SBK-L-15172, Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
| ML15257A212 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/08/2015 |
| From: | Dean Curtland NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LAR 14-04, SBK-L-15172 | |
| Download: ML15257A212 (2) | |
Text
NEXTe ra ENERGY ~
September 8, 2015 10 CFR 50.90 SBK-L-15 172 Docket No. 50-443 U. S. Nuclear RegUlatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure -
Temperature Limits Applicable for 55 Effective Full Power Years
References:
- 1. Seabrook Station License Amendment Request 14-04, "Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years," SBK-L-14 102, July 24, 2014 (ML14216A404).
- 2.
Seabrook Station Letter SBK-L-15 132 "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure -
Temperature Limits Applicable for 55 Effective Full Power Years," July 9, 2015.
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 14-04 to the Technical Specifications (TS) for Seabrook Station and requested an exemption from the requirements of 10 CFR 50 Appendix G. The proposed change revises the pressure-temperature (PIT) limits in TS 3/4.4.9 LCO 3.4.9.1, Reactor Coolant System Pressure-Temperature Limits, to be applicable to 55 effective full power years. The change also revises TS 3/4.4.9 LCO 3.4.9.3, Overpressure Protection Systems, by providing new overpressure protection setpoints and lowering the RCS temperature at which the TS is applicable.
In Reference 2, NextEra indicated that a "No Significant Hazards Consideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3" in response to the RAJ 2-2.1. NextEra is sending this letter to clarify that the revised TS changes in Reference 2 did not expand the scope of the original submittal. Additionally, NextEra is clarifying the informnation in Reference 2 to conclude that the revision to the revised TS changes as a result of the response to RAI 2-2.1 does not alter the conclusion in the original submittal that the proposed Arm 1 NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L-15172/Page 2 change does not involve a significant hazards consideration pursuant to 10 CFR 50.92 and there are no significant environmental impacts associated with the change. Therefore, please disregard the No Significant Hazards Consideration (NSHC) discussion in Reference 2, and only rely upon the NSHC discussion in Reference 1.
This letter contains no regulatory commitments.
Should you have any questions regarding this letter, please contact Mr. Michael Ossing, Licensing Manager, at (603) 773-7512.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 6
, 2015.
Sincerely, NextEra Energy Seabrook, LLC Dean Curtland Site Vice President Enclosure cc:
D. Dorman, NRC Region I Administrator J. Lamb, NRC Project Manager, Project Directorate 1-2 P. Cataldo, NRC Senior Resident Inspector Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 0 1702-5399