ML052020050

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Generator In-Service Inspection Report Unit 2, End of Cycle (EOC) 16
ML052020050
Person / Time
Site: Mcguire
Issue date: 07/07/2005
From: Gordon Peterson
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052020050 (17)
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Text

Duke GARY R. PETERSON

  • wPowere Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MGO0 VP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy.com July 7, 2005 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

Subject:

McGuire Nuclear Station Docket Nos. 50-370 Steam Generator In-Service Inspection Report Unit 2, End of Cycle (EOC) 16 Pursuant to ASME Section XI, Paragraph IWA-6230, Duke Energy Corporation hereby submits the attached Inservice Inspection (ISI) Outage Summary Report for McGuire Unit 2 EOC 16.

Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Compliance (704) 875-4306.

Gary R. Peterson Attachment www.duke-energy.com rn D

U. S. Nuclear Regulatory Commission Document Control Desk July 7, 2005 Page 2 cc: W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St. Suite 23T85 Atlanta, GA 30303 S. E. Peters NRC Senior Project Manager (MNS)

U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Joe Brady Senior Resident Inspector (MNS)

U. S. Nuclear Regulatory Commission

Steam Generator Outage Summary Report McGuire Unit 2 2005 Outage EOC 16 Location: 12700 Hagers Ferry Rd, Huntersville, NC 28078 NRC Docket No. 50-370 National Board No. 84 Commercial Service Date: March 1, 1984 Owner: Duke Energy Corporation 526 South Church St.

Charlotte, N.C. 28201-1006 Revision 0 Prepared By: .

  • s _

Date: 4-4V/-

Reviewed By: y&'p Date: C,- z4-or 3SAH~I Approved By: Date: v_______

Copy No. I Assigned To: DCD J

Controlled: Controlled: Uncontrolled:

ControlledDistribution Copy No. Assigned To Original McGuire Nuclear Station Document Control Master File MC 1201.35 1 NRC Document Control UncontrolledDistribution 2 Hartford Steam Boiler Inspection and Insurance Corporation (AIA) 3 State of North Carolina Department of Labor C/o J. M. Givens, Jr.

FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner: Duke Energy Corporation. 526 S. Church St.. Charlotte. NC 28201-1006 (Name and Address of Owner)
2. Plant: McGuire Nuclear Station. 12700 Hagers Ferry Rd. Huntersville, NC 28078 (Name and Address of Plant)
3. Plant Unit: 2
4. Owner Certificate of Authorization (if required) N/A
5. Commercial Service Date: March 1, 1984
6. National Board Number for Unit 84
7. Components Inspected:

Manufacturer State or National Component Manufacturer Serial No. Province No. Board No.

Steam Generator 2A BWI 7700-02 NC-302674 159 Steam Generator 2B BWI 7700-04 NC-302675 161 Steam Generator 2C BWI 7700-01 NC-302676 158 Steam Generator 2D BWI 7700-03 NC-302677 160 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-1 (Back)

8. Examination Dates March 16, 2005 to April 1, 2005
9. Inspection Period Identification: 1st Period
10. Inspection Interval Identification: 3rd Inspection Interval
11. Applicable Edition of Section XI 1998 Addenda 2000
12. Date/Revision of Inspection Plan: March 1st, 2004 Rev 0
13. Abstract of Examinations and Test. Reference attached Eddy Current Examination Technical Summary Rev 1 report dated 6/22/05.
14. Abstract of Results of Examination and Tests. Reference attached Eddy Current Examination Technical Summary Rev 1 report dated 6/22/05.
15. Abstract of Corrective Measures. Reference attached Eddy Current Examination Technical Summary report Rev 1 dated 6/22/05.

We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) NA Expiration Date NA Date -4#2-2 20 _5 Signed uke Energy Corp. By X47 (.

Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission iss elyy the National Board of Boiler and Pressure Vessel Inspctors and the State of Province of jL, employed by/L'Q3*ciof (L'sE- -It/ ave ins e ted the components described in this Ownersi Report during the period InI(c/ Lor 3 to V7,Q'1y4 2 H0eSi... __,and state that to the best of my knowledge and belif, the Owner has performed examinations and tests and taken corrective measures described in the Ownersi Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Ownersi Report.

F~urthermore, neither te Inspector nor his employer shall be liable in any manner for any personal or property da age or a loss of any kind arising from or connected with this inspection Inspeitor/Signature F Commissions A)(,- /590 V iJU 4 National Board, State, Province, and Endorsements

( Date a& 20 ds

20032-33 (6/23/2004 EA RELEASE DATE AO la At DOCUMENT RE RELEASE VARM NOTICE INITIALS I

AREVA CONTRACT NUMBER PLANT CC OR CHARGE NUMBER 1011678 McGuire Nuclear Station 12324 PAGE 1 OF I PART OR TASK No. DOCUMENT SAFETY PUL COLD COM (N/A If Not Appricable) NUMBER DOCUMENT TITLE CLASS (YN)(YN) (Y/N)

______________ _____________________________(SINS)(YN

________________ (Y)(Y)

N/A 51-5064658-01 McGuire Nuclear Station Unit 2 EOC 16 Eddy S N N N

___ ____ ____ ____ ___ Current Examination Technical Summary_ _ _ _

KEYWORDS (For Informational Purposes Only) SPECIAL REQUESTS LABEL lCCPIES 0 CD OF COLD I 0 OTHER (Specify Below i.e. Reproduction Instructions)

INFORMATIONAL DISTRIBUTION (Electronic Notification Only) REQUIRED DISTRIBUTION MAIL CODE COPIES Brown, Jerry Street Bill Boudreaux, Mike Angelakis, George Cecil, Bill Murphy, Rusty TOTAL NUMBER OF HARDCOPIES (STAPLED IS DEFAULT UNLESS SPECIAL REQUEST)

RELEASED BY (PRINT NAME) REVIEWED BY (PRINT NAME) PM FUNCTIONAL APPROVAL * (FAPPLICABLE)

Jeffrey C. Grigsby D ,R. Gr~ ene Jeni;rown 6-22-05m_ 6-22_09;.

E AT6-22-05l SIGNATURE 6 DATE 6-22-05 s t ,-IREGUEATORY, FAIPNS O -. RETURN ORIGINAL TO:

REGULATORY AFFAIRS (IF APPLICABLE) TECHNICAL MANAGER (IF APPLICABLE)S

-N/A[N/A Jeffrey C. Grigsby AEXTENSION MDNL CODE

.,SIGNATURE DATE SIGNATURE DATE - 3562 MR12 See DRN Instructions for signature requirements Refer to Procedure 0412-66 Framatome ANP, Inc., an AREVA and Siemens company

Page I of 10 20440-11 (3130/2004)

J%6 ENGINEERING INFORMATION RECORD AR EVA Document Identifier 51 - 5064658 - 01 Title McGuire Nuclear Station Unit 2 EOCI6 Eddy Current Examination Technical Summary PREPARED BY: REVIEWED BY:

Name Jeffrey C. Grigsby Name Deis Greene Signature 4 Ha  :<<* Date 6-22-05 Signatur aate 6-22-05 Technical Manager Statement: Initials g Reviewer is Independent.

Remarks:

This report summarizes the results of the eddy current examinations performed on the tubes in all four steam generators at Duke Power Company's McGuire Nuclear Station Unit 2 during the 16t refueling outage (EOC16)

Framatome ANP Inc., an AREVA and Siemens company

51-5064658-01 Page 2 ofO10 1L0 Introduction Eddy current examinations were performed on the .688" O.D. x 0.040" wall Inconel 690 tubing in all four steam generators during McGuire's Nuclear Station's Unit 2 Refuieling Outage sixteen (16).

2.0 Technical Summary This section provides a technical summary of the eddy current examinations performed at Duke Energy's McGuire Nuclear Station Unit 2 Refueling Outage sixteen (16).

McGuire Unit 2 has the following design characteristics: 1,180 MW Pressurized Water Reactor (PWR) Westinghouse 4 loop Nucleat Steam Supply System (NSSS). The steam generators are Babcock & Wilcox International (BWI) CFR80 vertical U-bent type containing 6,633 tubes each. Personnel fiom FANP performed the examinations during the 16 th refueling outage.

