ML061530114
| ML061530114 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Surry, North Anna  |
| Issue date: | 06/01/2006 |
| From: | Grecheck E Dominion Nuclear Connecticut, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-319, DOM-NAF-2, TAC MC4571, TAC MC4572, TAC MC4573, TAC MC4574, TAC MC4575, TAC MC4576 | |
| Download: ML061530114 (6) | |
Text
Dominion Resources Services, Inc.
5000 Dominion Boulevard, Glen Allcn, VA 2 3060 June 1, 2006 U.S. Nuclear Regulatory Com mission Attention: Document Control Desk Washington, D.C. 20555 Serial No.06-319 NL&OS/ETS RO Docket Nos. 50-3361423 50-338/339 50-280/281 License Nos. DPR-65 N P F-49 N P F-4/7 DPR-32/37 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)
VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
MILLSTONE POWER STATION UNIT NOS. 2 AND 3 NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 SURRY POWER STATION UNIT NOS. 1 AND 2 REQUESTED CLARIFICATION OF THE NRC SER
/TAC NOS. MC4571. MC4572. MC4573. MC4574. MC4575. AND MC4576)
FOR DOMINION FLEET REPORT DOM-NAF-2 In a September 30, 2004 letter, as supplemented in letters dated January 13, June 30 and September 8, 2005, Dominion requested approval of fleet report DOM-NAF-2, "Reactor ICore Thermal-Hydraulics Using the VIPRE-D Computer Code." By letter dated April 4, 2006, the NRC documented approval of Dominion's fleet report DOM-NAF-2. In a May 18, 2006 telephone conference call with the NRC staff (Messrs. S.R. Monarque and L. W. Ward), Dominion discussed SER language that could potentially limit the application of the fleet report to specific fuel types or vendors. The NRC staff concurred that the current wording could impose unintended restrictions on the application of DOM-NAF-2, aind verbally agreed to revise the SER. For convenience, the NRC staff requested that Dominion provide specific mark-ups identifying the locations in the SER that are believed to limit the application of DOM-NAF-2 to specific fuel vendors. The requested information is provided in the attachment to this letter.
During the May 18th conference call, the NRC also stated that the request to publish the accepted version of DOM-NAF-2 within 90-days of approval could be postponed until after a revised SER was issued by the NRC staff.
06-31 9 Docket Nos. 50-336/423, 50-338/339, 50-2801281 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.
Very truly yours, Eugene S. Grecheck Vice President - Nuclear Support Services Virginia Electric and Power Company Dominion Nuclear Connecticut, Inc.
Attach men t Commitmlents made in this letter: None
06-31 9 Docket Nos. 50-336/423, 50-338/339, 50-280/281 Page 3 of 3 cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, Pennsylvania 19406-1 41 5 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. Stephen R. Monarque NFlC Project Manager - Surry and North Anna U. S. Nuclear Regulatory Commission, Mail Stop 8 H12 Onle White Flint North 1 11555 Rockville Pike Rockville, Maryland 20852 Mr. V. Nerses NFlC Senior Project Manager - Millstone Units 2 and 3 U. S. Nuclear Regulatory Commission, Mail Stop 8 C2 One White Flint North 1 1 !555 Rockville Pike Rockville, Maryland 20852 Mr,. J. T. Reece NFlC Senior Resident Inspector North Anna Power Station Mr, S. M. Schneider NFIC Senior Resident inspector Millstone Power Station Mr. N. P. Garrett NRlC Senior Resident Inspector Surry Power Station
ATTACHMENT Serial No.06-319 Clarification of the NRC SER for Dominion Fleet Report DOM-NAF-2 Dated April 4,2006 (TAC Nos. MC4571, MC4572, MC4573, MC4574, MC4575, and MC4576)
Dominion Nuclear Connecticut, Inc.
Virginia Electric and Power Company
Serial No.06-319 Docket Nos. 50-336/423, 50-338/339, 50-280/281 Dominion Nuclear Connecticut, Inc.
