ML17223A940

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Forwards Evaluation of Potential Safety Impact of Failed Control Element Assemblies on Limiting Transients for Facility
ML17223A940
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 09/13/1990
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-332, NUDOCS 9009200107
Download: ML17223A940 (3)


Text

ACCELERATED DI RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)

ACCESSION NBR:9009200107 DOC.DATE: 90/09/13 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A. Florida Power & Light Co.

RECXP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards evaluation of potential safety control element assemblies on i pact of failed limiting transients.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution 3 ENCL ( SIZE:

NOTES:

RECIPIENT COPIES RECXPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 2 2 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC/LF 1 0 OGC/HDS2 1 0

~E~~~~~a.- 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP VS TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 21

'C P.O. Box14000, Juno Beach, FL 33408-0420 gpss SEP I 3 l990 L-90-332 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Re: St. Lucie Unit 1 Docket 50-335 Generic Implications and Resolution of CEA Failure at Maine Yankee By letter dated July 6, 1990, the Nuclear Regulatory Commission (NRC)

'taff requested additional information from Florida Power and Light (FPL) regarding the Combustion Engineering Regulatory Response Group (CERRG)

Action Program for addressing the issue of irradiation assisted stress corrosion cracking (IASCC) in Control Element Assemblies (CEAs).

Specifically, in question six of the referenced letter, the staff requested that FPL provide a comprehensive Safety Evaluation of the multiple rod failure event that could be postulated assuming that, old CEAs are subject to the Maine Yankee failure mechanism.

By letter L-90-272, dated July 17, 1990, FPL responded to the staff's questions, but stated that further clarification of the scope of the proposed CEA failure scenario would be necessary for the preparation of the requested Safety Evaluation. This clarification was subsequently provided by the staff during a conference call held on August 20, 1990.

Based upon the clarifying information provided by the staff in the referenced conference call, FPL has prepared the attached evaluation of the potential impact of failed CEAs on limiting transients for St. Lucie Unit 1.

Should you have any questions, please contact us.

Very truly yours, QA8 D. A. S er Vice P ident St. L i Plant DAS JMP.kw Attachment.

CC Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant y

DAS/PSL N254 9009200i07 9009i3 0,'i ~ an FPL Group company PDR P

ADOCK 05000335 PDC l '.~

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