ML050110224
| ML050110224 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Vogtle  |
| Issue date: | 01/07/2005 |
| From: | Stinson L Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-04-001, NL-04-2536 | |
| Download: ML050110224 (6) | |
Text
L M. Stinson (Mike)
Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SO)U T HER[N AM January 7, 2005 COMPA Energy to Serve Toul r Worldw Docket Nos.:
50-321 50-424 NL-04-2536 50-366 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections" Ladies and Gentlemen:
By letter dated October 25, 2004, Southern Nuclear Operating Company (SNC) submitted a response pursuant to the requirements of Nuclear Regulatory Commission (NRC)
Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections." This response provided information on the steam generator tube inspections at Joseph M.
Farley Nuclear Plant (FNP) Units I and 2 and at Vogtle Electric Generating Plant (VEGP) Units I and 2, including a description of the steam generator tube inspections performed during the last inspection at each plant (which took place at FNP Unit 2 and at VEGP Unit 2.)
In a verbal request made December 10, 2004, NRC clarified that the intent of GL-2004-01 was to seek a description of the last steam generator tube inspection performed at each unit at each plant. Accordingly, enclosed is a description of the last inspection performed at the other unit at each plant (FNP Unit I and VEGP Unit 1). This supplemental information does not affect the information, assessment, or associated discussion provided with the previous October 25, 2004 submittal, but in conjunction with that submittal forms a more complete response to GL-2004-0 1.
(Affirmation and signature provided on the following page.)
U. S. Nuclear Regulatory Commission NL-04-2536 Page 2 Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
This letter contains no NRC commitments. If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Swvorn to and subscribed before me this I day ofs n up Ay.
2005.
~Of;.
am a a L
Notary Public my cciiZssion expires: 4 '22 5d9 '7
?-SAary Public LMS/DWD/daj
Enclosures:
- 1. Farley Nuclear Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections"
- 2. Vogtle Electric Generating Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections" cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. E. Grissette, Vice President - Plant Vogtle Mr. J. R. Johnson, General Manager - Plant Farley Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CFA04.054; CVC7000; LC# 14197 U. S. Nuclear Regulatory Commission Dr. \\V. D. Travers, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. Gratton, NRR Project Manager - Vogtle Mr. C. A. Patterson, Senior Resident Inspector - Farley Mr. G. J. McCoy, Senior Resident Inspector - Vogtle Joseph M. Farley Nuclear Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections"
Joseph M. Farley Nuclear Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections" Southern Nuclear transmitted the response to Generic Letter (GL) 2004-01 to NRC for Farley Nuclear Plant (FNP) Units 1 and 2 in a letter dated October 25, 2004 (NL 2012). This letter provided information regarding the last steam generator (SG) tube inspection performed at the plant (at FNP Unit 2 during October 2002), as part of the information, assessment, and associated discussion as specified by GL 2004-01, Item 1.
The following supplemental information provides a description of the last SG tube inspection performed at the other unit (at FNP Unit 1, during October 2001), which was not addressed in the October 25, 2004 response. This supplemental information does not affect the information, assessment, and associated discussion previously provided in letter NL-04-2012.
Description of SG Tube Inspections Performed During the Last FNP Unit I Inspection:
In the last SG tubing eddy current inspection for FNP Unit 1, October 2001, the following tube inspection scope was performed in SGs A, B, and C, as the first ISI eddy current inspection after SG replacement:
100% full length inspection with the bobbin probe (except Row I and Row 2 U-bends),
- 20% hot leg (HL) expansion transition, by inspecting +/- 3 inches from the top of the tubesheet (ITS) with the +Point magnetic rotating pancake coil (MRPC) probe, 100% small radius (Row 1 and Row 2) U-bends with +Point probe, 100% of HL straight section dings and dents > 5 volts (as measured with the bobbin probe) with the +Point probe, Special interest +Point probe examination of all "I-codes" bobbin indications that were not cleared based on the pre-service inspection results.
Page I of I Vogtle Electric Generating Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections"
Vogtle Electric Generating Plant Supplemental Response to NRC Generic Letter 2004-01, "Requirements for Steam Generator Tube Inspections" Southern Nuclear transmitted the response to Generic Letter (GL) 2004-01 to NRC for Vogtle Electric Generating Plant (VEGP) Units 1 and 2 in a letter dated October 25, 2004 (NL-04-2012). This letter provided information regarding the last steam generator (SG) tube inspection performed at the plant (at VEGP Unit 2 during April 2004), as part of the information, assessment, and associated discussion as specified by GL 2004-01, Item 1.
The following supplemental information provides a description of the last SG tube inspection performed at the other unit (at VEGP Unit 1, during September 2003), which was not addressed in the October 25, 2004 response. This supplemental information does not affect the information, assessment, and associated discussion previously provided in letter NL-04-2012.
Description of SG Tube Inspections Performed During the Last VEGP Unit 1 Inspection:
In the last refueling outage, for VEGP Unit 1, September 2003, the following tube inspection scope was performed in SGs 2 and 3:
100% full length inspection with the bobbin probe (except Row 1 and Row 2 U-bends),
50% hot leg (HL) expansion transition, by inspecting +/- 3 inches from the top of the tubesheet (TIS) with the +Point magnetic rotating pancake coil (MRPC) probe,
- 50% small radius (Row 1 and Row 2) U-bends with the +Point probe, 100% of HL straight length dings and dents > 5 volts (as measured with the bobbin probe) with the +Point probe, Special interest +Point examination of all "I-codes" indications that were new or not resolved after history review.
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