L-2013-246, Steam Generator Tube Inspection Report

Steam Generator Tube Inspection Report

ML13277A358
Person / Time
Site:	Turkey Point
Issue date:	09/19/2013
From:	Kiley M Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2013-246
Download: ML13277A358 (26)

Text

September 19, 2013 L-2013-246 FPL. 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-00001 Re: Turkey Point Unit 4 Docket No. 50-251 Steam Generator Tube Inspection Report The attached Turkey Point Unit 4 Cycle 27 Refueling Outage Steam Generator Tube Inspection Report is submitted to NRC in accordance with Turkey Point Technical Specification 6.9.1.8, and within 180 days after the initial entry to MODE 4 following completion of the inspections performed in accordance with Technical Specification 6.8.4.j, Steam Generator (SG) Program.

The report includes the following:

a. The scope of inspections performed on each SG,

b. Degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each degradation mechanism,

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing,

h. The primary to secondary leakage rate observed in each SG during the cycle preceding the inspection which is the subject of the report,

i. The calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet for the most limiting accident in the most limiting SG, and

j. The results of monitoring for tube axial displacement (slippage).

Should there be any questions, please contact Robert Tomonto at (305) 246-7327.

Sincerely, Michael Kiley Vice President Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC.

Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 SW 344 St Homestead, FL 33035

L-2013-246 Page 1 of 16 Turkey Point Unit 4 (TP4-27)

Steam Generator Tube Inspection Report Attachment 1

Background

This report is provided in accordance with Turkey Point Unit 4 Technical Specification Section 6.9.1.8, "Steam Generator Tube Inspection Report" for the inspection conducted December 6-11, 2012 during the Unit 4 End-of-Cycle 26 (EOC-26) Refueling Outage (RFO), which is also referred to as the TP4-27 RFO. The TP4-27 RFO inspections satisfy the surveillance requirements for the 3rd Inspection Period of 72 Effective Full Power Months (EFPM) in accordance with Turkey Point Unit 4 Technical Specification Section 6.8.4.j.d.2.c.

Turkey Point Unit 4 contains three (3) Westinghouse Model 44F steam generators (SGs), which were installed in April, 1983 to replace the original Unit 4 SGs. At the completion of Cycle 26 (CY-26), the Unit 4 SGs had accumulated 23.05 Effective Full Power Years (EFPY) of operation.

Following the TP4-27 RFO, Turkey Point Unit 4 initially entered Mode 4 on March 25, 2013, which marked the beginning of Cycle 27 (CY-27).

Pursuant to Turkey Point Unit 4 Technical Specification 6.9.1.8, this Steam Generator Tube Inspection Report is required to be submitted to the NRC within 180 days after initial entry into Mode 4, or by September 20, 2013.

Turkey Point Technical Specification Section 6.8.4.j.d.2.c contains the third inspection period requirements and requires that 100% of the tubes be inspected every 72 EFPM (for the third and subsequent inspection periods). There were two SG inspections in the 3rd inspection period; one during TP4-25 RFO in 2009 and one during TP4-27 RFO in 2012. The inspections during TP4-25 RFO and TP4-27 RFO satisfied the TS surveillance requirements for the 3rd inspection period. There is only one remaining outage in the 3rd inspection period (TP4-28 RFO in Fall, 2014); that outage is a planned skip for primary side SG inspections. The next planned inspection for Unit 4 is during TP4-29 RFO in Spring, 2016, which will be the first outage in the 4th inspection period of 72 months.

Steam Generator Tube Inspection Report The Turkey Point Unit 4 Technical Specification 6.9.1.8, "Steam Generator Tube Inspection Report" requires the following input:

a. The scope of inspections performed on each SG,

b. Degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each degradation mechanism,

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing,

h. The primary to secondary leakage rate observed in each SG (if it is not practical to assign the leakage to an individual SG, the entire primary to secondary leakage should be conservatively

L-2013-246 Page 2 of 16 Turkey Point Unit 4 (TP4-27)

Steam Generator Tube Inspection Report Attachment 1 assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report,

i. The calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 1.82 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined, and

j. The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

The TP4-27 RFO SG tube inspections were conducted in all three SGs (4A, 4B, & 4C) as described below.

a. The scope of inspections performed on each steam generator The scope of this examination is summarized in Table 1 below and is established to meet the following requirements:

a. Technical Specification 6.8.4.j "Steam Generator (SG) Program" Note: As approved through License Amendments 255 and 251 (Reference 2) on Nov. 6, 2012, TSTF-510 was incorporated into the Turkey Point technical specifications to make changes to the sections pertaining to SG tube integrity, the SG program, and the SG tube inspection report.

b. Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines," Revision 7, EPRI, Palo Alto, CA, TR-1013706 (Ref. 4).

The basis for bobbin and +PointTM tube examinations is given in Table 1.

