ML18261A277

09/18/2018, Conversation Record with Department of Energy Idaho Operations Office Discuss Technical Request for Additional Information (RAI) on Three Mile Island, Unit 2 (TMI 2)ISFSI Renewal Application, Conversation Held on August 24, 2018

ML18261A277
Person / Time
Site:	07200020
Issue date:	09/18/2018
From:	Banovac K L Renewals and Materials Branch
To:	US Dept of Energy, Idaho Operations Office
Banovac K L
References
000993/L-2017-LNE-0007, 001028/L-2017-RNW-0019, CAC 000993, CAC 001028, EPID L-2017-LNE-0007, EPID L-2017-RNW-0019
Download: ML18261A277 (2)

Text

NRC FORM 699 ......... ,,,.~ (03-2013) r~*i U.S. NUCLEAR REGULATORY COMMISSION DATE OF SIGNATURE

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. .. ,, ,-CONVERSATION RECORD 09/18/2018 ***** NAME OF PERSON(S)

CONTACTED OR IN CONTACT WITH YOU Department of Energy Idaho Operations Office E-MAIL ADDRESS ORGANIZATION Department of Energy Idaho Operations Office LICENSE NUMBER(S)

SNM-2508 SUBJECT DOCKET NUMBER(S) 72-20 CONTROL NUMBER(S)

DATE OF CONTACT 08/24/2018 TELEPHONE NUMBER TYPE OF CONVERSATION DE-MAIL [ZJ TELEPHONE D INCOMING [ZJ OUTGOING OOI028/L-2017-RNW-0019 and 000993/L-2017-LNE-0007 Discuss technical request for additional information (RAI) on Three Mile Island , Unit 2 (TM] 2) Independent Spent Fuel Storage Installation (ISFSI) renewal application

SUMMARY

Department of Energy Idaho Operations Office (DOE-ID) attendees:

Scott Ferrara, Steven Wahnschaffe, Chris Backus , Brian Gutherman NRC attendees:

Kristina Banovac , Ricardo Torres , Mike Call A teleconference was held between DOE-ID and NRC representatives to discuss the January 29, 2018 , technical RA ls on the TMJ-2 ISFSI renewal application (ML 18030A 172). DOE requested the teleconference to provide its planned approach to respond to several RAis involving lightweight concrete (Licon) and discuss whether this approach was consistent with NRC's storage renewal guidance.

DOE-ID noted that it scoped the Licon material into the license renewal, as the Licon was included in the shielding , criticality , and thermal safety analyses for the TMJ-2 ISFSI. As DOE ID was working on the RAJ responses , it found limited information on aging mechanisms and aging effects on Licon material.

Continue on Page 2 ACTION REQUIRED (IF ANY) DOE-ID plans to respond to the RAls by September 30 , 2018. Continue on Page 3 NAME OF PERSON DOCUMENTING CONVERSATION Kristina Banovac S I GNAT URE NRC FORM 699 (03-2 013) Page 1 of 2 NRC FORM 699 (03-2013)

SUMMARY

(Continued from page 1) U.S. NUCLEAR REGULATORY COMMISSION CONVERSATION RECORD (continued)

Because of the limited information and data , DOE-ID plans to take a conservative approach by assuming the worst-case Licon degradation for the various safety analyses and analyzing the impacts of this Licon degradation on the safety analyses and margins. For example, if the worst-case assumption for the shielding analysis is the complete loss of Licon, DOE would analyze this to determine the changes in dose with the complete loss of Licon. For the criticality analysis , DOE would analyze replacement of the Licon with water or a void and also reconfiguration of the fuel debris into the most reactive geometry to determine the changes in reactivity. DOE-ID clarified that it is not revising or changing the design-basis safety analyses for the TMI 2 ISFSI. Rather , the new analyses regarding the worst-case Licon degradation would be used to support the aging management review in the license renewal application and to support the conclusion that no aging management program (AMP) or aging management activities are needed for the Licon in the requested period of extended operation. The NRC staff noted that analyses may be used in license renewal applications and the aging management review to justify the exclusion of an aging mechanism or effect or a s ubcomponent from the scope of an AMP (i.e., not requiring any aging management activities).

This is discussed in Section 3.5 ofNUREG-1927, Rev. I (ML16l79AI48).

If there is limited information or data on aging mechanisms

/effects , analyses can be used to support the conclusion that no aging management activities are needed. The NRC staff also provided additional clarification on RAI 2-4 , which was discussed at the June 7, 2018, public meeting. The staff noted that DOE's RAJ response regarding incorporation by reference of the aging management information from the CoC No. 1004 renewal (regarding the OS-197 transfer cask) should also include any revisions to the proposed UFSAR supplement, as appropriate. The staff also noted that the incorporation by reference of the OS 197 transfer cask AMP should be clear as to responsibility for inspections or other aging management activities when the transfer cask is not in DOE's possession , for clear AMP implementation in the future. NRC FORM 699 (03-2013)

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