BVY 11-033, License Renewal Safety Evaluation Report Supplement Comments
| ML11154A086 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/19/2011 |
| From: | Michael Colomb Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 11-033 | |
| Download: ML11154A086 (5) | |
Text
- "Entergy Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 11-033 May 19, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
REFERENCES:
License Renewal Safety Evaluation Report Supplement Comments Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
- 1.
Letter, Entergy to USNRC, "License Renewal Application," BVY 06-009, dated January 25, 2006
- 2.
Letter, USNRC to Entergy, "Audit Report Regarding The Vermont Yankee Nuclear Power Station License Renewal Application (TAC No. MC9668)," NVY 10-054, dated September 3, 2010
- 3.
Letter, USNRC to Entergy, "Supplemental Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station (TAC No. MC9668)," NVY 11-032, dated March 21, 2011
Dear Sir or Madam:
On January 25, 2006, Entergy Nuclear Operations, Inc. and Entergy Nuclear Vermont Yankee, LLC (Entergy) submitted the License Renewal Application (LRA) for the Vermont Yankee Nuclear Power Station (VYNPS) via Reference 1. After completion of an LRA audit as documented in Reference 2, teleconference meetings with VYNPS to discuss technical issues and LRA supplement letters submitted by VYNPS, the NRC staff developed and transmitted the "Supplemental Safety Evaluation Report Related to the License Renewal of Vermont Yankee Nuclear Power Station," hereinafter referred to as the Safety Evaluation Report (SER)
Supplement, as documented in Reference 3. Entergy has completed a review of the SER Supplement to verify accuracy. Reviewer comments are provided as Attachment 1 to this letter.
This letter contains no new commitments. Should you have any questions or require additional information concerning this submittal, please contact Mr. Robert Wanczyk at 802-451-3166.
Sincerely,
[MJC/PLC]
A4 n-7
BVY 11-033 / Page 2 of 2 Attachments: 1. License Renewal SER Supplement Review Comments cc:
Mr. William M. Dean, Regional Administrator U.S. Nuclear Regulatory Commission, Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Robert Kuntz, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11 F1 11555 Rockville Pike Rockville, MD 20852-2738 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
BVY 11-033 Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
License Renewal SER Supplement Review Comments
VERMONT YANKEE NUCLEAR POWER STATION SER SUPPLEMENT 2 REVIEW COMMENTS ATTACHMENT 1 Note: The section number(s) and page number(s) cited in the following listing correspond to the section number(s) and page number(s) as identified in the Safety Evaluation Report Supplement 2.
Comment Section Page Comment Number Number(s)
Number(s) 1 Abstract iii Safety Evaluation Report (SER) Supplement 1 was published in September 2009 2
3.0.3.1.3 3-3 License Renewal Application (LRA) Section A.2.1.19 was also amended by letter dated February 4, 2011 (BVY 11-010) 3 3.0.3.1.6 3-5,6 January 21, 2011 letter (BVY 11-001) referenced in these sections is not listed in 3.0.3.1.7 Appendix B Chronology 4
3.0.3.1.13 3-9 The lower torus shell was top coated in a band approximately one foot above and below the water line following blasting and recoating in 1998 RFO (Ref: BVY 11-010).
5 3.0.3.1.13 For the Protective Coating Program, Vermont Yankee Nuclear Power Station (VYNPS) provided new LRA Sections B.1.32 and A.2.1.38. The B.1.32 and A.2.1.38 designations were also used in letter dated 10/17/2006 for the Metal Enclosed Bus Program.
6 3.0.3.2.1 3-11 The third bullet on page 3-11 identifies soil sample parameters as soil composition, pH, chlorides, sulfates, redox potential, and resistivity. Consistent with the commitment to determine soil corrosivity in accordance with AWWA C105, VYNPS will determine soil corrosivity index based on soil resistivity, pH, redox potential, sulfides and moisture as indicated in letter dated February 10, 2011 (BVY 11-013).
7 3.0.3.2.1 3-11 VYNPS did not specify that the number of inspections of fuel oil system piping would increase to six, only that the total percentage inspected would increase to 12%. (Ref:
BVY 11-013, Commitment 54) 8 3.0.3.2.1 3-12 Per the buried pipe inspection summary tables in letter dated February 10, 2011 (BVY 11-013), the number of inspections conducted in the ten-year period prior to the period of extended operations is seven, not nine.
9 3.0.3.2.9 3-14 Reference to D2276 units should be mg/liter, not mg/ml.
Page 1 of 2 BVY 11-033 Docket 50-271
VERMONT YANKEE NUCLEAR POWER STATION SER SUPPLEMENT 2 REVIEW COMMENTS ATTACHMENT 1 Comment Section Page Comment Number Number(s)
Number(s) 10 3.0.3.2.9 3-14 In paragraph 5, D2709 is used for determination of water and sediment, not "water standards."
11 3.0.3.2.9 3-15 Paragraph 5 should follow paragraph 1. Paragraph 2 should follow paragraph 4.
12 3.0.3.2.9 3-15 AMP XI.M30 in GALL Rev 1 does not reference ASTM D975-04. GALL Rev 2 does.
Section 3.0.3 of the supplement states that all references to the GALL Report refer to Rev 1.
13 3.0.3.2.9 3-15 Statement "revised UFSAR supplement" in last sentence of last paragraph could be misleading. There is no record that A.2.1.9 was revised from original LRA description.
14 3.0.3.3.9 For the Neutron Absorber Monitoring Program, VYNPS provided new LRA Sections B.1.31 and A.2.1.37. The B.1.31 and A.2.1.37 designations were also used in letter dated 10/17/2006 for the Bolting Integrity Program.
15 3.0.3.3.9 3-17 VYNPS has nine NES racks installed in the spent fuel pool, not seven. This number (nine) was reported in BVY 11-010 and BVY 11-013.
16 3.3.2.2.6 3-19 February 15, 2011 letter (BVY 11-015) referenced in this section is not listed in Appendix B Chronology.
17 Appendix A A-10 LRA Commitment No. 51 LRA Section was correctly listed as 'N/A' in original SER. LRA Section B.1.31 does not apply to this commitment.
18 Appendix A LRA Commitment No. 55 is not listed in the Appendix. It is referenced and discussed in Section 3.0.3.1.13.
Page 2 of 2 BVY 11-033 Docket 50-271