ML18038B903
| ML18038B903 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/24/1997 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M98059, NUDOCS 9707020216 | |
| Download: ML18038B903 (6) | |
Text
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REGULAT INFORMATION DISTRIBUTIONOi'STEM (.RIDE'J ACCESSION NBR:9707020216 DOC.DATE: 97/06j24 NOTARIZED:
NO DOCKET FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to 970623 verbal request for addi info re core spray weld flaw evaluation. Clarification of methodology used to estimate increase in limiting peak clad temp for LOCA analysis, provided.
DISTRIBUTION CODE:
D030D COPIES RECEIVED:LTR l
ENCL Q SIZE!~
TITLE: TVA Facilities Routine Correspondence NOTES:
RECIPIENT ID CODE/NAM8 PD2-3 WILLIAMS,J.
INTERNAL: ACRS OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD2-3-PD SEB E
NRC PDR COPIES LTTR ENCL NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 9
ENCL
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 June 24, 1997 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Zn the Matter of Tennessee Valley Authority Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - RESPONSE TO VERBAL REQUEST FOR ADDITIONAL INFORMATION REGARDING CORE SPRAY WELD FLAW EVALUATION (TAC NO M98059)
This letter responds to the NRC's June 23, 1997, verbal request for additional information regarding core spray weld flaw evaluation.
NRC requested TVA clarify the methodology used in TVA's June 10, 1997 letter to estimate the increase in the limiting peak clad temperature (PCT) for a Loss of Coolant Accident (LOCA) analysis that assumed a loop of core spray piping supplied no flow to the vessel.
The PCT calculated and referenced in the June 10, 1997 submittal is the "licensing basis" PCT, which is referred to as PCT:APP.K in the NRC's June 1,
1984 Safety Evaluation Report regarding the acceptance for referencing of Licensing Topical Report NEDE-23785, GESTR-LOCA and SAFER Models for the Evaluation of the Loss of Coolant Accident.
The applicable acceptance criterion for the licensing basis PCT is 2200 F.
This is the PCT value most representative of the effect that a loss of a core spray loop would have on fuel cladding integrity from a regulatory standpoint.
97070202i6 970624 PDR ADOCK 05000296, P
PDR 620030
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U.S. Nuclear Regulatory Commission Page 2
June 24, 1997 There are no commitments in this letter. If you have any questions, please contact me at (205) 729-2636.
S'erely, T. E. Ab Manager of Li sang and Indus y Affair CC Mr. Mark Les r, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611 Mr. J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
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