 56 NDD SAI H11-0.18 0.17 102 26 0.41 DSP Marginal Change None 50 91 74 NDD SAI 118-0.92 0.53 121 46 0.6 FS No Change None 51 92 59 NDD SAI H6 + 1.57 0.2 108 27 0.26 FS Marginal Change None NDD SAI 116 + 2.05 0.26 104 30 0.23 FS Marginal Change None NDD SAI H6 + 2.25 0.29 71 27 0.2 FS Marginal Change None NDD SAI H16+2.74 0.3 73 30 0.6 FS Marginal Change None 52 92 65 NDD SAI H7+13.04 0.16 80 26 0.16 FS Change None NDD SAI 117 + 15.90 0.23 93 31 0.25 FS Change None 53 92 69 NDD SA1117 + 16.03 0.17 71 26 0.78 FS Marginal Change None 54 92 73 NDD MIAI H7 +13.92 0.13 55 25 0.21 FS Change None NDD MIAI H7 + 14.99 0.2 122 28 0.47 FS Marginal Change None NDD SAI117 + 12.01 0.25 111 32 0.57 FS Marginal Change None NDD SAI117 + 14.11 0.23 99 31 0.2 FS Change None NDD SAI 117 + 14.22 0.22 90 31 0.2 FS Change None 55 93 64 NDD SAI 117+ 3.15 0.2 98 26 0.39 FS No Change None NDD SAI117 + 4.25 0.16 107 22 0.33 FS No Change None 56 93 66 NDD SAI17+ 0.88 0.28 116 25 0.32 FS No Change 14.93V NDD SC 118+0.18 0.45 129 8 101 DSP No Change 3.40V 57 94 61 NDD SAI 118-0.11 0.44 132 41 0.46 DSP No Change 15.55V NDD SCI H17+0.67 0.19 105 39 42 FS No Change None NDD SCI 18+0.27 0.57 110 31 114 - DSP No Change 15.55V 58 94 63 NDD SCI H18+0.11 0.71 95 53 134 DSP No Change 19.11 V 59 94 65 NDD SCI 118 + 0.06 1.07 106 43 137 DSP Change 7.94 V 60 95 58 NDD SAI H6+18.57 0.14 81 24 0.19 FS No Change None NDD SAI H6 + 19.76 0.14 84 22 0.49 FS No Change None NDD SAT H6 + 20.82 0.22 115 30 0.49 FS No Change None 61 95 64 NDD SCI H18-0.60 0.28 90 62 38 FS No Change 10.46V 62 95 66 NDD SCI H8 + 0.14 0.73 109 42 111 DSP Change 6.84 V 63 95 70 NDD SAI H6 + 20.67 0.24 118 28 0.43 FS Change None 64 96 65 NDD SCI H18- 0.32 0.25 131 8 44 DSP Marginal Change 4.06 V 65 98 83 NDD SAI H6 + 20.00 0.52 135 46 0.26 FS Marginal Change None 66 99 62 NDD SAI 118 +2.33 0.15 120 27 0.31 FS Marginal Change None 67 100 69 NDD SAI 113+0.17 0.5I 138 45 0.71 DSP Change None 68 101 72 NDD SAI 117+0.3 0.26 113 34 0.29 DSP Change 14.10V 69 102 63 NDD SAI III - 0.13 0.23 102 35 0.32 DSP No Change None

LIC-04-0040 Attachment Page 16 Table 4 - Summary of the In Situ Pressure Testing Location Steam Generator B Row 94 Line 65 Test Pressure Target 1,609 NODP Achieved 1,700 Ramp Rate 61 psi/sec Target 2,710 SLBP Achieved 2,750 Ramp Rate 51 psi/sec

LIC-04-0040 Attachment Page 17 APPENDIX DEFINITIONS The acronyms defined below are used in Tables 1 through 4.

DFI: Differential Freespan Indication - An indication in the freespan that gives a flaw-like response on the bobbin coil (diagnostic/review required)

DSI: Distorted Support Indication (diagnostic/review required)

RNR: Indication not reportable (diagnostic/review required)

MAI: Multiple Axial Indication - Axial indications in the same plane (pluggable)

NDD: No detectable degradation (no further action required)

SAL: Single Axial Indication - Axially oriented crack-like indication (pluggable)

SCI Single Circumferential Indication - Circumferentially oriented crack-like indication (pluggable)

SVI: Single Volumetric Indication - Indication which represents that volumetric (non-oriented) degradation is present (pluggable)

TBP: To be plugged VOL: Volumetric - Indication which is volumetric in nature and generally associated with tube manufacturing (diagnostic/review required)

LIC-04-0040 Attachment Page 18 Figure 1 FORT CALHOUN STEAM GENERATOR ELEVATION DRAWING HTE Hot leg Tube End HTS Hot Leg Tubesheet H1-H6 Hot Leg Full Supports H7 Hot Leg Partial Egg Crate H8 Hot Leg Partial Drilled Support DBH Diagonal Bar Hot Leg VI-V3 Vertical Supports DBC Diagonal Bar Cold Leg \

C8 Cold Leg Partial Drilled Support DBH /V C7 Cold Leg Partial Egg Crate C6-C1 Cold Leg Full Supports CTS Cold Leg Tubesheet CTE Cold leg Tube End H8 H6 l~g-llll H4 . I1 H3II l H2