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Steam Generator Tube Inspection Report Attachment 1 TABLE I BASIS FOR TUBE EXAMINATION SAMPLES e Examination Sample Required or Basis Potential Supplemental Degradation 100% full length in rows 3 and higher. Row 1 & 2 examinations will be limited to the Wear/

hot leg and cold leg straight sections. Required Degradation Assessment ODSCC Screening of 100% of dings < 5 volts in straight sections (verticals). This includes Required Degradation Assessment ODSCC tubes with low-voltage u-bend offset (LVU) tubes. I 50% of the hot leg tubesheet to the extent of TTS +3.00 to -18.11 inches. (1) This Required Degradation Assessment. Foreign Object includes minimum 50% sample of BLG & OXP indications within the TS. Wear Note: Inspection expansion, if required, will be in accordance with the requirements of the Technical Specifications and Section 3.7 of the EPRI Steam Generator PWSCC Examination Guidelines Rev 7 and for FO Integrity Guideline Chapter 10. ODSCC All Hot Leg and Cold Leg Periphery Expansion Transitions - +3"/-2" from top of Supplemental Degradation Assessment. Foreign Object tubesheet. "Periphery Tubes" are defined as the two outer-most peripheral tubes Wear exposed to the annulus, and all open row 1 and 2 tubes in columns 1-92.

Tight radius u-bends - Required Degradation Assessment. PWSCC

-50% of row 1 and 2 (not inspected in prior inspection) ODSCC 50% of hot leg freespan dings > 5 volts between TSH and 06H +1.00" (not Required Degradation Assessment. PWSCC inspected in prior inspection)

PWSCC 50% of u-bend dings (not inspected in prior inspection) Required Degradation Assessment. ODSCC 50% of hot leg dents/dings at structures (not inspected in prior inspection) Required Degradation Assessment. PWSCC ODSCC Note (I) The examination depth of 18.11" was approved by License Amendments 254 and 250: F. Saba (NRC) to M. Nazar (FPL), "Turkey Point Nuclear Generating Station Unit Nos. 3 and 4 - Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes (TAC NOS. ME851 5 and ME8516)," November 5, 2012, (ADAMS Accession No. ML12292A342) (Ref. 3).

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Steam Generator Tube Inspection Report Attachment 1

b. Degradation mechanisms found The TP4-27 bobbin and +PointTM examination results for Turkey Point Unit 4 identified mechanical wear degradation at the following locations:

• Anti-vibration bar (AVB) contact points in the u-bends

• Broached tube support contact points

" Foreign Object wear at broach support location

" Hot Leg Baffle Plates (BAH)

In addition to the wear degradation discussed above, there were eleven (11) indications indicative of PWSCC reported amongst the three SGs in Unit 4. All of these indications were located near the H/L tube-end, below the H* distance, which is defined as Top of Tubesheet (TTS) - 18.11 ". On November 5th, 2012, the NRC approved License Amendments (Ref. 3) regarding permanent alternative repair criteria for service-induced degradation detected in the tubesheet region.

Reference 3 states: "Tubes with service-induced flaws located greater than 18.11 inches below the top of the tubesheet do not require plugging". Therefore, none of the eleven tubes with indications below the H* depth were removed from service. Aside from these indications reported below the H* depth, there were no other indications of corrosion-related tube degradation detected during the inspection.

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Steam Generator Tube Inspection Report Attachment 1

c. Nondestructive examination techniques utilized for each degradation mechanism ,

TABLE 2 - Turkey Point Unit 4 Examination Techniques for TP4-27 Depth Sizing Site-Specific Review Technique Industry Damage Demonstrated Extended Technique Deemed Acceptable Qualification Mechanism Applicability Applicability Applied Detection Sizing Bobbin 96001.1 Thinning Top of Tubesheet Above Differential Mix Revision 11 and TSP Tubesheet Phase Analysis Yes For Information 96004.1 AVBs and TSPs Differential Mix For Service(1 )

