ML032471386
| ML032471386 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (NPF-049) |
| Issue date: | 09/26/2003 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Christian D Dominion Nuclear Connecticut |
| Nerses V, NRR/DLPM, 415-1484 | |
| References | |
| TAC MB9897 | |
| Download: ML032471386 (6) | |
Text
September 26, 2003 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING EXEMPTION TO USE A LOW TIN CLADDING (TAC NO. MB9897)
Dear Mr. Christian:
By letter dated July 1, 2003, Dominion Nuclear Connecticut, Inc., requested an exemption from the requirements of Title 10 of the Code of Federal Regulations Parts 50.44, 50.46, and Appendix K. The purpose of this exemption would allow the use of up to eight lead test assemblies fabricated with a low tin version of ZIRLOTM, called Optimized ZIRLOTM.
In order to continue our review of your request, additional information, as delineated in the Enclosure, is required.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing and Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Request for Additional Information cc w/encl: See next page
Millstone Power Station, Unit No. 3 cc:
Lillilan M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Mr. P. J. Parulis Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. W. R. Matthews Senior Vice President - Nuclear Operations Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Mr. G. D. Hicks Director - Nuclear Station Safety and Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company Moody Street P.O. Box 426 Ludlow, MA 01056 Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. Chris Funderburk Director, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.
5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. David W. Dodson Licensing Supervisor Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
Millstone Power Station, Unit No. 3 cc:
Mr. S. E. Scace Assistant to the Site Vice President Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. A. J. Jordan, Jr.
Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
September 26, 2003 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING EXEMPTION TO USE A LOW TIN CLADDING (TAC NO. MB9897)
Dear Mr. Christian:
By letter dated July 1, 2003, Dominion Nuclear Connecticut, Inc., requested an exemption from the requirements of Title 10 of the Code of Federal Regulations Parts 50.44, 50.46, and Appendix K. The purpose of this exemption would allow the use of up to eight lead test assemblies fabricated with a low tin version of ZIRLOTM, called Optimized ZIRLOTM.
In order to continue our review of your request, additional information, as delineated in the Enclosure, is required.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing and Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-2 R/F JClifford VNerses CRaynor ACRS BMcDermott, RI OGC PClifford FAkstulewicz ADAMS Accession Number: ML032471386 OFFICE PDI-2/PM PDI-2/LA SRXB/SC PDI-2/SC NAME VNerses CRaynor FAkstulewicz JBoska for JClifford DATE 09/09/03 09/08/03 09/09/03 09/25/03 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION EXEMPTION TO 10 CFR PARTS 50.44, 50.46, AND APPENDIX K MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 By letter dated July 1, 2003, Dominion Nuclear Connecticut (DNC), Inc., requested an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Parts 50.44, 50.46, and Appendix K. The purpose of this exemption would allow the use of up to eight lead test assemblies fabricated with a low tin version of ZIRLOTM, called Optimized ZIRLOTM. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed changes to the Technical Specification (TS).
In order for the staff to complete its evaluation, the following additional information is requested:
- 1. Attachment 1, Page 1, of the DNC letter dated July 1, 2003, states, Westinghouse has submitted Addendum 1 to WCAP-12610-P-A/CENPD-404-P-A that addresses Optimized ZIRLOTM and demonstrates that Optimized ZIRLOTM has essentially the same properties as currently licensed ZIRLOTM and fits the definition of ZIRLOTM that was used when the Rule change was made to 10 CFR 50.44 and 10 CFR 50.46." Review of Addendum 1 is currently underway and this conclusion has not been acknowledged by the staff. Review of this exemption request needs to remain independent of Addendum 1 to WCAP-12610-P-A/CENPD-404-P-A. Instead of referencing Addendum 1, provide all necessary supporting material.
- 2. TS 5.3.1 states, A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. The exemption request states that the reload design will ensure that the lead test assemblies (LTAs) are not placed in limiting core locations. Describe the fuel management guidelines and supporting safety analyses used to ensure that the LTAs are not placed in limiting locations.
- 3. The exemption request does not specify fuel duty targets for the eight LTAs.
(a)
Provide fuel duty targets for the eight LTAs, including projected burnup for each reload cycle.
(b)
Is projected burnup expected to exceed the current licensed limit for ZIRLOTM?
(c)
Is projected fuel duty expected to exceed limits of less than 100 microns of predicted oxidation with no blistering or spallation?
- 4. The exemption request does not specify post-irradiation examinations for the eight LTAs.
Provide the details of the examinations (e.g., visual, fuel assembly length, fuel assembly bow, fuel assembly drag, fuel rod length, fuel rod wear, fuel rod profilometry, cladding oxidation, etc.) planned for the LTAs.
- 5. How will DNC/Westinghouse ensure that fuel performance models and fuel duty predictions remain conservative for this developmental cladding material, especially in subsequent cycles.
- 6. Attachment 1, Page 7, of DNC letter dated July 1, 2003, states, Application of the Baker-Just equation has been demonstrated to be appropriate for the Optimized ZIRLOTM alloy. Due to the similarities in the composition of the Optimized ZIRLOTM and standard ZIRLOTM, the application of the Baker-Just equation will continue to conservatively bound all post-loss-of-coolant accident scenarios.
(a)
In the first sentence, did you mean to state that the Baker-Just equation has been demonstrated to be appropriate for standard ZIRLOTM?
(b)
If it is correctly written, where has the Baker-Just equation been previously demonstrated to be appropriate for Optimized ZIRLOTM?