NL-09-156, Response to Request for Additional Information Regarding Relief Request No. 3
| ML093340048 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/19/2009 |
| From: | Robert Walpole Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-09-156, TAC ME1577 | |
| Download: ML093340048 (4) | |
Text
v=kP%'EnteW 0 Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Robert Walpole Licensing Manager Tel 914 734 6710 November 19, 2009 NL-09-156 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Regarding Relief Request RR-03 (TAC No. ME1577)
Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64
REFERENCE:
- 1. Entergy Letter NL-09-087 Regarding Relief Request IP3-1SI-RR-01, IP3-1SI-RR-02, and IP3-ISI-RR-03 For Fourth Ten-Year Inservice Inspection Interval, dated June 24, 2009
- 2.
Indian Point Nuclear Generating Unit No.3 -Request for Additional Information Regarding Relief Request RR-03 (TAC NO. ME1577),
dated November 12, 2009
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy) submitted Relief Request No. 03 (RR-03) for Indian Point Unit No. 3 (IP3) in Reference 1. The NRC requested additional information in Reference 2. The response to that request is in Attachment 1.
There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Robert Walpole, Licensing Manager.
Very truly yours, RW/sp cc on next page Akot-r
NL-09-156 Docket 50-286
'Page 2 of 2
Attachment:
- 1. Response to Request for Additional Information Regarding Relief Request 03 cc:
Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service Mr. Francis J. Murray, Jr., President and CEO, NYSERDA to NL-09-156 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 03 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NL-09-156 Docket 50-286 Page 1 of 1 Response to Request for Additional Information Regqarding Relief Request 03 On June 24, 2009, Entergy Nuclear Operations, Inc. (Entergy) submitted, Accession No. ML091820325, Relief Request (RR)-03 for Indian Point Nuclear Generating Unit No.3 (IP3) to use the alternative qualification requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Code Case N-739-1, in lieu of the requirements in the ASME Code, Section IWA-2300. On November 12, 2009 the Nuclear Regulatory Commission staff sent a letter with a request for additional information. The NRC question and the Entergy response are as follows:
Question 1 Based on the IP3 Updated Final Safety Analysis Report Section 5.1.2.1, the reactor containment structure is a reinforced concrete vertical right cylinder with a flat base and hemispherical dome. No post-tensioning steel tendons are used in its design. RR-03, Section 1, states that the following ASME Code components are affected by the proposed alternative:
L1.11 L1.12 L2.30 However, Item L2.30 is included in the ASME Code,Section XI, 2001 Edition with 2003 Addenda, Division I, Table IWL-2500-1 as Examination Category L-B for the "Unbonded Post-Tensioning System." Specifically, Item L2.30 refers to anchorage hardware and surrounding concrete. Please clarify why Item L2.30 is included as an affected component under the ASME Code in the IP3 relief request, considering that IP3 does not have a post-tensioning system.
Response
The NRC is correct in noting the IP3 reactor containment structure is a reinforced concrete vertical right cylinder with a flat base and hemispherical dome. No post-tensioning steel tendons are used in its design. The relief was requested from 10 CFR 50.55a(b)(2)(viii)(F),
personnel that examine containment concrete surfaces and tendon hardware, wires, or strands must meet the qualification provisions in IWA-2300 since the "owner-defined" personnel qualification provisions in IWL-231 0(d) are not approved for use. The relief requested the use of Code Case N-739-1, which would provide an acceptable level of quality and safety. Item number L2.30 is not an affected component of this relief request so relief is not required for Item number L2.30.