ML16132A080
| ML16132A080 | |
| Person / Time | |
|---|---|
| Site: | Hatch, PROJ0704  |
| Issue date: | 05/05/2016 |
| From: | Hanley T, Mcgehee A Electric Power Research Institute |
| To: | Michael Orenak Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16132A080 (2) | |
Text
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RESEARCH INSTITUTE 2016-047 ________________,BWR Vessel & Internals Project (BWRVIP)
May 5, 2016 Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Attention:
Subject:
Project No. 704 - Hatch Unit 1 Surveillance Capsule Test Results Report
Reference:
BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, EPRI, Palo Alto, CA: 2012. 1025144.
The purpose of this letter is to request that an extension of the date to submit the Hatch Unit 1 300° reactor pressure vessel surveillance capsule summary technical report to the NRC in accordance with 10 CFR 50 Appendix H.IV.A.
The Hatch Unit 1 300° capsule was withdrawn from the reactor on February 13, 2016 in accordance with the BWRVIP Integrated Surveillance Program (ISP) withdrawal schedule documented in BWRVIP-86, Revision 1-A, referenced above. The BWR ISP capsule reports go through the BWRVIP's committee review process that adds 2 to 3 months to completion and publication of the capsule report. Given the current timeline, the BWRVIP's report review and approval process, and experience with prior ISP reports, submittal of the Hatch Unit I 300° capsule report cannot be completed within the 1 year requirement of 10 CFR 50 Appendix H.IV.A.
Testing of the capsule contents will comply with the requirements of 10 CFR 50 Appendix H. The final report will be completed and transmitted to the NRC no later than August 31, 2017.
It should be noted that the plate material in the Hatch Unit I 300° capsule is identified in BWRVIP-86, Revision 1-A, as representative for target plate materials for the Hatch Unit 1 and Enrico Fermi Unit 2 reactor vessels.
The plate representative material in the 300°capsule is a heat specific match to material in the Hatch Unit I reactor vessel and therefore, direct use will be made of the surveillance data. Hatch Unit 1 's current Effective Full Power Years (EFPY) is 34.2 and the plant's current NRC approved Pressure-Temperature (P-T) limit curves are valid for 54 EFPY of operation. In addition, a license amendment request (ML15092A856) has been submitted to the NRC to move the Hatch Unit 1 P-T curves to a Pressure and Temperature Limits Report (PTLR). The PTLR submitted as part of the license amendment request includes Together... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillviaw Avenue, Polo Aho, CA 94304*1395 USA* 650.855.2000 *Customer Service 800.313.3774
- www.opri.com
I.J.J*
BWRVIP 2016-047 P-T limit curves for 38 and 49.3 EFPY.
The plate representative material in the 300°capsule is not a heat specific match to material in the Enrico Fermi Unit 2 reactor vessel and therefore, direct use will not be made of the surveillance data. There will be no impact of the surveillance data on the Enrico Fermi Unit 2 P-T limit curves.
The weld material in the Hatch Unit 1 300° capsule is not identified in BWRVIP-86, Revision 1-A, as representative for any reactor vessel weld materials in the BWR fleet. Therefore, the surveillance data for the Hatch Unit 1 weld material will not be used.
If you have any questions on this subject, please contact Drew Odell (Exelon Corp., BWRVIP Integration Committee Technical Chairman) by email at andrew.odell@exeloncorp.com or by telephone at 610.765.5483.
Sincerely, Andrew McGehee, EPRI, BWRVIP Program Manager Tim Hanley, Exelon, BWRVIP Chairman c:
M. Orenak, NRR Project Manager - Hatch C. Haney, NRC Regional Administrator D. Hardage, NRC Senior Resident Inspector-Hatch J. McHale, NRC A. Odell, Exelon Corp.
A. McGehee, EPRI C. Pierce, Soµthem Co.
A. Gordon, Southern Co.
D. Atwood, Southern Co.
T. Wells, Southern Co.
2
I I
'-r*
I e~~11 ELECTRIC POWER
- -*~
RESEARCH INSTITUTE 2016-047 ________________,BWR Vessel & Internals Project (BWRVIP)
May 5, 2016 Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Attention:
Subject:
Project No. 704 - Hatch Unit 1 Surveillance Capsule Test Results Report
Reference:
BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, EPRI, Palo Alto, CA: 2012. 1025144.
The purpose of this letter is to request that an extension of the date to submit the Hatch Unit 1 300° reactor pressure vessel surveillance capsule summary technical report to the NRC in accordance with 10 CFR 50 Appendix H.IV.A.
The Hatch Unit 1 300° capsule was withdrawn from the reactor on February 13, 2016 in accordance with the BWRVIP Integrated Surveillance Program (ISP) withdrawal schedule documented in BWRVIP-86, Revision 1-A, referenced above. The BWR ISP capsule reports go through the BWRVIP's committee review process that adds 2 to 3 months to completion and publication of the capsule report. Given the current timeline, the BWRVIP's report review and approval process, and experience with prior ISP reports, submittal of the Hatch Unit I 300° capsule report cannot be completed within the 1 year requirement of 10 CFR 50 Appendix H.IV.A.
Testing of the capsule contents will comply with the requirements of 10 CFR 50 Appendix H. The final report will be completed and transmitted to the NRC no later than August 31, 2017.
It should be noted that the plate material in the Hatch Unit I 300° capsule is identified in BWRVIP-86, Revision 1-A, as representative for target plate materials for the Hatch Unit 1 and Enrico Fermi Unit 2 reactor vessels.
The plate representative material in the 300°capsule is a heat specific match to material in the Hatch Unit I reactor vessel and therefore, direct use will be made of the surveillance data. Hatch Unit 1 's current Effective Full Power Years (EFPY) is 34.2 and the plant's current NRC approved Pressure-Temperature (P-T) limit curves are valid for 54 EFPY of operation. In addition, a license amendment request (ML15092A856) has been submitted to the NRC to move the Hatch Unit 1 P-T curves to a Pressure and Temperature Limits Report (PTLR). The PTLR submitted as part of the license amendment request includes Together... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillviaw Avenue, Polo Aho, CA 94304*1395 USA* 650.855.2000 *Customer Service 800.313.3774
- www.opri.com
I.J.J*
BWRVIP 2016-047 P-T limit curves for 38 and 49.3 EFPY.
The plate representative material in the 300°capsule is not a heat specific match to material in the Enrico Fermi Unit 2 reactor vessel and therefore, direct use will not be made of the surveillance data. There will be no impact of the surveillance data on the Enrico Fermi Unit 2 P-T limit curves.
The weld material in the Hatch Unit 1 300° capsule is not identified in BWRVIP-86, Revision 1-A, as representative for any reactor vessel weld materials in the BWR fleet. Therefore, the surveillance data for the Hatch Unit 1 weld material will not be used.
If you have any questions on this subject, please contact Drew Odell (Exelon Corp., BWRVIP Integration Committee Technical Chairman) by email at andrew.odell@exeloncorp.com or by telephone at 610.765.5483.
Sincerely, Andrew McGehee, EPRI, BWRVIP Program Manager Tim Hanley, Exelon, BWRVIP Chairman c:
M. Orenak, NRR Project Manager - Hatch C. Haney, NRC Regional Administrator D. Hardage, NRC Senior Resident Inspector-Hatch J. McHale, NRC A. Odell, Exelon Corp.
A. McGehee, EPRI C. Pierce, Soµthem Co.
A. Gordon, Southern Co.
D. Atwood, Southern Co.
T. Wells, Southern Co.
2