2 Bobbin Revision 13 Wear Diagonal and None Amplitude Analysis Yes (AVB Only)

Vertical Straps (Using Vert-Max) 96004.2 AVBs and TSPs Absolute Mix 3 Bobbin Revision 13 Wear DiagonalStraps and None Amplitude Analysis Yes For Information Vertical (Using Vert-Max) 96005.2 Freespan in the Not Sized with Bobbin Revision 9 Pitting Presence of Sludge Pile Bobbin Yes No Copper 5 Bobbin 24013.1 2 ODSCC Freespan Dings None Not Bobbin Sized with Yes For Information Revision <5.00 Volts 6 Bobbin 6 Bobbin 1-28411 Reiin2 Axial ODSCC

~~~~~Drilled TSP With or w/o Dents None NtSzdwt BobnYes e o nomto For information 1-28412 < 2 volts Not Sized with 7 obn 1-28412 AilOSC FesaNoeNot Sized withYeFoInrmtn Revision 2 Axial ODSCC Freespan None Bobbin Bobbin 1-28413 Axial ODSCC Broached TSP, None Not Sized with Yes For information Revision 2 Sludge Pile Bobbin 27091.2 0 PLP Wear PLP Wear 9 Bobbin Revision PLP Wear (part not present) (When Part N/A Yes N/A Present)________ ______ ___

10 +PointTM Revision 96511.1/.216 WSCC Low Row U-bend None Single PhaseFrequency Analysis Yes For Information

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Steam Generator Tube Inspection Report Attachment 1 TABLE 2 - Turkey Point Unit 4 Examination Techniques for TP4-27 continued Industry Damage Demonstrated Extended Depth Sizing Site-Specific Review Technique Qualification Mechanism Applicability Applicability Technique Deemed Acceptable Applied Detection Sizing Dent, Dings, Single Frequency 11 +PointT i 20510.1 Circ PWSCC Expansion Non-Dented Singe Frequenc Yes For Information Revision 7 Transition Support Phase Analysis Structures, Tubesheet 1 PitMAilPSCNon-Dented Yes For Information 12 +PointTM 20511.1 Axial PWSCC Expansion Support Single Frequency Revision 8 Transition Structures, Phase Analysis Tubesheet 13 +PointTM 673. Axial PWSCC Dent Non-Dented Yes For Information 130. itSupport Single Frequency Revision 17 Structures, Phase Analysis Tubesheet 14 +PointTM 22401.1 Axial ODSCC Dented Support Tubesheet, Revision 4 Structures Expansion Single PhaseFrequency Analysis Yes For Information

> 2.0 volts Transition, Dents, Dings, Non-dented TSP 96910.1 AVB, Baffle Differential Mix 15 +PointT' Revision 10 Wear Broached TSP Plate and PLP Amplitude Analysis Yes For Service Wear (Using Vert-Max)

Single Frequency 6 +Poin Revision 4 Volumetric Freespan None Amplitude Analysis Yes forroion I_ (Using Peak-Peak) 17 +PointTM 22842.3 5 Circ Dented Support None Sizing using LengthFrom/To Yes For Information Revision ODSCC Structures

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Steam Generator Tube Inspection Report Attachment 1 TABLE 2 - Turkey Point Unit 4 Examination Techniques for TP4-27 continued Industry Damage Demonstrated Extended Depth Sizing Site-Specific Review Technique Qualification Mechanism Applicability Applicability Technique Deemed Acceptable Applied Detection Sizing 18 +PointTM 21410.1(2) Circ ODSCC Expansion FTSP, Single Frequency Yes For Information Revision 6 Transition Sludge Pile, Phase Analysis Tubesheet, Dents, Dings, U-bend 19 +PointTM¶ 96701.1 Circ PWSCC Expansion Dents, Dings, Single Frequency Analysis Yes For Information Revision 12 Transition Tubesheet Amplitude (Using Peak-Peak)

Based on Max Depth Phase 20 +PointTMl 27901.1 Rev. 1 20 27902.1 27903.1 Rev. 1 PLP Wear PLP Wear None PLP Wear Yes For Service Rev. 1 Morphology Morphology 27904.1 Rev. 1 Dependent Dependent 27905.1 Rev. 1 (part not present) (part not present) 27906.1 Rev. 1 27907.1 Rev. 1 21 21+PintTM

+PointTM Revision 1-28424 2 Axial ODSCC Sludge Pile None Not qualified Yes No 22 +PointTMl 1-28425 2 Axial ODSCC Freespan, None Not qualified Yes No Revision Broached TSP 23 +PointTM 1-28431 1 Revision Axial ODSCC Sludge Pile None Single Frequency No For Information Amplitude Analysis 24 +PointTNM 1-28432 1 Revision Axial ODSCC Freespan, Broached TSP None Single Frequency No For Information Amplitude Analysis All Locations Single Frequency +PointTM 115 21401.1 25 Pancake Revision 6 Axial ODSCC except U-bends, None Phase Analysis is the For Information Dents, Expansions primary

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Steam Generator Tube Inspection Report Attachment 1 TABLE 2 - Turkey Point Unit 4 Examination Techniques for TP4-27 continued Industry Damage Demonstrated Extended Depth Sizing Site-Specific Review Technique Qualification Mechanism Applicability Applicability Technique Deemed Acceptable Applied Detection Sizing 26 Single PhaseFrequency

