3F1197-51, Provides Addl Info Requested by NRC During 971119 Telcon Re LAR 218 on Rev of Makeup Sys Letdown Line Failure Accident Analysis

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Provides Addl Info Requested by NRC During 971119 Telcon Re LAR 218 on Rev of Makeup Sys Letdown Line Failure Accident Analysis
ML20199L079
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/25/1997
From: Rencheck M
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F1197-51, TAC-M99571, NUDOCS 9712010273
Download: ML20199L079 (2)


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lorida 19E3r c ==l November 25,1997 3F1197-51 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

AdditionalInfoirnation Regarding the use of RELAP5 for LAR #218, Revision of the Makeuo System Letdown Line Failure Accident Analysis (TAC No. M99571)

References:

1. FPC to NRC letter dated September 9,1997," License Amendment Request 218, Revision of the Makeup System Letdown Line Failure Accident Analysis"

[3F0997-14)

2. NRC to Framatome Techno;ogies incorporated (FTI) letter dated February 18, 1997, " Acceptance for Referencing of Topical Report BAW-10192-P, 'BWNT Loss-of-Coolant Accident Evaluation Model for Once Through Steam Generator Plants' "(TAC No. M89400)

Dear Sir:

Florida Power Corporation (FPC) hereby provides additicnalinformation requested by the NRC during a telephone call between FPC and NRC on November 19,1997, regarding License Amendment Request (LAR) 218 (Reference 1). This additionalinformation provides details on the use of RELAPS in the analysis to support the LAR.

As stated in Reference 1, RELAPS was used to support the Makeup System Letdown Line Failure Accident Analysis because it allowed for more detailed modeling of the loss of coolant accident (LOCA) phenomena while still producing a conservative assessment of the reactor coolant system (RCS) pressure response. The RCS pressure predicted using RELAP5 resulted in a conservatively large inventory loss through the broken letdown line with corresponding offsite dose consequences.

The RELAP5 analyses were performed by Framatome Technologies incorporated (FTI) with the I

version of the emergency core cooling system (ECCS) evaluation model (EM) as approved in i topical report BAW-10192-P. In Reference 2, the NRC documented its review of the topicai report along with the FTl responses to requests for additionalinformation. g,g There are no modeling limitations for RELAPS in this application. The conditions and restrictions mnacified in Reference 2." relate to the application of RELAPS to ECCS analyses and not to 9712010273 971125 PDR ADOCK 05000302t l

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gencial thermal-hydraulic calculations as used in the letdswn line break analysis. Nonetheless, the RELAPS code */ersion, the physical arrangement of control volumes, and time steps that were used in the letdown line break analysis are the srne that would be applied for a LOCA EM.

Only the boundary conditions specific to the event being analyzed were different.

If you have any questions regarding this submittal, please contact Mr David Kunsemiller, Manager, Nuclear Licensing at (352) 563-4566.

Sincerely, M.W. Rencheck Director Nuclear Engineering and Projects 1

MWR/dah cc: Regional Administrator, Region ll NRR Project Manager Senior ResHent inspector 1

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