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| issue date = 12/18/1992
| issue date = 12/18/1992
| title = Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors, Annual Rept for CY92
| title = Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors, Annual Rept for CY92
| author name = PLUNKETT T F
| author name = Plunkett T
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ACCEI ERAT DOCUMENT DISTR UTION SYSTEM REGULATO INFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NBR:9212280161 DOC.DATE: 92/12/18 NOTARIZED:
{{#Wiki_filter:ACCEI ERAT                   DOCUMENT DISTR UTION SYSTEM REGULATO       INFORMATION DISTRIBUTION           STEM (RIDS)
NO FACIE:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION PLUNKETT,T.F.
ACCESSION NBR:9212280161             DOC.DATE:     92/12/18   NOTARIZED: NO           DOCKET FACIE:50-250 Turkey Point Plant, Unit 3,               Florida   Power and Light   C 05000250 50-251 Turkey Point Plant, Unit 4,               Florida   Power and Light   C 05000251 AUTH. NAME           AUTHOR AFFILIATION PLUNKETT,T.F.         Florida   Power & Light Co.                                             R RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document             Control Desk)
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
Criteria for              in Light    Water Nuclear Power i


==SUBJECT:==
==SUBJECT:==
"Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors," annual rept for CY92.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR i ENCL i SIZE: 5 TITLE: OR Submittal:
  "Acceptance                         ECCS Reactors," annual rept for             CY92.                                         D DISTRIBUTION CODE: AOOID TITLE:  OR COPIES RECEIVED:LTR Submittal: General Distribution i ENCL     SIZE:   5 NOTES NRR RAGHAVANP L                                                                 05000250 /
General Distribution DOCKET 05000250 05000251 R D NOTES NRR RAGHAVAN P L NRR RAGHAVAN,L 05000250/05000251 RECIPIENT ID CODE/NAME PD2-2 LA AULUCKiR INTERNAL: NRR/DET/ESGB NRR/DST/SELB 7E NRR/DST/SRXB 8E OC LFMB-~EM Ol EXTERNAL: NRC PDR NOTES: COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DOEA/OTSB11 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS3 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1.1 1 1 1 1 1 1 1 0 1 1 1 1 D D D D NOTE TO ALL"RIDS" RECIPIENTS:
NRR RAGHAVAN,L                                                                 05000251 RECIPIENT               COPIES              RECIPIENT          COPIES ID CODE/NAME           LTTR ENCL          ID  CODE/NAME      LTTR ENCL          D PD2-2 LA                     1      1      PD2-2 PD                1  . 1 AULUCKiR                     2      2                                                D INTERNAL: NRR/DET/ESGB                 1      1      NRR/DOEA/OTSB11        1    1 NRR/DST/SELB 7E             1      1      NRR/DST/SICB8H7        1     1 NRR/DST/SRXB 8E              1      1      NUDOCS-ABSTRACT         1    1 OC LFMB                      1      0      OGC/HDS3               1    0
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15  
                  - ~EM    Ol        1      1      RES/DSIR/EIB           1     1 EXTERNAL: NRC PDR                      1       1     NSIC                    1     1 NOTES:                                  1       1 D
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D D
P.O.Box 029100, Miami, FL, 33102-9100 OIS 18'(992 L-92-338 10 CFR 50.46 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 10 CFR 50.46,"Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors"-Annual Re ort Gentlemen:
NOTE TO ALL"RIDS" RECIPIENTS:
10 CFR 50.46 (a)(3)(ii) requires that licensees report to the Commission at least annually the nature of changes to, or errors discovered in, the emergency core cooling system (ECCS)evaluation models, or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis.This letter provides Florida Power and Light Company's report for Turkey Point Units 3 and 4 for calendar year 1992.Should there be any questions, please contact us.Very truly yours, Wr.7/~EH 8 T.F.Plunkett Vice President.
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
Turkey Point Nuclear Attachment TFP/RJT/rjt cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant r;~OO'zs 9212280ibi 9212i8 PDR ADQCK 05000250 R PDR an FPL Group company g0 c'-92-338 Attachment Page 1 ATTACHMENT Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 10 CFR 50.46,"Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Lar e Break IOCA LBLOCA By letter L-91-165 dated June 7, 1991'lorida Power and Light Company (FPL)reported a peak clad temperature of 2132'F in the event of a worst case large break loss of coolant accident (LBLOCA)transients This value included a calculated peak temperature of 2082'F plus 50 F increment due to containment purge coincident with a LBLOCA, increased steady-state pressurizer pressure uncertainty band, transition fuel core penalty, implementation of debris resistant fuel assemblies and stainless steel rods in fuel assemblies, and steam generator tube collapse during an earthquake.
TOTAL NUMBER OF COPIES REQUIRED: LTTR                 17   ENCL   15
Recent corrections to LBLOCA modelling have resulted in a decrease in the peak clad temperature for the worst case LBLOCA of 3'F for a total of 2129'F.This 3 F benefit is a result of a revision in the grid loss coefficients for the Optimized Fuel Assemblies (OFA).The LBLOCA analysis as de'scribed in the Updated Final Safety Analysis Report (UFSAR)was performed by Westinghouse in 1991 using the BART computer model with fuel assembly spacer grids.Small Break LOCA SBLOCA By letter L-91-165, Florida Power and Light Company reported a peak clad temperature of 1749'F in the event of a worst case small break loss of coolant accident (SBLOCA)transient.
 