.115 Pancake 21402.1 6 Revision Circ ODSCC Transition Sludge Pile detection For Information Analysis coil 27 .115 21503.1 Axial PWSCC Sludge Pile Single Frequency +Poin For Information Pancake Revision 4 Transition Phase Analysis is the primary

.115 21504.1 Circ PWSCC Sludge Pile Single Frequency detection For Information 28 Pancake Revision 4 Transition Phase Analysis coil Info only: FoInrmtn 29 .115 99998.1 Pitting Freespan in the Sludge Pile Single Frequency Use 96005.2 For Information Panak 9Rviio15Presence of Amplitude Analysis fs in0the Pancake Revision 5 Copper (Using Peak-Peak) for pits in the sludge pile

.115 96911.1 Absolute Mix 30 Pacae 9evsin1 Wear Broached TSP PLP Wear Amplitude Analysis +PointTl For Service Pancake Revision 9 (Using Vert-Max) is the primary 31 .080 HF Pancake 21505.1 3 Revision Axial PWSCC Expansion Transition Sludge Pile Single PhaseFrequency Analysis detection coil For Information 32 .080 HF 21506.1 Circ PWSCC Expansion Sludge Pile Single Frequency For Information Pancake Revision 4 Transition Phase Analysis 33 +PointT' Axial ODSCC Support Structures, Expansion Yes For Information 21409.1 Freespan Region, Transition ingle Frequency Revision 7 Sludge Pile and Axial / Circ Phase Analysis Tubesheet Crevice Notes: (1) Broached TSP wear should be sized with Technique 96910.1 (2) The sizing parameters in EPRI ETSS 21410.1 are equivalent to those listed in EPRI Report TR 107197-Pl

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Steam Generator Tube Inspection Report Attachment 1

d. Location, orientation (if linear) and measured sizes (if available) of service induced indications Please see Attachments 2, 3 & 4 for indication listings for SG 4A, 4B and 4C respectively.

e. Number of tubes plugged during the inspection outage for each degradation mechanism Table 3 Turkey point Unit 4 Tube Plugging TP4-27 Nonconforming Condition SG A SG B SG C Total Preventative Tube Plug (PTP) for foreign object Indication with the part still present 0 1 0 1 Total (1) Row 17 column 74 in SG 4B was preventively (conservatively) plugged and stabilized due to the presence of a wear indication associated with (and in the presence of) a possible foreign object at the 01 H broach support location.

f. The number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator No tube repair methods (i.e. sleeving) are approved for Turkey Point Unit 4 that would have an effect on the effective plugging percentages. Therefore, the applicable effective plugging percentage is synonymous with the % Plugged in Table 4 below:

Table 4 Turkey Point Unit 4 Steam Generator Cumulative Tube Plugging Summary TP4-27 SG # Plugged  % Plugged 4A 33 1.03%

4B 21 0.65%

4C 11 0.34%

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Steam Generator Tube Inspection Report Attachment 1

g. The results of condition monitoring, including the results of tube pulls and in-situ testing All tubes inspected met the tube integrity performance criteria in TS 6.8.4.j.b and condition monitoring requirements. No tubes required in-situ pressure testing. No tube removal was required.

h. The primary to secondary leakage rate observed in each SG (if it is not practical to assign the leakage to an individual SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report No primary to secondary leakage was reported during the preceding cycle of operation.

i. The calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 1.82 times the maximum operational primary to secondary leakage rate, the report should describe how it was determined The accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet is calculated from any observed normal operating leakage that cannot be attributed to a source other than the tubesheet expansion region. The technical basis for this calculation is contained in the H* Alternate Repair Criteria (ARC) for the Turkey Point plant. For the operating period preceding the TP4-27 RFO inspection, no operational primary-to-secondary leakage has been observed. Further, there are no existing degradation mechanisms that have the potential for leakage.

