ULNRC-05450, Results of First Replacement Steam Generator Tube In-Service Inspection

Results of First Replacement Steam Generator Tube In-Service Inspection

ML073050323
Person / Time
Site:	Callaway
Issue date:	10/25/2007
From:	Diya F AmerenUE
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-05450
Download: ML073050323 (11)

Text

AmerenUE P0 Box 620 Ca//away P/ant Fulton, MO 65251 October 25, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555-0001 Ladies and Gentlemen: ULNRC-05450 DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC COMPANY FACILITY OPERATING LICENSE NPF-30 WA mreon RESULTS OF FIRST REPLACEMENT STEAM GENERATOR TUBE UE IN-SERVICE INSPECTION In accordance with Callaway Plant Technical Specification 5.6.10, the attached report provides the results of Callaway Plant's first replacement steam generator tube in-service inspections. The attachment, "Special Report: Results of First Replacement Steam Generator Tube In-Service Inspection", includes the following:

a. The scope of inspections performed on each steam generator;

b. Active 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 active degradation mechanism; f Total number and percentage of tubes plugged to date; and

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

No commitments are contained in this correspondence. If you have any questions concerning this matter, please contact me at (573) 676-6411 or Mr. Ryan Reed at (573) 676-4747.

Very truly yours, Fadi M. Diya Plant Director DJW/nls

Attachment:

Special Report: Results of First Replacement Steam Generator Tube In-Service Inspection (8 pages) a subsidiary of Ameren Corporation

ULNRC-05450 October 25, 2007 Page 2 cc: Mr. Elmo E. Collins, Jr.

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-8G14 Washington, DC 20555-2738

ULNRC-05450 October 25, 2007 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and public disclosed).

Electronic distribution for the following can be made via Other Situations ULNRC Distribution:

C. D. Naslund A. C. Heflin F. M. Diya L. H. Graessle G. A. Hughes S. A. Maglio S. L. Gallagher L. M. Belsky (NSRB)

R. H. Reed Ms. Diane M. Hooper Mr. Dennis Buschbaum Supervisor, Licensing TXU Power WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Stan Ketelsen Regulatory Affairs Manager, Regulatory Services Palo Verde NGS Pacific Gas &,Electric P.O. Box 52034, Mail Stop 104/5/536 Mail Station 7636 P.O. Box 56 Phoenix, AZ 85072-2034 Avila Beach, CA 93424 Mr. Scott Head Mr. John O'Neill Supervisor, Licensing Pillsbury Winthrop Shaw Pittman LLP South Texas Project NOC 2300 N. Street N.W.

Mail Code N5014 Washington, DC 20037 P.O. Box 289 Wadsworth, TX 77483 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360

\,

Attachment 1 to ULNRC-05450 SPECIAL REPORT RESULTS OF FIRST REPLACEMENT STEAM GENERATOR TUBE IN-SERVICE INSPECTION REPORTING REQUIREMENTS:

Technical Specification AC 5.6.10 requires that a report shall be submitted within 180 days after initial entry into MODE 4 following completion of an inspection in accordance with Specification 5.5,9, Steam Generator (SG) Program. This report shall include:

a. The scope of inspections performed on each steam generator;

b. Active degradation mechanisms found;

c. Nondestructive examination techniques utilized for each degradation mechanism found;

d. Location, orientation (if linear), and measured size (if available) of service induced degradation;

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

f. Total number and percentage of tubes plugged to date, and

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

SUMMARY

The first replacement steam generator tube in-service inspections were completed by Areva during the Refuel 15 outage. An in-service inspection was performed on all four steam generators. The scope of inspections performed are described in the following Inspection Report. Callaway found no active degradation mechanisms. However, anti-vibration (AVB) wear was found in all four steam generators in a small quantity of tubes.

For AVB wear, the non-destructive examination technique used was EPRI Examination Technique 96004.1. Table 1 provides the eddy current testing task summary for tubes inspected. Table 2 provides the summary of wear indications found for all four steam generators. Callaway did not perform repairs to any tubes because no tubes exceeded the repair criteria. In addition, the Condition Monitoring Report concluded that the Callaway steam generator tubes satisfied the structural integrity performance criterion, accident induced leakage criterion, and operational leakage criterion.

