ML100610677
| ML100610677 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/04/2010 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | John Carlin Ginna |
| Pickett D | |
| References | |
| TAC ME1500, WCAP-17036-NP, Rev 0 | |
| Download: ML100610677 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 4, 2010 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REVIEW OF WCAP-17036-NP, "ANALYSIS OF CAPSULE N FROM THE RE.
GINNA REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM,"
REVISION 0 - RE. GINNA NUCLEAR POWER PLANT (TAC NO. ME1500)
Dear Mr. Carlin:
Appendix H to Part 50 of 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 Commission's (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 1 year of the capsule withdrawal date.
Paragraph IV.B of the rule requires that these reports shall include all data specified 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 May 29, 2009, as supplemented by letter dated February 18, 2010, RE. Ginna Nuclear Power Plant, LLC, the licensee, submitted WCAP-17036-NP, Revision 0, "Analysis of Capsule N from the RE. Ginna Reactor Vessel Radiation Surveillance Program," May 2009, to comply with the above requirements. WCAP-17036-NP provides the applicable fracture toughness test data for surveillance capsule N, which was removed from the R.E. Ginna Nuclear Power Plant (Ginna) RV after exposure to neutron radiation equivalent to 30.5 effective full-power years of facility operation. This report also re-analyzes all prior data that was reported in earlier reports for Ginna surveillance capsules R, S, T, and V.
The surveillance program for the Ginna RV currently utilizes the plant's own surveillance capsules as the basis for monitoring the embrittlement trends for the RV beltline materials. The surveillance weld material being irradiated in the Ginna RV surveillance capsules was fabricated from Heat No. 61782 weld wires. The Heat No. 61782 surveillance weld is representative of the intermediate-to-Iower shell circumferential weld in the Ginna RV. The surveillance plate materials being irradiated in the Ginna RV surveillance capsules are representative of RV Lower Shell Plate 125P666 and Intermediate Shell Plate 125S255.
The NRC staff has performed its review of WCAP-17036-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 review, the
J. Carlin
- 2 staff has not identified any immediate safety issues associated with the information provided in report number WCAP-17036-NP. Therefore, the staff intends to forward this report to the Pacific Northwest National Laboratory for the purpose of officially updating the surveillance data in the staffs Reactor Vessel Integrity Database. The licensee will be expected to incorporate the updated surveillance data into the next revision of the plant's pressure-temperature limits report, as required by 10 CFR Part 50, Appendix G.
Please contact me at 301-415-1364 if you have any questions.
Sincerely,
.~ V r~tt Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Requlation Docket No. 50-244 cc: Distribution via Listserv
ML100610677 OFFICE LPL1-1/PM LPL1-1/LA CVIB/BC BC/LPL 1-1 NAME DPickett SLittie MMitchell memo dated NSalgado DATE 03/04/10 03/04/10 02/25/10 03/04/10