ML14064A321

License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information

ML14064A321
Person / Time
Site:	Nine Mile Point
Issue date:	02/25/2014
From:	John Stanley Constellation Energy Nuclear Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14064A321 (2)

Text

This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachments (6) and (7).

James J. Stanley Office: 315-349-5205 Plant General Manager-Nine Mile Point Fax: 315-349-1321 E-mail: James.Stanley@cengllc.com CENG.

a joint venture of consteatnergy, NINE MILE POINT NUCLEAR STATION February 25, 2014 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 Docket No. 50-4 10 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information

REFERENCE:

(a) Letter from P. Swift (NMPNS) to Document Control Desk (NRC), dated November 1, 2013, License Amendment Request Pursuant to 10 CFR 50.90:

Maximum Extended Load Line Limit Analysis Plus Nine Mile Point Nuclear Station, LLC (NMPNS) hereby provides supplemental information to the Nine Mile Point Unit 2 (NMP2) License Amendment Request for Maximum Extended Load Line Limit Analysis Plus (MELLLA Plus), Reference (a). The supplemental information satisfies the commitment made in Reference (a) and provides 1) the cycle specific Supplemental Reload Licensing Report (SRLR) and Fuel Bundle Information Report (FBIR), and 2) a cycle - specific core design loading map and summary of differences between the reference design described in the MELLLA Plus Safety Analysis Report and the cycle-specific core design.

Submittal of the SRLR and FBIR satisfy MELLLA+ Licensing Topical Report (LTR) Limitation and Condition 12.4. Submittal of the cycle-specific core design satisfies the NRC staff request made at the MELLLA+ pre-submittal meeting on February 27, 2013 .and documented in the March 13, 2013 summary of the meeting (TAC NO MF0587).

The supplemental information provided in the attachments was prepared by Global Nuclear Fuel -

Americas LLC (GNF-A). The SRLR is provided in Attachment (1). The cycle-specific core design Nine Mile Point Nuclear Station P.O. Box 63, Lycoming, NY 13093 This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachments (6) and (7).

Document Control Desk February 25, 2014 Page 2 loading map is on page 25 of the SRLR. The FBIR is GNF-A proprietary report 000N0123-FBIR-P. The non-proprietary version of the FBIR is provided in Attachment (2). The affidavit from GNF-A detailing the reasons for the request to withhold the proprietary information in the FBIR is provided in Attachment (4). The proprietary version of the FBIR is provided in Attachment (6). The comparison of the MELLLA Plus reference design to the cycle 15 specific core design is GNF-A Report 000N2495-R1-P. The non-proprietary version of GNF-A Report 000N2495-RI-P is provided in Attachment (3). The affidavit from GNF-A detailing the reasons for the request to withhold the proprietary information in GNF-A Report 000N2495-R1-P is provided in Attachment (5). The proprietary version of GNF-A Report 000N2495-Ri-P is provided in Attachment (7). Attachments (6) and (7) are considered to contain proprietary information exempt from disclosure pursuant to 10 CFR 2.390. Therefore, on behalf of GNF-A, NMPNS hereby makes application to withhold these attachments from public disclosure in accordance with 10 CFR 2.390(b)(1).

Pursuant to 10 CFR 50.91(b)(1), NMPNS has provided a copy of this supplemental letter to the appropriate state representative. This supplemental letter does not change the initial determination of "no significant hazards consideration" justified in the original amendment request, Reference (a).

Should you have any questions regarding the information in this submittal, please contact Everett (Chip)

Perkins, Director Licensing, at (315) 349-5219.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February 25, 2014.

Sincerely, CRC/KJK Attachments (1) Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2), Reload 14 Cycle 15, Extended Power Uprate (EPU)/ Maximum Extended Load Line Limit Plus (MELLLA+) (00ON0123-SRLR)

(2) Fuel bundle Information Report for Nine Mile Point 2, Reload 14 Cycle 15 (00ON0123-FBIR-NP) (Non-proprietary)

(3) Nine Mile Point Nuclear Station Unit 2, Comparison of MELLLA+ Reference Design to Cycle 15 Design Characteristics (000N2495-RI-NP) (Non-proprietary)

(4) Affidavit from Global Nuclear Fuel - Americas, LLC (GNF-A) Justifying Withholding Proprietary Information Contained in Attachment (6)

(5) Affidavit from Global Nuclear Fuel - Americas, LLC (GNF-A) Justifying Withholding Proprietary Information Contained in Attachment (7)

(6) Fuel bundle Information Report for Nine Mile Point 2, Reload 14 Cycle 15 (00ON0123-FBIR-P) (Proprietary)

(7) Nine Mile Point Nuclear Station Unit 2, Comparison of MELLLA+ Reference Design to Cycle 15 Design Characteristics (000N2495-RI-P) (Proprietary) cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC A. L. Peterson, NYSERDA (without Attachments (6) and (7))