ML16001A002

North Carolina State University - Response Submittal 2 to the Request for Additional Information for Technical Specification Amendment 19 - Use of 6 Percent Enriched Fuel

ML16001A002
Person / Time
Site:	North Carolina State University
Issue date:	12/31/2015
From:	Hawari A I North Carolina State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MF6088
Download: ML16001A002 (19)

Text

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC SUBJECT RESPONSE SUBMITTAL 2 TO THE REQUEST FOR ADDITIONAL INFORMATION FOR TECHINCAL SPECIFICATION AMENDMENT 19 - USE OF 6% ENRICHED FUEL License No. R-120 Docket No. 50-297 Please find enclosed submittal 2 of the response to the Request for Additional Information (RAI) for the License Amendment Request (LAR) related to the use of six percent enriched fuel (TAC NO. MF6088). This submittal supplies the response to RAI question 4. If you have any questions regarding this amendment or require additional information, please contact Andrew Cook at (919) 515-4602 or atcook@ncsu.edu. I declare under penalty of perjury that the forgoing is true and correct. Executed on 31 December 2015. Sincerely, Ayman I. Hawari, Ph.D. Director, Nuclear Reactor Program North Carolina State University

Enclosures:

Submittal 2 - Response to Request for Additional Information

tally_check.sh coreID_peakingfactors.mctaltally_check.outcoreIDstrc1rc8 coreID_burn.out list_ID burn_check.shcoreID_fission_check.datburn_check.out

BOC AnalysisVerify model geometry and materials listSet: kcode 100000 1.017 200 1000 300000 0Generate inputs for excess reactivity, rod worths, critical positionRun standard kcode for all cases using MCNP6Determine critical position, then generate input for peaking factors and verify F7 tally cell listRun kcode with F7 tally for peaking factors using MCNP6Burn-up CalculationUsing the excess reactivity input as a template, insert the necessary burn-up flags in MCNP6 inputVerify the isotope and burn material listSet: kcode 500 1.00000 50 550 100000 0Run kcode with Burn-up using MCNP6Post Burn-up Processing Extract the post burn-up fuel material cards and adjust fuel cell densities for not tracked materials, using in-house scriptGenerate template EOC input deck by inserting new material cards and fuel cell definitionsVerify the insertion of new cardsEOC AnalysisVerify model geometry and materials listSet: kcode 100000 1.017 200 1000 300000 0Generate inputs for excess reactivity, rod worths, critical positionRun standard kcode for all cases using MCNP6Determine critical position, then generate input for peaking factors and verify F7 tally cell listRun standard kcode with F7 tally for peaking factors using MCNP6Core ReconfigurationReconfigure assembly/reflector locations for next coreInsert new fuel cell cards and assemlbies, with the established ID convention, as necessary Verify that all core geometry changes were made correctly, and are consistent with OEMReturn to BOC Analysis