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/at A-. Ito - /_,z A .540" diameter tuned bobbin coil ancyarray coil combination probe was used to perform a full length examination of 6630 tubes in steam generator A, 3760 tubes in steam generator B, 3834 tubes in steam generator C and 6629 tubes in steam generator D. The array coil data was utilized for the top of tubesheet examinations of 2008 tubes in steam generator A, 1908 tubes in steam generator B, 1892 tubes in steam generator C and 1989 tubes in steam generator D. The array coil data was utilized for possible loose parts (PLP) examination of 814 tubes in steam generator A, 814 tubes in steam generator B, 814 tubes in steam generator C, and 814 tubes in steam generator D. All existing plugs were visually inspected with no indications of leakage present. 17 tubes were removed from service in steam generator A; no tubes were removed from service in steam generators B, C and D.

51-5064658-01 Page 3 of 10 2.1 Summary The following summarizes the results of eddy current examinations fox all four steam generators.

Note: Attachment I contains a list of all three-lettei codes and acronyms used throughout this report. Attachment 2 contains the eddy current results fiom all four CFR80 steam generators for McGuire Unit 2 Refueling Outage 16.

A S/G:

  • Eddy current examinations began on 3/16/05 @ 0153 and were completed on 3/25/05 @ 0255.
  • 6630 tubes were examined with a bobbin coil probe.
  • 1 tube was reported to have indications of 40% TW or greater with the bobbin or awiay coil probes..
  • 7 tubes were reported to have 8 indications of 20 - 39% TW or greater with the bobbin or array coil probes.
  • 170 tubes were examined for Special Interest Locations.
  • 2008 Hot leg top-of-tubesheets were examined fiom the tube end to 2" above the tubesheet.
  • 814 Periphery hot leg top-of-tubeshects were examined for possible loose parts (PLP).
  • 13 tubes were removed from service by plugging based on the eddy current results.
  • 4 tubes were removed from service due to inadvertent tube end repair.
  • See Attachment 2 for details.

B S/G:

  • Eddy current examinations began on 3/16/05 @ 1926 and weie completed on 3/24/05 @ 0131.
  • 3760 tubes were examined with a bobbin coil probe.
  • 0 tubes were reported to have indications of 40% TW or greater with the bobbin or array coil probes.
  • 0 tubes were reported to have indications of 20 - 39% 1W or greater with the bobbin or array coil probes.
  • 24 tubes were examined for Special Interest Locations.

1908 Periphery hot leg top-of-tubesheets were examined from the tube end to 2" above the tubesheet.

  • 814 Hot legs top-of-tubesheets were examined for possible loose parts (PLP).
  • 0 tubes were removed from service by plugging.
  • See Attachment 2 for details.

51-5064658-01 Page 4 of 10 C S/G:

  • Eddy current examinations began on 3/16/05 @ 1813 and were completed on 3/24/05 @ 0332.
  • 3834 tubes were examined with a bobbin coil probe.
  • 0 tubes were reported to have indications of 40% TW or greater with the bobbin or array coil probes.
  • 1 tube was reported to have 1 indication of 20 - 39% 1W or greater with the bobbin or airay coil probes.
  • 190 tubes were examined for Special Interest Locations.
  • 1892 Hot leg topof-tubeshects were examined from the tube end to 2" above the tubesheet.
  • 814 Peripheiy hot legs top-of-tubesheets were examined for possible loose parts (PLP).
  • 0 tubes were removed from service by plugging.
  • See Attachment 2 for details.

D S/G:

  • Eddy current examinations began on 3/16/05 @ 0220 and were completed on 3/24/05 @ 2231.
  • 6629 tubes were examined with a bobbin coil probe.
  • 0 tubes were reported to have indications of 40% TW or greater with the bobbin or array coil probes.
  • 1 tubes was reported to have 1 indication of 20 - 39% TW or greater with the bobbin or alray coil probes.
  • 126 tubes were examined for Special Interest Locations.
  • 1989 Hot leg top-of-tubesheets were examined from the tube end to 2" above the tubesheet.
  • 814 Periphery hot legs top-of-tubesheets were examined for possible loose parts (PLP)
  • 0 tubes were removed from service by plugging.
  • See Attachment 2 for details.

