ML16281A118
| ML16281A118 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/17/2016 |
| From: | Mozafari B Plant Licensing Branch 1 |
| To: | Bryan Hanson Exelon Nuclear, Nine Mile Point |
| Mozafari B, NRR/DORL/LPL1-1, 415-2020 | |
| References | |
| CAC MF7497 | |
| Download: ML16281A118 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 October 17, 2016
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - CORRECTION TO LICENSE AMENDMENT NO. 158, RE: REACTIVITY ANOMALIES (CAC NO. MF7497)
Dear Mr. Hanson:
By letter dated September 15, 2016, Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16188A029, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 158 to Renewed Facility Operating License (FOL) No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2 (NMP2). This amendment consisted of changes to the technical specifications (TSs) in response to the Exelon Generation Company, LLC (Exelon, the licensee) application dated March 18, 2016, (ADAMS Accession No. ML16078A065).
This amendment approved changes to the Technical Specifications to modify TS 3.1.2, "Reactivity Anomalies" for Unit 2, by changing the method used to perform the reactivity anomaly surveillance. Specifically, the amendment would allow performance of the surveillance based on the difference between the monitored (i.e., actual) core reactivity and the predicted core reactivity. The surveillance is currently performed based on the difference between the monitored control rod density and the predicted control rod density.
Subsequent to issuance of the amendment, the NRC staff determined that paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69, "Technical Specifications and Environmental Protection Plan," inadvertently cited the previous Amendment No. 157 in lieu of the current Amendment No. 158.
Enclosed is the corrected page 4 of the NMP2 renewed FOL with a marginal line indicating the revision to the page. This correction does not change any of the NRC staff's conclusions in the safety evaluation associated with the amendment.
Please replace the current page 4 with the corrected page 4 of the FOL to correctly include Amendment No. 158. If there are any questions regarding this matter, please contact me at 301-415-2020.
Docket No. 50-41 O
Enclosure:
As stated cc w/encl: Distribution via Listserv Sincerely, Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation
- (1)
Maximum Power Level Exelon Generation is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are Attached hereto, as revised through Amendment No. 158 are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Fuel Storage and Handling (Section 9.1.SSER 4)*
- a.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b.
When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or Storage racks in the New Fuel Vault or Spent Fuel Storage Facility
- c.
The above three fuel assemblies shall maintain a minimum edge-To-edge spacing of twelve (12) inches from the shipping container Array and approved storage rack locations.
- d.
The New Fuel Storage Vault shall have no more than ten fresh Fuel assemblies uncovered at any one time.
(4)
Turbine System Maintenance Program (Section 3.5.1.3.1 OSER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the Manufacturer's calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 16, 1990 from Robert Martin to Mr. Lawrence Burkhardt, Ill).
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-69 Amendment 117 through 140, 141, 143, 144, 145, 146, 147, 150, 151, 152, 154, 156, M, 158
ML16281A118 OFFICE NRR/DORL/LPL 1-1/PM NRR/DORL/LPL 1-1/LA NRR/DORL/LPL 1-1/PM NRR/DORL/LPL 1-1/BC NAME BMozafari KGoldstein BMozafari TT ate DATE 10/17/2016 10/12/2016 10/17/2016 10/17/2016