INSPECTION REPORT:

The Callaway Plant 1 5 th refueling outage occurred in the spring of 2007. The plant started up and reached MODE 4 on April 25, 2007. During this period an in-service inspection was performed on all four steam generators. The inspection scope was as follows:

• 100% full length (bobbin coil) examination of all four steam generators

• Periphery tube top of tubesheet (TTS) RPC (+Point) examination of all four steam generators

• Special interest RPC (+Point) of bobbin coil indications as required Page 1 of8

Attachment 1 to ULNRC-05450 Table 1 Eddy Current Testing Task Summary (Tubes Inspected)

Extent S/G A S/G B S/G C S/G D ECT Task Total 100% Bobbin Tube end hot to 5535 5536 5536 5536 22143 F/L tube end cold MRPC Top of Tubesheet 935 935 935 935 3740 periphery +31"-3" tubes MRPC S.I. Specified 40 48 52 35 175 location (Note: I tube plugged in S/G A during manufacturing)

Callaway found no active degradation mechanisms. However, anit-vibration bar (AVB) wear was found in all 4 steam generators in a small quantity of tubes. For AVB wear, the nondestructive examination technique used was EPRI Examination Technique 96004.1.

Callaway found a total of 36 tubes with AVB wear.

Table 2 Summary of Wear Indications Steam Row Column Location Size (%TW)

Generator AV3 +0.06 5 AV4 +0.24 5 A 77 51 AV3 -0.02 5 AV3 -0.08 4 AV4 +0.13 7 AV2 +0.06 6 AV3 +0.06 9 A 78 76 AV2 -0.12 9 AV3 +0.02 6 AV3-0.09 8 AV2 +0.13 10 AV4 +0.00 13 AV5 +0.00 9 A 85 63 AV3 +0.04 9 AV2 -0.04 5

AV2 +0.02 8 AV3 -0.05 3 AV3 +0.06 8 Page 2 of 8

Attachment 1 to ULNRC-05450 Steam Geeat Row Column Location Size (%TW)

Generator AV4 -0.07 3 85 63 AV4 +0.09 11 A

AV5 -0.01 6 AV5 +0.03 6 AV4 +0.09 6 A 92 82 AV4 +0.05 6 AV4 -0.05 5 AV3 +0.11 6 AV4 +0.06 3 AV3 +0.05 6 A 96 66 AV3 +0.11 4 AV4 +0.03 2 AV4 -0.08 5 AV1 +0.02 4 AV2 +0.04 6 AV3 +0.06 9 AV4 +0.06 5 A 98 66 AV1 +0.19 4 AV1 -0.21 6 AV2 -0.02 8 AV3 +0.04 5 AV3 +0.08 8 AV4 +0.01 8 AV1 +0.22 3 AV2 +0.15 5 AV3 +0.06 6 AV4 +0.09 3 AV5 +0.24 5 AV1 +0.01 3 A 99 .67 AV1 +0.17 3 AV2 -0.04 5 AV2 -0.10 2 AV3 -0.03 5 AV3 +0.03 4 AV4 -0.09 2 AV5 +0.09 7 AV6 +0.17 2 A 104 64 AV6 -0.10 3 Page 3 of 8

,i Attachment 1 to ULNRC-05450

[Steam]

Geeat Row Column Location Size (%TW)

Generator AVI -0.11 6 AV2 +0.13 8 AV3 +0.09 10 AV4 +0.09 5 107 65 AV5 +0.15 3 A

AV1 -0.09 9 AV2 +0.04 10 AV3 -0.07 12 AV4 +0.01 7 AV5 +0.01 5 AV6 -0.13 5 AV6 -0.15 7 AV2 +0.02 5 AV3 +0.04 5 A 110 686 AV3 -0.01 6 AV2 -0.11 3 A 111 63 A201 AV2 -0.11 4 AV1 +0.22 3 AV2 +0.02 4 AV3 +0.07 7 AV4 +0.07 3 AV5 +0.11 4 AV6 +0.04 2 AV1 +0.16 4 AV1 +0.02 3 AV2 +0.01 4 AV2 +0.03 3 AV3 +0.06 8 AV4 +0.13 5 AV5 +0.07 6 AV6 +0.12 3 AV3 +0.09 4 AV4 +0.07 5 AV3 +0.08 6 AV4 +0.05 7 AV3 +0.07 9 B 91 65 AV4 +0.11 4 Page 4 of 8

Attachment 1 to ULNRC-05450

[Steam S mRow Column Location Size (%TW)