51-5064658-01 Page 5 of 1O 2.2 Examinations The examinations, analysis, equipment and personnel were in compliance with the requirements of the FANP Multi-Frequency Eddy Current Examination of Tubing (ISI-400) latest revision, Written Practice for Personnel Qualification in Eddy Current Examination (ISI-24) latest revision, Eddy Current Acquisition Guidelines forx Duke Power Company's CFR80 Steam Generator and Eddy Current Analysis Guidelines for Duke Power Company's CFR80 Steam Generators.

The steam generator tubing examinations were performed by technicians qualified to Level II, IIA, or Level I under direct supervision of personnel qualified to Level II in accordance with FANP procedure ISI-24, latest revision. The data was evaluated by personnel qualified to a minimum of Level IIA in accordance with FANP procedure ISI-24, latest revision. The examination and evaluation procedures and guidelines were reviewed and approved by personnel qualified to Level III in accordance with FANP procedure 1SI-24, latest revision. All inspection fiequencies were generated using a Zetec TC-7700 remote data acquisition unit.

The bobbin and alray coil examinations were performed with 0.540" diameter probes. The inspection frequencies used were 650, 320, 170 and 70 k.Hz operating in differential and absolute modes. A 650/170 kHz differential tube support plate suppression mix was used to enhance the detection of indications occurring at TSP and TS intersections.

The special interest examinations were performed with 0.540" diameter ariay probes. The inspection frequencies were 650, 320, 170 and 70 kHz.

A 320/170 kHz tube support plate suppression mix was used to enhance the detection of indications occurring at TSP and TS intersections Official results of the data analysis were recorded on optical disks and verified by two Eddy Current Data management systems: Fiamatome Data Management System, (FDMS) and EddyNet Inspection management System, (EIMS). These systems were used to check the data results for invalid analysis entries, perform data sorting routines, and ensure all the required tubes were examined.

51-5064658-01 Page 6 of' 10 2-3 Areas of'Concein Eddy current examinations cannot, in all cases, determine the actual cause of'damage. The signal recorded during the eddy current examination can be used to estimate the physical size of any tube damage detected, i.e.

penetration into the wall, axial extent. However the actual type of degradation and its cause can only be determined by tube removal and metallurgical studies.

2.3.1 Loose Parts - Loose parts, or damage attributed to loose parts impact or fietting, may be present adjacent to tubes in the periphery. Indications of loose parts and damage associated with loose parts have been detected in the CFR80 Steam Generators.

2.3.2 Mechanical Wear- Indications indicative of TSP or FB weal have been identified and reported in the CFR8O Steam Generators.

Analysts were trained for wear, type indications and reported indications indicative of wear in accordance with the guidelines.

2.3.3 lube-to-Tube Contact - Tube-to-Tube contact/proximity has been identified as an area of concein for the CER80 replacement steam generators. A number of tubes in the CFR80 design steam generators have been identified as representative of tubes that are in close proximity. The area of concern is the entire u-bend area were monitored for indications indicative of degradation. Any indications indicative of tube-to-tube contact wear shall was reported in accordance with the guidelines.

2.4 Results Attachment 2 details the results ofthe various eddy current examinations performed in all four Steam Geneiator's.

51-5064658-01 Page 7 of 10 Attachment I Bobbin Characteuization Codes CODE DESCRIPTION I ADI Absolute DIift Indication 2 BLG Bulge 3 BOR Boron 4 CHT Chatter 5

  • CHG Histofical comparison has been performed and indication has Changed based on the criteria 6 DNT Dent 7 DW] Dent With Indication 8 FC Final Calibration 9 FCL Final Calibration Late 10 HNI Historical comparison has been performed and indication has Not changed based on the criteria II ICR Incomplete Roll 12 IC Initial Calibration 13 IV Independent Verification of tube identification 14
  • IDOK lube ID Verified; This code shall be used to identify tubes acquired more than once duting the current outage Use of this code requires tube to tube comparison or fingerprinting of the affected tube(s) 15 INF Indication Not Found 16 INR Indication Not Reportable 17 IRR Irregular Roll 18
  • L3R Level 11 Review 19 MSG Analyst Message 20 NEX No Expansion 21 NFC No Final Calibration 22 NQI Non-Quantifiable Indication 23 NSR Needs SGME Review 24 OBS Obstructed 25 OVR Over Roll 26 OXP Over Expansion 27 PID Positive Identification 28
  • PLG Plugged lube 29 PLP Possible Loose Parts 30 PVN Permeability Variation 31 RBD Retest - Bad Data 32 RFB Retest - Fan Bai using a wear standard for sizing 33 RIC Retest - Incomplete 34 RNC Retest - Tube Number Check-35 ROB Retest - Obstructed 36 RRC Retest - Rotating Coil 37 RPD Retest - Positive Identification 38 SAT Satisfactory 39 SLG Sludge 40 SKR Skip Roll 41 WAR Wear 42 WTG Wetting/Leaking
  • Denotes code to be used in the "UTIL I" field

