ML062700642
| ML062700642 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/11/2006 |
| From: | Fields M NRC/NRR/ADRO/DORL/LPLIV |
| To: | Venable J Entergy Operations |
| Fields M, NRR/DORL/LP4, 415-3062 | |
| References | |
| TAC MD2111 | |
| Download: ML062700642 (4) | |
Text
October 11, 2006 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD2111)
Dear Mr. Venable:
By letters dated May 24, 2005, and May 17, 2006, Entergy Operations, Inc. (the licensee),
submitted the results of the steam generator tube inspections for the spring 2005 refueling outage at the Waterford Steam Electric Station, Unit 3.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is enclosed. As discussed with Dana Millar of your staff, the NRC staff is requesting a response within 60 days of this letter.
If you have any questions, please contact me at 301-415-3062.
Sincerely,
/RA/
Mel B. Fields, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: See next page
ML062700642 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NAME MFields LFeizollahi DTerao DATE 10/11/06 10/11/06 10/11/06
REQUEST FOR ADDITIONAL INFORMATION WATERFORD STEAM ELECTRIC STATION, UNIT 3 STEAM GENERATOR TUBE INSPECTIONS DOCKET NO. 50-382 By letters dated May 24, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML051460385), and May 17, 2006 (ADAMS Accession No. ML061390029), Entergy Operations, Inc., submitted the results of the steam generator tube inspections for the spring 2005 refueling outage at the Waterford Steam Electric Station, Unit 3.
The Nuclear Regulatory Commission staff has reviewed the information provided and determined that the following additional information is required in order to complete the evaluation:
1.
On page 3 of the May 24, 2005, report and page 3 of the May 17, 2006, report, you indicated that possible loose parts indications were identified during the inspection.
Please discuss the scope and results of the foreign object search and retrieval on each steam generator (SG). If any loose parts were identified, discuss whether the loose parts were removed. If the parts were not removed or the locations were not visually inspected, please discuss the results of any evaluations performed to ensure these parts (or suspected parts) would not result in a loss of tube integrity for the period of time between inspections.
2.
On page 2 of the May 24, 2005, report, Table 2.1 states that you expanded the inspection of wear scars for SG 31, but not for SG 32. Then, on page 2 of the May 17, 2006, report, Table 3.1 states that you did not expand the inspection of wear scars for SG 31, but you did for SG 32. Please clarify this discrepancy.
3.
On page 2 of the May 17, 2006, report, you indicated in Table 3.1 that you identified 188 new wear scars in SG 31 and 214 new wear scars in SG 32. Please discuss the cause for the apparent increase in the number of new wear scars.
4.
On page 3 of the May 24, 2005, letter, you indicated in Table 2.2 that four volumetric indications were detected in the cold leg of SG 31 and one volumetric indication was detected in the hot leg of SG 32. Please discuss the nature, cause, and severity of these indications.
5.
On page 4 and page 7 of the May 24, 2005, report, you indicated in Tables 3.1.1 and 3.3.1 that there has been a reduction in the number of detected indications of circumferential and axial cracking at the top of the tubesheet when compared to past outages. Please discuss any insights you have concerning the trend. In addition, please discuss the reduction in the number of free-span indications. Include in your response a discussion on the noise levels associated with the SG eddy current data.
May 2006 Waterford Steam Electric Station, Unit 3 cc:
Vice President Operations Support Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Director Nuclear Safety Assurance Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Wise, Carter, Child & Caraway P.O. Box 651 Jackson, MS 39205 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn LLP 1700 K Street, N.W.
Washington, DC 20006 Resident Inspector/Waterford NPS P.O. Box 822 Killona, LA 70066-0751 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Parish President Council St. Charles Parish P.O. Box 302 Hahnville, LA 70057 Executive Vice President
& Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Chairman Louisiana Public Services Commission P.O. Box 91154 Baton Rouge, LA 70825-1697 Richard Penrod, Senior Environmental Scientist State Liaison Officer Office of Environmental Services Northwestern State University Russell Hall, Room 201 Natchitoches, LA 71497