For Turkey Point Unit 4, the maximum operational primary-to-secondary leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet is determined by multiplying any normal operating leakage by a factor of 1.82 to determine the accident induced leakage rate. This multiplying factor for leakage is based on H* Alternate Repair Criteria (ARC) methodology. Since no operational primary-to-secondary leakage has been observed, the calculated accident induced leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet is zero.

Therefore, neither the normal operating leakage limit nor the accident induced leakage limits will be challenged during the next operating period.

j. The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

Monitoring of tube slippage was completed in accordance with Regulatory Commitment #1 in Ref. 3. No tube slippage was discovered based on the results of the TP4-27 RFO SG inspections.

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Steam Generator Tube Inspection Report Attachment 1

References:

1. Technical Specifications Task Force (TSTF) Traveler TSTF-51 0, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."

2. License Amendments 255 and 251: F. Saba (NRC) to M. Nazar (FPL), "Turkey Point Nuclear Generating Station Unit Nos. 3 and 4 - Issuance of Amendments Regarding Adoption of TSTF 510, 'Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection' (TAC NOS. ME9106 and ME9107)," November 6, 2012. (ADAMS Accession No. ML12297A240)

3. License Amendments 254 and 250: F. Saba (NRC) to M. Nazar (FPL), "Turkey Point Nuclear Generating Station Unit Nos. 3 and 4 - Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes (TAC NOS. ME8515 and ME8516),"

November 5, 2012. (ADAMS Accession No. ML12292A342)

4. EPRI Steam Generator Management Program: "Pressurized Water Reactor Steam Generator Examination Guidelines," Revision 7, EPRI, Palo Alto, CA, TR- 1013706.

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Steam Generator Tube Inspection Report Attachment 1 Abbreviations ARC - Alternate Repair Criteria CSI - Component Support and Inspections ECT - Eddy Current Testing EPRI - Electric Power Research Institute ISI- In-service Inspection NEI - Nuclear Energy Institute PWSCC - Primary Water Stress Corrosion Cracking RFO - Refueling Outage SG - Steam Generator TTS- Top of Tubesheet Report Acronyms AVB - Anti-Vibration Bar BLG - Bulge C/L - Cold Leg CLP - Clip Plot Measurement DSI - Distorted Support Indication H/L- Hot Leg LAR - Lead Analyst Reviewed NDD - No Detectable Degradation OXP - Over-expansion PID - Positive Tube Identification PLP - Possible Loose Part PTP - Preventative Tube Plug TEC - Tube End Cold Leg TEH - Tube End Hot Leg TSC - Tubesheet Cold Leg TSH - Tubesheet Hot Leg TSP - Tube Support Plate TWD - Through Wall Depth WAR - Mechanical Wear Outage Designators TP4-23 = EOC-22 TP4-24 = EOC-23 TP4-25 = EOC-24 TP4-27 = EOC-26

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Steam Generator Tube Inspection Report Attachment 1 ADDITIONAL INFORMATION The following information is included to assist the staff in their review of the information provided in this report.

Secondary Side Inspection Secondary side inspection information is not required by TS Section 6.9.1.8. However, this information is being provided based on NRC requests for additional information regarding previous reports submitted by FPL in accordance with this specification:

Secondary Side Inspections (SSI) during the TP4-27 RFO include the following:

• Upper Bundle Flush

• Sludge Lance

• FOSAR (Foreign Object Search and Retrieval)

Upper bundle flush and sludge lancing was completed in all three steam generators. The processes recovered 27 lbs of sludge from SG 4A, 27 lbs from SG 4B and 24 lbs from SG 4C.

Post sludge lancing FOSAR was performed in all three steam generators. Foreign objects that could not be removed are listed in Table 5. Several of the objects are sludge scale or hardened sludge fragments which are not considered to be credible threats to tube integrity but are documented for completeness. An engineering evaluation for the foreign objects remaining in the steam generators was completed, and the integrity of the steam generators until the next scheduled inspection is not affected.

No tube degradation was associated with any of the objects being tracked.

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Steam Generator Tube Inspection Report Attachment 1 Table 5 Turkey Point Unit 4 SG Secondary Side Foreign Objects Summary Table (Actively Tracked)

Status as of TP4-27 Initial TP4-23 TP4-24 TP4-25 TP4-27 Item SIG Description Location Location & Location & Location & Location &