This value was based upon a new Turkey Point SBLOCA analysis performed by Westinghouse in 1991 using the NOTRUMP digital computer code.Recent plant changes and corrections in SBLOCA coding have resulted in a decrease in the peak clad temperature for the worst case SBLOCA of 33'F for a total of 1716'F.This value includes a 2'F increase due to the presence of stainless steel rods in fuel assemblies, and a 35'F benefit due to a NOTRUMP Bessel function correction.
Il
C L-92-338 Attachment Page 2~Summa+The revised peak clad temperatures of 2129'F for the worst case LBLOCA and 1716'F for the worst case SBLOCA, correcting for the effects discussed herein and summarized in the enclosed Tables 1 and 2, are below the 10 CFR 50.46 acceptance limit of 2200'F.
    ~'
L-92-338 Attachment Page 3 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Evaluations s ecified in FPL letter L-91-165 2082'F Effect of Containment Purging Pressurizer Pressure Uncertainty Implementation of Debris Resistant FA Transition Core Penalty Stainless Steel Rods in Fuel Assemblies Steam Generator Tube Collapse During an Earthquake Total LBLOCA PCT specified in FPL Letter L-91-165 9 F 8oF 3 F 10 F 18oF 2 F 2132'F Evaluations since issuance of FPL letter L-91-165 Increase Core Pressure Drop Total Estimated LBLOCA PCT 3 F 2129'F L-92-338 Attachment Page 4 TABLE 2 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Evaluations since issuance of L-91-165 Stainless Steel Rods-Cycle 12 Fuel NOTRUMP Bessel Function Correction Tota1 Estimated SBLOCA PCT 2'F-35'F 1749 F 1716 F  
 
~'f}}
P.O. Box 029100, Miami, FL, 33102-9100 OIS 18             '(992 L-92-338 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn:     Document       Control Desk Washington, D.C. 20555 Re:   Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria         for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Gentlemen:
10 CFR   50.46       (a)(3)(ii) requires that licensees report to               the Commission at         least annually the nature of changes to, or errors discovered in, the emergency core cooling system (ECCS) evaluation models, or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis. This letter provides Florida Power and Light Company's report for Turkey Point Units 3 and 4 for calendar year 1992.
Should there be any questions,           please contact us.
Very   truly     yours, Wr. 7/~EH 8 T. F. Plunkett Vice President.
Turkey Point Nuclear Attachment TFP/RJT/rjt cc:   Stewart D. Ebneter, Regional Administrator, Region II,                         USNRC Senior Resident Inspector, USNRC, Turkey Point Plant r;~OO'zs 9212280ibi 9212i8 PDR     ADQCK     05000250 R                         PDR                                                           g0 an FPL Group company
 
