ML14203A675

NRR E-mail Capture - Final RAI for Quad Cities Regarding Use of Neutron Absorbing Inserts (TAC Nos.: MF2489 and MF2490)

ML14203A675
Person / Time
Site:	Quad Cities
Issue date:	07/22/2014
From:	Mozafari B Division of Operating Reactor Licensing
To:	Nicely K Exelon Corp
References
MF2489, MF2490
Download: ML14203A675 (3)

Text

NRR-PMDAPEm Resource From: Mozafari, Brenda Sent: Tuesday, July 22, 2014 11:48 AM To: Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com)

Subject:

Final RAI for QUAD CITIES REGARDING USE OF NEUTRON ABSORBING INSERTS (TAC NOS.: MF2489 AND MF2490)

Importance: High

Ken, This is a repeat of our previous RAI. We would like to finalize it by letter but before doing so as we discussed with you during our RAI clarification call with Quad Cities on 6/26, we wanted to schedule a follow-up call to clarify what you plan to submit as a response to the third RAI submitted as part of Round 2. At the time of the 6/26 call, the you did not appear to have a fully developed plan for addressing this third question. At this time, you should be able to provide a reasonable level of detail regarding your approach. We would recommend Thursday afternoon (7/17/14), ending by 4 pm. This call should not take more than half an hour. Let me know if a different time would be preferred.

Additional RAI -

By letter dated July 16, 2013, (Agencywide Documents Access and Management Systems Accession Number [ADAMS] ML13199A037), Exelon Generation Company, LLC. (the licensee),

submitted a license amendment request to revise the Quad Cities Nuclear Station, Units 1 and 2 Technical Specifications to support use of neutron absorbing inserts in spent fuel pool.

REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATIONS, UNITS 1 AND 2 REGARDING USE OF NEUTRON ABSORBING INSERTS IN SPENT FUEL STORAGE RACKS DOCKET NOS.: 50-254 AND 50-265 TAC NOS.: MF2489 AND MF2490 RAI 1-17 requested justification for the use of a code that had not yet been submitted for review by the NRC for reload analysis methods with the SVEA-96 Optima2 fuel assembly, in order to obtain isotopic data for use in the criticality analyses. No specific information was provided to allow NRC staff to determine if CASMO-4 isotopic composition predictions are acceptable for SVEA-96 type lattices. NRC staff agrees that for the most part, the SVEA-96 lattice is comparable to other fuel lattices already approved for use with CASMO-4 in the U.S. However, the water wings are a relatively unique feature, and the SVEA-96 calculation results show a much larger bias between CASMO-4 and MCNP than the GE14 calculations. Appendix C shows the difference between CASMO-4 and MCNP5 calculations to be less than two sigma for the GE14 fuel design, while comparison of Tables 7.1(a) and 7.2(a) shows that the difference can approach the 20-sigma threshold for the SVEA-96 fuel design. This suggests that the heterogeneities of the SVEA-96 Optima2 fuel lattice may require special modeling considerations or treatment that is substantially different from that of other fuel assembly designs. Please provide evidence that the CASMO-4 code would be expected to compute isotopic quantities comparable to codes previously approved by the NRC for use in reload analysis of SVEA-96 Optima2 fuel.

Following our clarification call on 7/17/14, we agreed that your final response would be due by August 12, 2014.

Thanks Brenda L. Mozafari 1

Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission Dresden 2/3 and QuadCities 1/2 301-415-2020 email: brenda.mozafari@nrc.gov 2

Hearing Identifier: NRR_PMDA Email Number: 1444 Mail Envelope Properties (Brenda.Mozafari@nrc.gov20140722114800)

Subject:

Final RAI for QUAD CITIES REGARDING USE OF NEUTRON ABSORBING INSERTS (TAC NOS.: MF2489 AND MF2490)

Sent Date: 7/22/2014 11:48:16 AM Received Date: 7/22/2014 11:48:00 AM From: Mozafari, Brenda Created By: Brenda.Mozafari@nrc.gov Recipients:

"Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com)" <ken.nicely@exeloncorp.com>

Tracking Status: None Post Office:

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