And Basis Basis (111/06) Basis (4108) Basis 11/09 Basis 11/12 H/L R 12/13 ECT PLP Located in Wire bristle Not Seen by C 36 Object hard sludge imbedded in FOSAR 1/32" x 1 P" C3y embedded In sle hard deposit 11/18/2012 wire coil 38 ECT PLP hard sludge on retrieval seen by FOSAR at C36 tube. Retrieval attempted 11/10/09 unsuccessful attempted H/L R1i0/11 Seen by Seen by FOSAR Not Seen by C76/77 SSI Seen by FOSAR 11/10/09. No FOSAR 1/16" x 2" Report shows FOSAR 11/06 04/08, no retrieval 11/18/2012

2. 4A Weld Rod C75/76, Retrieval retrieval attempted, above entry attempts attempted, remains fixed in is in ENG unsuccessful fixed in location Eval R8 location Seen by FOSAR Seen by 0.4"dia by 11/10/09 FOSAR 0.13" Wedged tightly. 11/18/12

3. 4A Metal snap C45/46 N/A N/A Retrieval Wedged shaped Unsuccessful tightly.

object Retrieval Unsuccessful PLP (no wear)

Visual confirmed Not Seen by

4. 4A pilehard Small H/L R20 C36 N/A N/A 11/09. Retrieval FOSAR not possible. 11/18/2012 PLP (no wear) Not Seen by Adhered tube Visual confirmed FOSAR

5. 4A scale H/L R34 C62 N/A N/A 11/09. Retrieval 11/18/2012 not possible.

Seen by FOSAR Possible H/L 23-36 11/18/12

6. 4A Hard Deposit and 23-37 N/A N/A N/A Wedged tightly.

Retrieval Unsuccessful

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Steam Generator Tube Inspection Report Attachment 1 Table 5 (Cont.)

Turkey Point Unit 4 SG Secondary Side Foreign Objects Summary Table (Actively Tracked)

Status as of TP4-27 Initial TP4-23 TP4-24 TP4-25 TP4-27 Item S/G Description Location Location & Location & Location & Location &

And Basis Basis (11/06) Basis (4/08) Basis 11/09 Basis 11/12 PLP (no wear) Visually

- 0.25" Visual confirmed confirmed,

7. 4B irregular Hot Leg N/A N/A 11/09. Retrieval object round Sludge R13 C76 not possible. remains fixed Rock in place.

11/20/2012 Visually PLP (no wear) confirmed, Visual confirmed hard pile 11/09. greatly

8. 4B Hard sludge Hot Leg N/A N/A reduced due pile R17 C 42-58 to water lancing process 11/20/2012 PLP (no wear) Visually 0.5 x - 0.25 Visual confirmed confirmed,

9. 4B rectangular Hot Leg N/A N/A 11/09 object object sludge rock 58 wedged tightly. remains fixed Retrieval in place.

unsuccessful. 11/20/2012 PLP (no wear) Not Seen by 0.5" ECT verified Visual confirmed FOSAR

10. 4C oblong H/L R 20/21 presence ECT Skip 11/09 object 11/21/2012 metallic C 47 Based on look Cycle wedged tightly.

object back Retrieval unsuccessful.

Wedge PLP (no wear) Visually shaped Visual confirmed confirmed,

11. 4C sludge rock H/L R24 C33 N/A N/A 11/09 object object 0.1 x 0.3 x wedged tightly. remains fixed 1.5" Retrieval in place.

unsuccessful. 11/21/2012

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Steam Generator Tube Inspection Report Attachment 1

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TABLE 6 Turkey Point Unit 4 SG Secondary Side Foreign Objects Removed during TP4-27 Outage Initial Location TP4-27 Location & Basis Item SIG Description And Basis 1112012 H/L R22/23 C46 Legacy Item # 1 14A 1/16'x 2" Wire T-TS Retrieved by FOSAR 11/18/2012 Long rod shaped H/L R22 C44 Legacy Item # 6 (PLP) 2 4A -1 "x 0.1" TTS Retrieved by FOSAR

~2" above tubesheet 11/18/2012 H/L 44-47 and New and Retrieved by 4A Weld Slag 44-48 FOSAR TTS 11/18/2012 Small diameter C/L 23-46 and New and Retrieved by 4 23-45 FOSAR cTTS 11/18/2012 54A metalli rod TFOA New and Retrieved by 5 4Small diameter H/L 34-62 FOSAR 4A metal rod TTS1/821 H/L 2 1-62 and New and Retrieved by TTS 11/18/2012 4A Flat metallic object 21-61 FOSAR 6TATS 11/18/2012 H/L 42-61 and New and Retrieved by 7 4A Small twisted tie wire 42-62 FOSAR 11/18/2012 TTS Annulus H/L 20-47 and New and Retrieved by 4B Small cylindrical 20-48 FOSAR 8 metallic object 11/20/2012 TTS

L-2013-246 Page 1 of 3 Turkey Point Unit 4 (TP4-27) SG 4A Steam Generator Tube Inspection Report Attachment 2 SG 4A Indication Listings Listing Description Page No.

Tubes Plugged Listing (No Tubes Plugged) 2 Bobbin WEAR at AVB locations 20-1 00%TWD 2 Bobbin WEAR at AVB locations 1-19% TWVD 2 WEAR (WAR) sized by +PointTM probe 1-100% (Broach/Baffle) 3 I_________________

L-2013-246 Page 2 of 3 Turkey Point Unit 4 (TP4-27) SG 4A Steam Generator Tube Inspection Report Attachment 2 Turkey Point Unit 4 (EOC-26)

SG 4A Tubes Plugged Listing 12/12 - U4C27 EOC26 ECT Results for Tubes Plugged ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE Note: No tubes required plugging as a result of these inspections in steam generator (SG)4A Turkey Point Unit 4 (EOC-26)

