Letter Sequence Supplement |
|---|
|
|
MONTHYEARML14064A3232013-12-31031 December 2013
000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15
Project stage: Request
ML14002A1702014-01-0202 January 2014
Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - MF3056, License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14002A2202014-01-0202 January 2014
Revised Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14023A6542014-01-21021 January 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Commitment Date to Provide Supplemental Information
Project stage: Supplement
ML14028A3982014-01-28028 January 2014
MF3056 - Acceptance of Requested Licensing Action License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Acceptance Review
ML14064A3222014-01-31031 January 2014
00N0123-SRLR, Rev. 2, 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+)
Project stage: Request
ML14051A1382014-02-14014 February 2014
Response to Request for Supplemental Information to License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus
Project stage: Supplement
ML14043A0062014-02-20020 February 2014
First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+)
Project stage: RAI
ML14063A4742014-02-25025 February 2014
License Amendment Request to Relocate the Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report - Supplement to Revise Implementation Date
Project stage: Supplement
ML14064A3212014-02-25025 February 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information
Project stage: Supplement
ML14064A3242014-02-28028 February 2014
000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics
Project stage: Request
ML14029A0392014-03-0505 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated November 1, 2013
Project stage: Withholding Request Acceptance
ML14051A0152014-03-0606 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 14, 2014
Project stage: Withholding Request Acceptance
ML14071A4662014-03-10010 March 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to Srxb RAI 1 and RAI 2
Project stage: Request
ML14071A2422014-03-12012 March 2014
NMP Unit 2, MF3056, 2nd Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
ML14083A0232014-03-31031 March 2014
Second Round of Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: RAI
ML14139A4162014-05-14014 May 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to RAI STSB-1 and RAI STSB-2
Project stage: Response to RAI
ML14204A3692014-08-14014 August 2014
Third Round of Request for Additional Information & Enclosure 1, Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+) (Tac No. MF3056)
Project stage: RAI
ML14065A0902014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 25, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
ML14072A0152014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated March 10, 2014
Project stage: Withholding Request Acceptance
ML14246A3962014-09-0303 September 2014
NMP Unit 2, MF3056, 4th Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus2014-09-15015 September 2014
Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Response to RAI
ML14260A1202014-11-0606 November 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated September 15, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
ML14314A2142014-11-10010 November 2014
MF3056, E-mail Capture - LAR Mellla+, Simulator Audit Plan, November 20-21, 2014 at the Plant Site
Project stage: Approval
ML14321A0642014-11-17017 November 2014
Point Unit 2, MF3056, LAR Mellla+, Supplement to the Simulator Audit Plan
Project stage: Approval
ML14351A4282014-12-11011 December 2014
Updated TIP Comparisons for Current Operating Conditions, GE-PPO- 1GYEF-KG1-742, Enclosure 2
Project stage: Request
ML15002A1622015-01-26026 January 2015
Request for Withholding Information from Public Disclosure Submission Dated December 11, 2014, for Supplement Information for NRC Simulator Audit LAR for Mellla+
Project stage: Withholding Request Acceptance
ML15033A0022015-01-30030 January 2015
MF3056, LAR - Mellla+, Revised RAI - Neutron Fluence Calculation Related
Project stage: RAI
ML15051A4642015-02-18018 February 2015
Response to Fifth Request for Additional Information Concerning License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Request
ML15056A3792015-03-16016 March 2015
Request for Withholding Information from Public Disclosure Submission Dated February 18, 2015, for License Amendment Request Pursuant to 10 CFR 50.90 Maximum Extended Load Line Limit Analysis Plus
Project stage: Withholding Request Acceptance
ML15105A4432015-05-0404 May 2015
Draft Safety Evaluation for License Amendment Request - Mellla+
Project stage: Draft Approval
ML15114A1602015-05-0707 May 2015
Issuance of Simulator Audit Report License Amendment Request Regarding MELLLA Plus
Project stage: Approval
ML15096A0762015-09-0202 September 2015
Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus
Project stage: Approval
ML15210A3262015-09-0404 September 2015
LTR-15-0388-1 - John W. Stetkar Letter Nine Mile Point Nuclear Station Unit 2 Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request
Project stage: Other
2014-03-12
[Table View] |
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))
