ML080590022
| ML080590022 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/29/2008 |
| From: | John Hughey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Sanders, Carleen, NRR/DORL 415-1603 | |
| References | |
| TAC MD3458 | |
| Download: ML080590022 (4) | |
Text
February 29, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - 10 CFR PART 50 APPENDIX H, TEST REPORT REQUIREMENTS: REVIEW OF REPORT WCAP-16629-NP, REVISION 0, ANALYSIS OF CAPSULE W FROM THE DOMINION NUCLEAR CONNECTICUT MILLSTONE UNIT 3 REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM, SEPTEMBER 2006 (TAC NO. MD3458)
Dear Mr. Christian:
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements (the rule), provides the Nuclear Regulatory Commissions (NRC) surveillance and testing requirements for ferritic components of the reactor vessels (RVs) of operating U.S. light-water reactors. The rule requires licensed owners of U.S. light-water reactor facilities to install a number of surveillance capsules within the cavities of their RVs and to remove capsules and test the capsule materials in accordance with the withdrawal schedule and testing requirements of the American Society for Testing and Materials (ASTM) Standard Practice E-185. Paragraph IV.A of the rule requires the RV material surveillance capsule test results to be the subject of a summary technical report that is required to be submitted to the NRC within one year of the capsule withdrawal date. Paragraph IV.B of the rule specifies that these reports shall include all data required by ASTM Standard Practice E-185-82 and the results of all fracture toughness tests conducted on the surveillance capsule materials in both the unirradiated and irradiated condition.
By letter dated October 2, 2006, Dominion Nuclear Connecticut, Inc. (the licensee) submitted WCAP-16629-NP, Revision (Rev.) 0, Analysis of Capsule W from the Dominion Nuclear Connecticut Millstone Unit 3 Reactor Vessel Radiation Surveillance Program, September 2006, to comply with the above requirements. WCAP-16629-NP, Rev. 0, provides the applicable fracture toughness test data for surveillance capsule W, which was removed from the Millstone Power Station, Unit No. 3 (MPS3) RV during the fall 2005 refueling outage. This report also re-analyzes all prior data that was in earlier reports for MPS3 surveillance capsules U and X.
The surveillance program for the MPS3 RV currently utilizes the plants own surveillance capsules as the basis for monitoring the embrittlement trends for the RV beltline materials. The surveillance weld materials being irradiated in the MPS3 surveillance capsules were fabricated from Heat No. 4P6052 weld wires. The Heat No. 4P6052 surveillance weld is representative of all beltline welds in the MPS3 RV. The surveillance plate materials being irradiated in the MPS3 surveillance capsules were fabricated from Heat No. C-4039-2, which is representative of Intermediate Shell Plate No. B9805-1.
The NRC staff has performed its preliminary review of WCAP-16629-NP and has confirmed that the report includes all of the data and test results that are required by Paragraph IV.B of 10 CFR Part 50, Appendix H and by ASTM Standard Practice E185-82. Furthermore, based on this preliminary review, the NRC staff has not identified any immediate safety issues associated with the information provided in WCAP-16629-NP. Therefore, the NRC staff intends to forward this report to the Pacific Northwest National Laboratory for the purpose of officially updating the surveillance data in the NRC staffs Reactor Vessel Integrity Database. The licensee will be expected to incorporate the updated surveillance data into the next revision of MPS3 pressure-temperature limits, as required by 10 CFR Part 50, Appendix G.
This completes the NRC staffs efforts on TAC No. MD3458. Please contact me at 301-415-1603 if you have any questions.
Sincerely,
/ra/
John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-423 cc: See next page The NRC staff has performed its preliminary review of WCAP-16629-NP and has confirmed that the report includes all of the data and test results that are required by Paragraph IV.B of 10 CFR Part 50, Appendix H and by ASTM Standard Practice E185-82. Furthermore, based on this preliminary review, the NRC staff has not identified any immediate safety issues associated with the information provided in WCAP-16629-NP. Therefore, the NRC staff intends to forward this report to the Pacific Northwest National Laboratory for the purpose of officially updating the surveillance data in the NRC staffs Reactor Vessel Integrity Database. The licensee will be expected to incorporate the updated surveillance data into the next revision of MPS3 pressure-temperature limits, as required by 10 CFR Part 50, Appendix G.
This completes the NRC staffs efforts on TAC No. MD3458. Please contact me at 301-415-1603 if you have any questions.
Sincerely,
/ra/
John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-423 cc: See next page DISTRIBUTION:
PUBLIC LPL1-2 R/F RidsNrrDorlLpl1-2 RidsNrrPMJHughey RidsNrrLAABaxter RidsRgn1MailCenter RidsAcrsAcnwMailCenter RidsOgcRp MMitchell, NRR CSydnor, NRR ADAMS Accession No.:ML080590022
- By memorandum dated OFFICE LPL1-2/GE LPL1-2/PM LPL1-2/LA DCI/CVIB LPL1-2/BC NAME CSanders JHughey ABaxter MMitchell*
HChernoff DATE 02/28/2008 02/28/2008 02/28/2008 02/22/2008 02/29/2008 Official Record Copy
Millstone Power Station, Unit No. 3 cc:
Lillilan M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
Building 475, 5th Floor 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. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's 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 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. Joseph Roy, Director of Operations 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.
Building 475, 5th Floor 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. William D. Bartron Licensing Supervisor Dominion Nuclear Connecticut, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385 Mr. David A. Sommers Dominion Resources Services, Inc.
5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711