ML070570453
| ML070570453 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 02/22/2007 |
| From: | Ridgel J Entergy Nuclear South, Entergy Operations |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| W3F1-2007-0010 | |
| Download: ML070570453 (6) | |
Text
Etergy Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6485 jridgel@entergy.com Jerry A. Ridgel Acting Nuclear Safety Assurance Director Waterford 3 Contains 10 CFR 2.390(a)(4) Proprietary Information W3F11-2007-0010 February 22, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Steam Generator Batwing Inspection Proprietary Documentation Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
On January 15, 2007, Entergy received an NRC Staff request for copies of Westinghouse documentation required to support inspection activities associated with the Waterford 3 Steam Generator (SG) Batwing issue. is the list of NRC Staff requested documents. Attachment 2, Proprietary Copies of ~
Westinghouse Documents Associated with the SG Batwing Issue, contains information proprietary to Westinghouse Electric Company LLC. Therefore, it is requested that Attachment 2 be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. is a nonproprietary copy of Attachment 2 for the public document room. is the supporting Westinghouse affidavit for withholding the proprietary information in Attachment 2. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit CAW-07-2246 should be addressed to B.F. Maurer, Acting Manager of Regulatory Compliance and Plant Licensing, Westinghouse Electric Company, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
AOD
W3Fl-2007-O01 0 Page 2 If you have any questions or require additional information, please contact Ron Williams at (504) 739-6255.
Sincerely, Attachments:
- 1. List of NRC Staff Requested Documents
- 2. Proprietary Copies of Westinghouse Documents Associated with the SG Batwing Issue
- 3. Non-Proprietary Copies of Westinghouse Documents Associated with the SG Batwing Issue
- 4. Westinghouse Affidavit Regarding Proprietary Information
W3171 -2007-0010 Page 3 cc:
(w/o Attachments 2 & 3)
U.S. Nuclear Regulatory Commission Attn: Mr. Mel B. Fields MS O-7E1 Washington, DC 20555-0001 Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washingoton, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P.O0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers 95 Glastonbury Blvd - Suite 300 Glastonbury, CT 06033-4443 To W3FI-2007-OOI 0 List of NRC Staff Requested Documents W3FI -2007-0010 Page 1 of 2 List of NRC Staff Requested Documents
- 1. 00000-DC-STD-702, Revision 00, Combustion Engineering, Inc. Design Criteria for Support Bar Stabilizer for Standard Plants (Non-Proprietary) Note, the support bar stabilizers in this specification were mistakenly interpreted to be tube supports or spacers referred to as bat wings, which resulted in the incorrect safety/seismic classification depicted in Waterford 3 evaluation document ER-W3-2006-0339. Also, ER-W3-2006-0362-000 "Enhance the Steam Generator Batwing Support / Wrap Around Bar Welds" contains an erroneous statement in ER Section 1.3 that reads: "The existing weld designs per CE 74270-271-13 are still applicable to all other welds that are not in the presence of the stay cylinder region per PDD-581 7-13616. " Batwing welds verified by inspection in areas both inside and outside the stay cylinder area were found deficient (weld one side rather than two) for Steam Generator 2. Discrepancies were entered into the corrective action program as Condition Report CR-WF3-2007-300 included in Attachment 3.
