ML14246A396

NMP Unit 2, MF3056, 4th Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)

ML14246A396
Person / Time
Site:	Nine Mile Point
Issue date:	09/03/2014
From:	Bhalchandra Vaidya Plant Licensing Branch 1
To:	Kristensen K, Tom Loomis, Syrell T Exelon Corp, Nine Mile Point
Vaidya B, NRR/DORL/LPL1-1, 415-3308
References
TAC MF3056
Download: ML14246A396 (2)

Text

From: Vaidya, Bhalchandra Sent: Wednesday, September 03, 2014 12:50 PM To: 'Terry.Syrell@exeloncorp.com'; Kristensen, Kenneth J:(NMP)

(kenneth.kristensen@exeloncorp.com); Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)

Cc: Beasley, Benjamin; Stattel, Richard; Thorp, John; Bucholtz, Kristy; Elliott, Robert; Dozier, Jerry; Shoop, Undine; Guzzetta, Ashley; Huang, Tai; Jackson, Christopher; Karipineni, Nageswara; Dennig, Robert; Panicker, Mathew; Dean, Jeremy; Weerakkody, Sunil; Eagle, Eugene; Green, Brian; Ki, DaBin; Chung, Donald

Subject:

NMP Unit 2, MF3056, 4th Round of DRAFT RAIs - LAR RE: License Amendment Request- RE: Maximum Extended Load Line Limit Analysis Plus (MELLLA+)

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 - FORTH ROUND OF REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) (TAC NO. MF3056)

By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS)

Package Accession No. ML13316B090), as supplemented by letters dated January 21, 2014 (ADAMS Accession No. ML14023A654), February 14, 2014 (ADAMS Package Accession No. ML14051A155),

February 25, 2014 (ADAMS Accession No. ML14064A321), March 10, 2014 (ADAMS Accession No. ML14071A466), May 14, 2014 (ADAMS Accession No. ML14139A416), and June 13, 2014 (ADAMS Accession No ML14169A034), Nine Mile Point Nuclear Station, LLC (the licensee) submitted a license amendment request for Nine Mile Point Nuclear Station, Unit 2. The proposed amendment would allow (1) operation in the expanded maximum extended load line limit analysis plus (MELLLA+) domain; (2) use of the Detect and Suppress Solution - Confirmation Density, DSS-CD stability solution; (3) use of the TRACG04 analysis code; (4) increase the isotopic enrichment of boron-10 in the sodium pentaborate solution used to prepare the neutron absorber solution in the Standby Liquid Control System (SLS); and (5) increase the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loops in operation.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your LAR and has determined that additional information is needed to complete its review. The NRC staffs DRAFT request for additional information (RAI) is provided below.

===============================

DRAFT RAIs for SAFETY EVALUATION INPUT RELATING TO LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS FOR NINE MILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. MF3056)

By letter dated November 1, 2013 (Agencywide Document Access and Management System (ADAMS)

Package No. ML13316B090), the licensee submitted a license amendment request for Maximum Extended Load Line Limit Analysis Plus (MELLLA+) and the use of the General Electric Hitachi Nuclear Energy (GEH) analysis code TRACG04. The proposed amendment request would allow operation in the expanded MELLLA+ domain.

Upon review of two documents, Attachment 10 to the 11/01/13 submittal titled, NEDC-33576NP, Safety Analysis Report for Nine Mile Point Unit 2 Maximum Load Line Limit Analysis Plus, and, attachment to

the 02/14/14 submittal titled, Response to NRC Request for Supplement Information in Support of NMP2 MELLLA+ LAR Acceptance Review, the staff has the following requests for additional information:

RAI # APHB-1: Please describe any operator manual actions that will be added, deleted, or changed to support the proposed license amendment, including reductions in time available to complete the actions.

RAI # APHB-2: Please quantify the reductions in time available for operator actions and provide the process used to validate that all necessary human actions can be reliably completed within the available time.

RAI # APHB-3: Please provide the NRC with any operating experience that was used in this proposed change. These may include but are not limited to plant-specific condition reports, Licensee Event Reports, INPO reports, prior implementations of the MELLLA+ design, and other relevant sources.

RAI # APHB-4: As a result of the implementation, please describe any changes to the procedures, training documents, displays, and simulator referred to on page 89/119 of the submittal.

RAI # APHB-5: Will any changes to the Safety Parameter Display System be required? If yes, describe.

==================================

The NRC staff would like to receive the responses to the RAIs within 30 days from the date of this communication. Please contact me, ASAP, to schedule a telephone conference between the licensee and the NRC staff to ensure that the licensee clearly understands the RAIs and also, to obtain a firm commitment/ confirmation from the licensee for the Responses to these RAIs.

Please contact me, if you have any questions.

Thanks, Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov