RC-05-0076, Operating License, Special Report (Spr 2005-001)

Operating License, Special Report (Spr 2005-001)

ML051440438
Person / Time
Site:	Summer
Issue date:	05/19/2005
From:	Archie J South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-05-0076, SPR 2005-001
Download: ML051440438 (3)

Text

Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY May 19, 2005 RC-05-0076 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 SPECIAL REPORT (SPR 2005-001)

South Carolina Electric & Gas Company (SCE&G) is submitting this report pursuant to the requirements of Technical Specification Surveillance Requirement 4.4.5.5.a. & b. This inspection constitutes the "Thirteenth In-service Inspection" of Steam Generator tubes.

Section 4.4.5.5.a requires that the number of tubes plugged or repaired in each generator be reported in a Special Report within 15 days following the completion of each in-service inspection of steam generator tubes. The inspection activity during Refueling Outage 15 at the Virgil C. Summer Nuclear Station was completed on May 8, 2005.

Summarized in the table below is the number of plugs installed in each generator as a result of the inspections performed during this outage.

I Generator A B C No. Plugged in RF-15 0 0 0 Previously Plugged 3 1 4 Total Tubes Plugged 3 1 4 No tube plugging was required in this outage.

Section 4.4.5.5.b requires that within 12 months following the completion of the in-service inspection of the generators, the complete results will be submitted to the Commission as a Special Report. This information is being provided below:

1. Number and extent of the tubes inspected.

Steam Generator "A" 6,304 tubes (100%) Bobbin Exam Full Length 1,262 tubes (20%) Hot Leg TTS +3" to -3" 30 tubes Low Row U-bend Region 58 areas of "Special Interest" (i.e. Potential Loose Parts, Dents, Dings, Bobbin Indications of Interest)

NUCLEAR EXCELLENCE - A SUMMER TRADITION! Jr -uo I SCE&G I Virgil C.Summer Nudear Station . P.O. Box 88 . Jenkinsville, South Carolina 29065 eT (803) 345.5209 .www.scona.com

Document Control Desk L-99-01 93 RC-05-0076 Page 2 of 3 Steam Generator "B" 6,306 tubes (100%) Bobbin Exam Full Length 1,262 tubes (20%) Hot Leg TTS +3"to -3" 39 areas of "Special Interest" (i.e. Potential Loose Parts, Dents, Dings, Bobbin Indications of Interest)

Steam Generator "C"

• 6,303 tubes (100%) Bobbin Exam Full Length

• 1,262 tubes (20%) Hot Leg TTS +3' to -3" 65 areas of "Special Interest* (i.e. Potential Loose Parts, Dents, Dings, Bobbin Indications of Interest)

2. Location and percent of wall-thickness penetration for each indication of an Imperfection.

Steam Generator "A" Two tubes were found to have wear-like indications at the anti-vibration bars.

Tube R19-C140 was found to have a wear-like indication with an estimated depth of 7% at AV7.

• Tube R26-C139 was found to have a wear-like indication with an estimated depth of 4% at AV2 and 5%at AV7.

All three of the wear-like indications were found to be apparent in the review of the 1994 pre-service inspection and all three were very similar to the results found in the RF-1 2 inspection. This would indicate that they were present during pre-service.

Two tubes were found to have wear-like indications at the TSPs.

Tube R2-C77 was found to have indications at the upper and lower edges of the 08H TSP with estimated depths of 8 and 21% TW, respectively.

• Tube R4-C1 03 was found to have Indications at the upper and lower edges of the 05C TSP with estimated depths of 10 and 8%TW, respectively.

All indications were found to be apparent in the review of the 2000 bobbin coil inspection and all were very similar in signal characteristics to the RF-12 inspection data. This would indicate very small growth rate over 2 complete cycles of operation.

Steam Generator "B" No degradation detected.

Steam Generator "C" One tube was found to have a wear like indication at an anti-vibration bar.

Document Control Desk L-99-0193 RC-05-0076 Page 3 of 3

• Tube R26-C3 was found to have a wear like indication with an estimated depth of 4% at AV2.

This wear-like indication was found to be apparent in the review of the 1994 pre-service inspection and was also very similar in the data from the RF-12 inspection, This would indicate that it was present during pre-service.

Three tubes were found to have wear-like indications at the TSPs.

Tube Rl-C8 was found to have an indication at the upper edge of the 07C TSP with an estimated depth of 5%TW.

Tube Rl-C82 was found to have an indication at the upper edge of the 08H TSP with an estimated depth of 6%TW.

Tube Rl-C94 was found to have an indication at the upper edge of the 06H TSP with an estimated depth of 11% TW.

All but one (R1-C82) of the indications was found to be apparent in the review of the 2000 bobbin coil inspection and all were very similar in signal characteristics to the RF-12 inspection data. This would indicate very small growth rate over 2 complete cycles of operation.

3. Identification of tubes plugged.

No tubes required plugging.

Should you have any questions regarding these inspection results, please call Mr. Charles McKinney at (803) 345-4723.

e yours, y B.Archie CJM/JBAlcm C: N. 0. Lorick NRC Resident Inspector S. A. Byme Winston & Strawn N. S. Cams NSRC T. G. Eppink INPO Records Center R.J. White CER (L-99-0193)

W. D. Travers File (818.08)

R. E. Martin DMS (RC-05-0076)