Generator AV2 -0.02 3 AV2 -0.08 4 C 91 65 AV3 +0.16 8 AV3 +0.15 5 AV4 +0.09 4 AV3 -0.04 6 AV3 -0.02 6 AV4 +0.04 5 AV3 +0.00 5 AV5 +0.00 4 AV5 +0.00 7 AV3 +0.01 6 AV4 +0.02 7 AV5 +0.00 4 AV3 +0.00 4 AV2 +0.00 6 AV2 +0.02 7 AV3 -0.02 4 AV5 -0.08 5 AV3 +0.00 7 AV3 +0.09 8 AV3 +0.00 7 AV2 +0.02 5 C 84 76 AV2 -0.03 4 AV2 +0.01 3 AV3 -0.08 5 AV3 +0.04 5 AV5 +0.02 8 AV4 +0.00 10 AV3 +0.00 10 AV2 +0.02 10 AV6 -0.02 5 C 89 61 AV6 -0.03 7 AV2 +0.03 8 AV2 -0.03 5 AV3 +0.01 9 AV4 -0.02 6 AV4 +0.04 6 Page 5 of 8

Attachment 1 to ULNRC-05450 Steam Row Column Location Generator Size (% TW) 89 61 AV5 +0.03 4 C

AV5 -0.02 6 AV5 +0.00 6 AV3 +0.00 7 AV4 +0.00 4 C 89 71 AV4 +0.00 4 AV3 -0.02 9 AV5 -0.04 8 AV5 +0.13 4 C 90 72 AV5+0.14 5 AV5 +0.00 5 C 91 71 AV5 -0.02 5 AV5 +0.08 2 AV3 +0.00 7 AV2 -0.02 6 AV1 +0.09 4 AV1 +0.18 6 AV2 +0.02 7 AV3 +0.02 9 AV3 +0.00 5 AV4 +0.00 3 C 93 71 AV4 +0.01 5 AV3 -0.01 7 AV5 -0.02 4 AV6 +0.00 4 AV3 +0.00 4 AV4 +0.02 3 AV6 +0.00 5 AV3 +0.00 3 AV4 +0.02 6 AV5 -0.12 5 AV3 +0.00 11 AV4 +0.00 5 AV2 +0.02 5 C 96 58 AV4 +0.18 6 AV4 -0.07 3 AV2 -0.02 6 AV3 +0.02 9 Page 6 of 8

Attachment 1 to ULNRC-05450

[Steam Generator Row Column Location Size (%TW)

C 96 58 AV3 -0.02 4 AV2 +0.00 5 C 96 74 AV2 +0.03 4 AV2 -0.04 1 AV3 +0.00 7 AV4 +0.00 4 C 97 71 AV4 +0.00 4 AV3 -0.07 9 AV4 +0.00 5 AV3 +0.00 6 AV2 +0.00 7 C 100 74 AV2 -0.02 8 AV3 +0.08 6 AV3 -0.03 2 AV4 -0.02 5 AV4 +0.00 14 AV3 +0.00 7 AV2 +0.15 4 AV5 -0.07 4 AV5 -0.07 6 AV2 +0.13 6 AV3 +0.05 7 AV3 -0.04 3 AV4 +0.02 13 AV4 +0.06 2 AV3 +0.00 5 AV3 +0.01 6 AV4 +0.00 5 AV4 +0.03 6 AV3 +0.00 8 AV3 -0.00 7 AV4 -0.02 6 AV4 +0.05 5 AV5 +0.12 4 AV5 +0.17 3 AV6 -0.17 4 AV6 -0.12 5 D 88 56 AV3 -0.02 5 Page 7 of 8

S.

I Attachment 1 to ULNRC-05450 Steam

[eeat Row Column Location Size (%TW)

Generator AV3 +0.00 8 88 56 AV3 +0.10 6 D

AV4 -0.02 4 AV4 +0.1O 4 0 88 72 AV5 -0.17 3 AV5 -0.10 4

Callaway did not perform repairs to any tubes in Refuel Outage 15. No tubes exceeded the repair criteria. The total number of tubes repaired to date is one. This is 4.5 x 10-7%

plugged. This tube was plugged during manufacturing of the steam generators.

Results of Condition Monitorine The Condition Monitoring report concluded that the Callaway steam generator tubes satisfied the structural integrity performance criterion, accident induced leakage criterion and operational leakage performance criterion. These criteria are specified in Technical Specification AC 5.5.9 and SR 3.4.13. Callaway did not perform any tube pulls or in-situ testing.

Key AV 1,2,3,4,5,6 - Anti-Vibration Bars TWD - Through Wall Degradation Page 8 of 8