SG 4A 12/12 - U4C27 Bobbin Wear at AVB's 20-100%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 33 72 0.64 0 P2 TWD 21 AVI +0.09 TEH TEC 15 COLD 720UL 37 65 0.73 0 P2 TWD 23 AV2 +0.00 TEH TEC 15 COLD 720UL 0.74 0 P2 TWD 24 AV4 +0.00 TEH TEC 15 COLD 720UL Total Tubes  : 2 Total Records: 3 Turkey Point Unit 4 (EOC-26)

SG 4A 12/12 - U4C27 Bobbin Wear at AVB's 1-19%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 26 20 0.22 0 P2 TWD 7 AVI +0.33 TEH TEC 4 COLD 720UL 30 16 0.22 0 P2 TWD 9 AV2 +0.00 TEH TEC 3 COLD 720UL 30 80 0.26 0 P2 TWD 10 AV2 -0.02 TEH TEC 17 COLD 720UL 32 74 0.45 0 P2 TWD 12 AVI +0.09 TEH TEC 16 COLD 720UL 0.40 0 P2 TWD 11 AV2 +0.07 TEH TEC 16 COLD 720UL 32 76 0.36 0 P2 TWD 10 AV4 -0.09 TEH TEC 16 COLD 720UL 33 72 0.36 0 P2 TWD 14 AV3 +0.00 TEH TEC 15 COLD 720UL 33 74 0.22 0 P2 TWD 10 AVI +0.07 TEH TEC 15 COLD 720UL 35 67 0.40 0 P2 TWD 11 AV4 -0.17 TEH TEC 16 COLD 720UL 37 20 0.28 0 P2 TWD 11 AVI +0.11 TEH TEC 3 COLD 720UL 0.35 0 P2 TWD 14 AV2 +0.20 TEH TEC 3 COLD 720UL 37 65 0.44 0 P2 TWD 16 AV3 +0.28 TEH TEC 15 COLD 720UL 42 63 0.26 0 P2 TWD 11 AV3 +0.52 TEH TEC 15 COLD 720UL Total Tubes  : 11 Total Records: 13

L-2013-246 Page 3 of 3 Turkey Point Unit 4 (TP4-27) SG 4A Steam Generator Tube Inspection Report Attachment 2 Turkey Point Unit 4 (EOC-26)

SG 4A 12/12 - U4C27

+PointPA WAR at Supports (Broach supports and Baffle plates)

ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 4 58 0.15 105 P5 WAR 02H +0.47 02H 02H 5 96910.1 37 HOT 680PP 13 4 0.30 95 P5 WAR BAR -0.28 BAH BAH 11 96910.1 36 HOT 680PP 91 P5 WAR BAH +0.09 BAH BAH 6 96910.1 36 HOT 680PP 39 28 0.14 Total Tubes  : 3 Total Records: 3 Notes: The qualified EPRI sizing technique used for depth estimates is identified in the Util 2 field.

For tubes identified with "WAR" in the "IND" column, the %TW depth is identified in the Util 1 field.

L-2013-246 Page 1 of 3 Turkey Point Unit 4 (TP4-27) SG 4B Steam Generator Tube Inspection Report Attachment 3 SG 4B Indication Listings Listing Description Page No.

Tubes Plugged Listing (Tube plugged for Foreign Object wear) 2 Bobbin WEAR at AVB locations 20-1 00%TWD 2 Bobbin WEAR at AVB locations 1-19% TWD 3 WEAR (WAR) sized by +PointTM probe 1-100% (Broach/Baffle) 3 J

L-2013-246 Page 2 of 3 Turkey Point Unit 4 (TP4-27) SG 4B Steam Generator Tube Inspection Report Attachment 3 Turkey Point Unit 4 (EOC-26)

SG 4B Tubes Plugged Listing 12/12 - U4C27 EOC26 ECT Results for Tube Plugged ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 17 74 0.13 126 P5 WAR 01H +0.70 01H 01H 5 96910.1 42 HOT 680PP 0 P5 CLP 01H +0.70 01H 01H 0.38 0.25 42 HOT 680PP 0.09 99 7 PLP 01H +0.70 01H 01H LAR 42 HOT 680PP PTP 01H +0.70 01H 01H LAR 42 HOT 680PP 0.18 124 P5 PID 01H +0.70 01H 01H 46 HOT 680PP 0.40 79 P1 DSI 01H +0.78 TEH TEC 12 COLD 720UL NDD TEH TSH 29 HOT 680PP Total Tubes  : 1 Total Records: 7 Note: This tube was preventively plugged due to wear associated with a foreign object that was still present Turkey Point Unit 4 (EOC-26)

SG 4B 12/12 - U4C27 Bobbin WAR at AVB's 20-100%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE Total Tubes  : 0 No indications were reported in this range.

Total Records: 0

L-2013-246 Page 3 of 3 Turkey Point Unit 4 (TP4-27) SG 4B Steam Generator Tube Inspection Report Attachment 3 Turkey Point Unit 4 (EOC-26)

SG 4B 12/12 - U4C27 Bobbin WAR at AVB's 1-19%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 13 42 0.28 0 P2 TWD 11 AVI +0.00 TEH TEC 19 COLD 720UL 21 6 0.33 79 P2 TWD 12 AV3 +0.00 TEC TEH 11 HOT 720UL 23 50 0.39 0 P2 TWD 11 AV3 +0.00 TEH TEC 14 COLD 720UL 23 85 0.32 0 P2 TWD 12 AV3 -0.21 TEC TEH LAR 3 HOT 720UL 26 83 0.27 0 P2 TWD 11 AV2 +0.00 TEC TEH LAR 3 HOT 720UL 27 72 0.39 0 P2 TWD 11 AVI +0.04 TEH TEC 14 COLD 720UL 0.40 0 P2 TWD 11 AV2 +0.11 TEH TEC 14 COLD 720UL 27 82 0.28 0 P2 TWD 8 AV4 +0.24 TEH TEC 14 COLD 720UL 30 65 0.51 0 P2 TWD 17 AV2 +0.31 TEH TEC 13 COLD 720UL 0.32 0 P2 TWD 12 AV3 +0.11 TEH TEC 13 COLD 720UL 30 73 0.31 0 P2 TWD 12 AV2 +0.13 TEH TEC 13 COLD 720UL 0.34 0 P2 TWD 13 AV3 +0.09 TEH TEC 13 COLD 720UL 0.40 0 P2 TWD 14 AV4 -0.09 TEH TEC 13 COLD 720UL 31 13 0.29 0 P2 TWD 11 AV4 +0.02 TEH TEC 1 COLD 720UL 33 16 0.32 0 P2 TWD 12 AV4 +0.00 TEH TEC 1 COLD 720UL 0 P2 TWD AV2 -0.26 TEH TEC 16 COLD 720UL 33 62 0.31 10 34 46 0.54 114 P2 TWO 17 AV2 -0.50 TEH TEC 7 COLD 720UL 0.39 30 P2 TWD 14 AV2 +0.70 TEH TEC 7 COLD 720UL 35 54 0.51 0 P2 TWD 17 AV3 +0.22 TEH TEC 15 COLD 720UL 38 58 0.33 0 P2 TWD 10 AV3 +0.07 TEH TEC 16 COLD 720UL Total Tubes  : 15 Total Records: 20 Turkey Point Unit 4 (EOC-26)