51-5064658-01 Page8of 10 MRPC/Anay Characteiization Codes

  1. CODE DESCRIPTION 1 AXI Axial Indication 2 DNT Dent 3 DPS Potential Deposit at Support structures 4
  • 13R Level III Review 5 MAI Multiple Axial Indication 6 MCI Multiple Circumferential Indication 7 MMI Mixed-Mode Indication 8 MSG Analyst Message 9 MVI Multiple Volumetric Indications 10 NDF No Defect Found 11 + NQS Non-Quantifiable Signal 12 OBS Obstructed 13 PID Positive Identification 14 PLP Possible Loose Part 15 PVN Permeability Variation 16 RBD Retest - Bad Data 17 RIC Retest - Incomplete 18 RNC Retest - lube Number Check 19 ROB Retest - Obstructed 20 SAI Single Axial Indication 21 SCI Single Circumferential Indication 22 SVI Single Volumetric Indication 23 VOL Volumetric 24
  • WAR Weat Denotes code to be used in the "UTIL 1" field.

+ Code foi Resolution analysts only.

51-5064658-01 Pagc 9 of 10 Attachment 2 McGuite Unit 2 EOC 16 CFR80 Eddy Cuxient Results Bobbin Examinations Steam Generator "A" Steam Generator 9B" Tubes rested: 6630 1f Tubes Tested: 3760 Tubes with Number of Tubes with Number of Indications Indications Indications Indications TWD > 40% 1 1 0 0 TWD 20-39% 7 8 0 0 TWD <20% 58 63 33 36 ADI 23 23 5 5 DNT 1 2 0 0 HNI 14 16 17 17 TNF 0 0 0 0 INR 3 3 6 7 NQI4 4 0 0 PLP 24 29 7 13 PVN 0 0 .0 0 Steam Generator "C" Steam Generator "D" Tubes Tested: 3834 Tubes Tested: 6629 Tubes with Number of Tubes with Number of Indications Indications Indications Indications TWD > 40% 0 0 0 0 TVD 20-39% 1 1 0 0 TWD < 20% 62 63 50 58 ADI 12 14 7 7 DNT 4 5 0 0 HNI 10 12 6 8 INF 19 20 0 0 INR 7 10 1 I NQI 1 1 3 3 PLP 64 78 17 19 PVN 0 0 0 0

5 1-5064658-0 1 Page 10 of 10 Special Inteiest: including PLP bounding, HL-TIS examinations and Periphety PLP examinations.

Steam Gcnerator "A" Steam Generator "B" Tubes Tcsted: 2992 _ _ Tubes Tested: 2746 Tubes with Number of Tubes with Number of Indications Indications Indications Indications Fan Bar Wear 52 59 31 34 TSP Wear 8 9 2 2 Loose Part Wear 5 7 0 0 DNT 1 2 0 0 MAI 0 0 0 0 MCI 0 0 0 0 MMI 0 0 0 0 MVI 0 0 0 0 PLP 24 29 7 13 SAI 0 0 0 0 SCI 00 0 0 SVI 9 9 0 0 VOL 38 40 7 9 Steam Generator "C" Steam Generator "D" Tubes Tested: 2896 Tubes Tested: 2929 Tubes with Number of Tubes with Number of Indications Indications Indications Indications Fan Bar Wear 63 64 51 59 TSP Wear 0 0 0 0 Loose Part Wear 0 0 0 0 DNT 4 5 0 0 MAI 0 0 0 0 MCI 0 0 0 0 MMI 0 0 0 0 MVI 0 0 0 0 PLP 64 78 17 19 SAI 0 0 0 0 SO 0 0 0 0 SVI 0 0 0 0 VOL 10 12 18 19

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