Virginia Electric and Power Company Clarification of the NRC SER for Dominion Fleet Report DOM-NAF-2 Dated April 4,2006 Discussion In a Sept:ember 30, 2004 letter, as supplemented in letters dated January 13, June 30 and September 8, 2005, Dominion requested approval of fleet report DOM-NAF-2, "Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code."
By letter dated April 4, 2006, the NRC documented approval of Dominion's fleet report DOM-NAF-2. In a May 18, 2006 telephone conference call with the NRC staff (Messrs. S.R.
Monarque and L. W. Ward), Dominion discussed SER language that could potentially limit the application of the fleet report to specific fuel types or vendors. The staff agreed that there is no specific reason to limit the use of the fleet report DOM-NAF-2 to Westinghouse and Framatome (AREVA) fuel and that DOM-NAF-2 could be used with NRC-approved PWR fuel types. While it is true that AREVA and Westinghouse are currently the only available fuel vendors for PWR nuclear reactors in the US, this situation may change in the future. If that were the case, Dominion would be required to submit for NRC review and approval an additional appendix to DOM-NAF-2 qualifying any new CHF correlations associated with the new fuel type with the VIPRE-D code.
For convenience, the NRC staff requested that Dominion provide specific mark-ups identifying the locations in the SER that are believed to limit the application of These locations and a few edit:orial changes are provided below: -
SER Clarification SER Section Paraa raDh/Sentence 2.0 Regulatory Evaluation Second paragraph - third DOM-NAF-2 to specific fuel vendors (Westinghouse and AREVA).
enten Therefore, this review addresses the specific application of VIPRE-01 by the licensees to the in the licensees' nuclear steam supply system (NSSS).
NRCapproved PWR fuel types SER Paae 1
2.0 Regulatory Evaluation Last paragraph - second sentence 2
The licensees have previously used the COBRA Illc/MIT computer code (Reference 3) to perform the thermal hydraulic analyses and is submitting this fleet report to replace COBRA Illc/MIT computer code with the VIPRE-D coniputer program along with the new CHF correlations for the various l
=
l a
F NRC-approved PWR fuel designs.
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Serial No.06-319 Docket Nos. 50-336/423, 50-338/339, 50-280/281 SER Section Paraa raDh/Sentence SER Paae 3.0 Technical Evaluation First paragraph - first sentence 2
In order to evaluate DNB in the licensees NSSS for the NRC-approved PWR fuel types, the NRC staff reviewed the application of the VIPRE-D code along with the various pertinent code correlations and models, fuel-specific CHF correlations, and DNBR design limits.
3.0 Technical Eva1 uati o n Fourth paragraph - second sentence The licensees only added the new CHF correlations (Reference 1, Appendix A and Reference 2, Appendix B) to accommodate the DNBR assessments of the NRC-approved PWR fuel types.
3.3 Compliance with the Fifth paragraph - item (4)
VIPRE-01 SER 2
4 (4) As required by the NRC staff in Reference 4, the following model options were reviewed and justified by the licensees for use in the DNB evaluation of the Framamw&ebNRC-approved PWR fuel.
4.0 Conclusion First paragraph -third sentence 9
The VIPRE-D fuel design limits are also found to be acceptable by the NRC staff for the NRC-approved PWR fuels types listed herein.
In addition, Dominion has identified the following typographical errors:
SER Section Paraarar>h/Sentence 3.3 Compliance with the Sixth paragraph - Fuel Rod Model -
VIIPRE-01 SER third sentence SER Paae 5
This approach is consistent with previous approved licensees methodologies fReWewe4) (Reference 3).
3.5 Correlations and DNBR Limits Last paragraph - last sentence 8
For the MSLB the limit of 1.45 will be used for pressures 500 to WQ-psia 1000 psia and the limit of 1.3 will be used for pressures above 1000 psia.
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