SG 4B 12/12 - U4C27

+PointTM WAR at Supports (Broached support and Baffle Plates)

ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 5 12 0.27 88 P5 WAR 04H +0.44 04H 04H 11 96910.1 42 HOT 68=0=PP 5 86 0.08 147 P5 WAR 01H +0.74 01H 01H 3 96910.1 42 HOT 680PP 9 80 0.13 112 P5 WAR 02H +0.47 02H 02H 5 96910.1 42 HOT 680PP 17 74 0.13 126 P5 WAR 01H +0.70 01H 01H 5 96910.1 42 HOT 680PP 19 86 0.24 98 P5 WAR BAH -0.25 BAH BAH 10 96910.1 42 HOT 680PP 0.24 103 P5 WAR BAB -0.22 BAH BAH 10 96910.1 42 HOT 680PP 28 80 0.15 106 P5 WAR 05H -0.55 05H 05H 6 96910.1 42 HOT 680PP 31 60 0.40 102 P5 WAR 02H -0.27 02H 02H 16 96910.1 42 HOT 680PP 35 70 0.19 102 P5 WAR BAH -0.36 BAN BAH 8 96910.1 42 HOT 680PP 40 25 0.11 146 P5 WAR 01C +0.40 01C 01C 5 96910.1 37 COLD 680PP 40 26 0.17 105 P5 WAR BAR -0.28 BAH BAN 7 96910.1 42 HOT 680PP 0.15 105 P5 WAR BAH +0.19 BAH BAH 6 96910.1 42 HOT 680PP 44 38 0.37 121 P5 WAR 04C +0.51 04C 04C 14 96910.1 37 COLD 680PP Total Tubes  : 11 Total Records: 13 Note: The qualified EPRI sizing technique used for depth estimates is identified in the Util 2 field. For tubes identified with "WAR" in the "IND" column, the %TW depth is identified in the Util 1 field.

L-2013-246 Page 1 of 3 Turkey Point Unit 4 (TP4-27) SG 4C Steam Generator Tube Inspection Report Attachment 4 SG 4C Indication Listings Listing Description Page No.

Tubes Plugged Listing (No tubes plugged) 2 Bobbin WEAR at AVB locations 20-1 00%TWD 2 Bobbin WEAR at AVB locations 1-19% TWD 2 WEAR (WAR) sized by +PointTM probe 1-100% (Broach/Baffle) 3

L-2013-246 Page 2 of 3 Turkey Point Unit 4 (TP4-27) SG 4C Steam Generator Tube Inspection Report Attachment 4 Turkey Point Unit 4 (EOC-26)

SG 4C Tubes Plugged Listing Note: No tubes required plugging as a result of these inspections in steam generator (SG)4C Turkey Point Unit 4 (EOC-26)

SG 4C 12/12 - U4C27 Bobbin WAR at AVB's 20-100%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 32 16 0.52 0 P2 TWD 20 AV2 +0.09 TEH TEC 28 COLD 720UL 35 31 0.91 0 P2 TWD 28 AV2 +0.24 TEH TEC 28 COLD 720UL Total Tubes  : 2 Total Records: 2 Turkey Point Unit 4 (EOC-26)

SG 4C 12/12 - U4C27 Bobbin WAR at AVB's 1-19%TWD ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 12 4 0.31 0 P2 TWD 13 AV4 +0.25 TEH TEC 23 COLD 720UL 13 4 0.37 0 P2 TWD 10 AV4 -0.23 TEH TEC 22 COLD 720UL 22 7 0.25 0 P2 TWD 11 AV2 -0.06 TEH TEC 23 COLD 720UL 22 82 0.23 143 P2 TWD AVI +0.31 TEH TEC 19 COLD 720UL 22 83 0.24 0 P2 TWD 7 AV4 -0.13 TEC TEH 5 HOT 720UL 24 12 0.35 0 P2 TWD 15 AV4 -0.15 TEH TEC 28 COLD 720UL 26 82 0.30 125 P2 TWD 13 AVI +0.24 TEH TEC 19 COLD 720UL 27 80 0.22 88 P2 TWD 7 AV3 +0.02 TEH TEC 18 COLD 720UL 27 81 0.26 113 P2 TWD 12 AVI +0.17 TEH TEC 19 COLD 720UL 0.33 67 P2 TWD 14 AV4 +0.00 TEH TEC 19 COLD 720UL 30 15 0.33 0 P2 TWD 14 AVI +0.15 TEH TEC 28 COLD 720UL 30 75 0.25 0 P2 TWD 7 AV2 +0.35 TEH TEC 16 COLD 720UL 31 80 0.32 0 P2 TWO 13 AV3 -0.04 TEH TEC 30 COLD 720UL 32 70 0.65 0 P2 TWD 17 AVI -0.34 TEH TEC 16 COLD 720UL 0.47 0 P2 TWD 13 AV3 -0.07 TEH TEC 16 COLD 720UL 33 76 0.25 0 P2 TWD 7 AVi +0.13 TEH TEC 29 COLD 720UL 34 17 0.27 0 P2 TWD 7 AVl -0.11 TEH TEC 1 COLD 720UL 34 53 0.22 0 P2 TWD 7 AVl -0.21 TEH TEC 16 COLD 720UL 34 75 0.32 0 P2 TWD 9 AV4 +0.00 TEH TEC 16 COLD 720UL 36 74 0.24 1il P2 TWD 11 AV3 -0.02 TEH TEC 14 COLD 720UL 37 71 0.13 0 P2 TWD 4 AVi +0.02 TEC TEH 40 HOT 720UL 37 73 0.28 113 P2 TWD 13 AV3 -0.20 TEH TEC 14 COLD 720UL 39 69 0.26 34 P2 TWD 12 AV2 -0.20 TEH TEC 14 COLD 720UL 40 68 0.19 0 P2 TWD 9 AV2 -0.26 TEH TEC 14 COLD 720UL Total Tubes  : 22 Total Records: 24

L-2013-246 Page 3 of 3 Turkey Point Unit 4 (TP4-27) SG 4C Steam Generator Tube Inspection Report Attachment 4 Turkey Point Unit 4 (EOC-26)

SG 4C 12/12 - U4C27

+PointTM WAR at Supports (Broach support and Baffle Plate)

ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 28 82 0.18 0 P5 WAR BAH +0.44 BAH BAH 7 96910.1 48 HOT 68===PP 35 75 0.24 0 P5 WAR 06H +0.35 06H 06H 10 96910.1 48 HOT 680PP Total Tubes  : 2 Total Records: 2 Note: The qualified EPRI sizing technique used for depth estimates is identified in the Util 2 field. For tubes identified with "WAR" in the "IND" column, the %TW depth is identified in the Util 1 field.