- 2. 09270-PE-120 Revision 07, Combustion Engineering, Inc. Project Specification for Steam Generator Assemblies for Water-ford Unit No. 3 (Proprietary)
- 3. CN-SGDA-05-36 Rev.1, Westinghouse Evaluation of Degraded batwing Tube Supports in the Water-ford 3 Steam Generators at 3716 MWt Power Uprate Conditions (Contained as an attachment to Corrective Action CR-WF3-2006-04395) (Proprietary)
- 4. LTR-SGDA-06-89 "Loose Parts Evaluation of Water-ford Unit 3" (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 5. LTR-SGDA-05-100, Westinghouse Recommendations to Address Detached Batwings in the Waterford 3 Steam Generators dated May 6, 2005 (Contained within Corrective Action CR-WF3-2005-01 977 GA#6) (Non-Proprietary)
- 6. LTR-SGDA-05-05-107, Westinghouse Review of Water-ford Ill Steam Generator Manufacturing Records dated May 12, 2005 (Contained within Corrective Action CR-WF3-2005-01977 CA#14) (Proprietary)
- 7. LTR-SGDA-06-181, Rev.1, "Effect of Multiple Batwing Failure on Thermal Hydraulics at Water-ford 3 Steam Generators with 20% SGTP" dated October 20, 2006 " (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 8. LTR-SGDA-06-1 99 Rev 1, "Evaluation of the Effect of Failed Batwings at Waterford-3 Operating at 3716 MWt Uprated Conditions with up to 20% Steam Generator Tube Plugging" dated December 15, 2006 (Contained as an attachment to ER-W3-2006-0339)
(Proprietary)
- 9. LTR-SGDA-06-221, Effect of Multiple Batwing Failure on Thermal Hydraulics at Water-ford 3 Steam Generator with 3716 MWt Power Uprate and 20% SGTP dated December 8, 2006 (Contained as an attachment to Corrective Action CR-WF3-2006-03966 CA#12 and attachment to ER-W3-2006-0339) (Proprietary)
- 10. LTR-SGDA-06-225 "Evaluation of Steam Line Break Accident Condition Affecting Degraded Batwings at Waterford 3" dated December 15, 2006 (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 11. LTR-SGDA-06-228, Rev. 0, " Waterford 3 Batwing Upper Weld Evaluations in Support of the RF14 Outage". Dated December 12, 2006 (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 12. LTR-SDGA-06-228 Rev.1, Water-ford 3 Batwing Upper Weld Evaluation in Support of the RF14 Outage dated December 16, 2006 (Contained as an attachment to ER-W3-2006-0362) (Proprietary)
W3F1 -2007-0010 Page 2 of 2
- 13. LTR-SGDA-06-229 "Water-ford 3 Steam Generator Stability Ratios, and Turbulent Amplitudes for Tube Rows in the Central Cavity without Batwing Support" dated December 14, 2006 (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 14. LTR-SDGA-06-236, Rev. 2, Evaluation of Upper Weld Clip and Attachment Welds to Batwing for Waterford 3 Steam Generator dated December 15, 2006 (Contained as an attachment to ER-W3-2006-0362 and attachment to ER-W3-2006-0339) (Proprietary)
.15. LTR-SGDA-06-238 "Tube-Batwing Contact Force Attenuation Results For Degraded Batwings at Water-ford 3" dated December 15, 2006 (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 16. LTR-SDGA-06-240, Evaluation of Potential Secondary Side Loose Parts from Batwing Welding and the Effects of Increased Tube Temperatures in Water-ford 3 Steam Generators dated December 17, 2006 (Contained as an attachment to ER-W3-2006-0362) (Proprietary)
- 17. LTR-SGDA-06-243, Rev. 1, "Input to the Preliminary OA to Address Detached Batwings in the Water-ford 3 Steam Generators" dated December 17, 2006 (Contained as an attachment to ER-W3-2006-0339) (Proprietary)
- 18. LTR-SGDA-06-248 'Water-ford 3 Sentinel 'Ribbed" Mechanical Plugs-Description and Leak rate" dated December 20, 2006 (Contained as an attachment to ER-W3-2006-0339)
(Proprietary)
- 19. SS-1 13, Excerpts from Combustion Engineering, Inc. Detailed Structural Analysis for Tubes and Tube Supports A486-A594 (Proprietary)
- 20. CWTR3-06-94 "Batwing Loose Part Impact on Tube Rupture" December 19, 2006 (Contained as an attachment to ER-W3-2006-0339) (Non-Proprietary)