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=Text=
=Text=
{{#Wiki_filter:ACCELERATED DI RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)ACCESSION NBR:9009200107 DOC.DATE: 90/09/13 NOTARIZED:
{{#Wiki_filter:ACCELERATED DI                   RIBUTION DEMONST                 TION SYSTEM REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
NO FACIL:50-335 St.Lucie Plant, Unit 1, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION SAGER,D.A.
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.
Florida Power&Light Co.RECXP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)
RECXP.NAME           RECXPIENT AFFILIATION Document     Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards evaluation of potential safety i pact of failed control element assemblies on limiting transients.
Forwards evaluation of potential safety control element assemblies          on i pact of failed limiting transients.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR 3 ENCL (SIZE: TITLE: OR Submittal:
DISTRIBUTION CODE: AOOID TITLE:  OR COPIES RECEIVED:LTR Submittal: General Distribution                3 ENCL   ( SIZE:
General Distribution NOTES: DOCKET 05000335 RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACRS NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LF~E~~~~~a.-
NOTES:
EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 0 1 1 1 1 RECXPIENT ID CODE/NAME PD2-2 PD NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
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
PLEASE HELP VS TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 21  
        ~E~~~~~a.-                     1     1     RES/DSIR/EIB           1   1 EXTERNAL: NRC PDR                        1     1     NSIC                  1   1 NOTE TO ALL "RIDS" RECIPIENTS:
'C gpss P.O.Box14000, Juno Beach, FL 33408-0420 SEP I 3 l990 L-90-332 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:
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!
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.
TOTAL NUMBER OF COPIES REQUIRED: LTTR               23   ENCL   21
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 Vice P St.L i er ident Plant DAS JMP.kw Attachment.
'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:
CC Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant y DAS/PSL N254 0,'i~an FPL Group company 9009200i07 9009i3 PDR ADOCK 05000335 P PDC l'.~pyul 0 Jl 1}}
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 '.~
pyul
 
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Latest revision as of 22:49, 29 October 2019

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)
v • d • e


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 '.~

pyul

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