c'-92-338 Attachment Page   1 ATTACHMENT Re:   Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Lar e   Break IOCA LBLOCA By letter L-91-165 dated June 7, 1991'lorida Power and Light Company (FPL) reported a peak clad temperature of 2132'F in the event of a worst case large break loss of coolant accident (LBLOCA) transients     This value included a calculated peak temperature of 2082'F plus 50 F increment due to containment purge coincident with a LBLOCA, increased steady-state pressurizer pressure uncertainty band, transition fuel core penalty, implementation of debris resistant fuel assemblies and stainless steel rods in fuel assemblies, and steam generator tube collapse during an earthquake.
Recent corrections to LBLOCA modelling have resulted in a decrease in the peak clad temperature for the worst case LBLOCA of 3'F for a total of 2129'F. This 3 F benefit is a result of a revision in the grid loss coefficients for the Optimized Fuel Assemblies     (OFA) .
The LBLOCA analysis as de'scribed in the Updated Final Safety Analysis Report (UFSAR) was performed by Westinghouse in 1991 using the BART computer model with fuel assembly spacer grids.
Small Break     LOCA   SBLOCA By letter   L-91-165, Florida Power and Light Company reported a peak clad temperature     of 1749'F in the event of a worst case small break loss of coolant accident (SBLOCA) transient. This value was based upon a new Turkey Point SBLOCA analysis performed by Westinghouse in 1991 using the NOTRUMP digital computer code.
Recent   plant changes and corrections in SBLOCA coding have resulted in a decrease in the peak clad temperature for the worst case SBLOCA of 33'F for a total of 1716'F. This value includes a 2'F increase due to the presence of stainless steel rods in fuel assemblies, and a 35'F benefit due to a NOTRUMP Bessel function correction.
 
C L-92-338 Attachment Page 2
~Summa+
The revised peak clad temperatures of 2129'F for the worst case LBLOCA and 1716'F for the worst case SBLOCA, correcting for the effects discussed herein and summarized in the enclosed Tables 1 and 2, are below the 10 CFR 50.46 acceptance limit of 2200'F.
 
L-92-338 Attachment Page 3 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record                                     2082'F Evaluations s ecified in FPL letter L-91-165 Effect of Containment Purging                   9 F Pressurizer Pressure Uncertainty               8oF Implementation of Debris Resistant FA           3 F Transition Core Penalty                       10 F Stainless   Steel   Rods in Fuel Assemblies           2 F Steam Generator Tube Collapse During an Earthquake                               18oF Total   LBLOCA PCT   specified in FPL Letter L-91-165                               2132'F Evaluations since issuance of     FPL letter L-91-165 Increase Core Pressure Drop                     3 F Total Estimated     LBLOCA PCT                         2129'F
 
L-92-338 Attachment Page 4 TABLE 2 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record                             1749 F Evaluations since issuance of L-91-165 Stainless Steel Rods Cycle 12 Fuel       2'F NOTRUMP Bessel Function Correction       -35'F Tota1 Estimated SBLOCA PCT                     1716 F
 
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Latest revision as of 21:41, 3 February 2020

Acceptance Criteria for ECCS in Light Water Nuclear Power Reactors, Annual Rept for CY92
ML17349A560
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/18/1992
From: Plunkett T
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-338, NUDOCS 9212280161
Download: ML17349A560 (8)
v • d • e


Text

ACCEI ERAT DOCUMENT DISTR UTION SYSTEM REGULATO INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9212280161 DOC.DATE: 92/12/18 NOTARIZED: NO DOCKET FACIE:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power & Light Co. R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

Criteria for in Light Water Nuclear Power i

SUBJECT:

"Acceptance ECCS Reactors," annual rept for CY92. D DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution i ENCL SIZE: 5 NOTES NRR RAGHAVANP L 05000250 /

NRR RAGHAVAN,L 05000251 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 1 PD2-2 PD 1 . 1 AULUCKiR 2 2 D INTERNAL: NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC LFMB 1 0 OGC/HDS3 1 0

- ~EM Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTES: 1 1 D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 15

Il

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P.O. Box 029100, Miami, FL, 33102-9100 OIS 18 '(992 L-92-338 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Gentlemen:

10 CFR 50.46 (a)(3)(ii) requires that licensees report to the Commission at least annually the nature of changes to, or errors discovered in, the emergency core cooling system (ECCS) evaluation models, or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis. This letter provides Florida Power and Light Company's report for Turkey Point Units 3 and 4 for calendar year 1992.

Should there be any questions, please contact us.

Very truly yours, Wr. 7/~EH 8 T. F. Plunkett Vice President.

Turkey Point Nuclear Attachment TFP/RJT/rjt cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant r;~OO'zs 9212280ibi 9212i8 PDR ADQCK 05000250 R PDR g0 an FPL Group company

c'-92-338 Attachment Page 1 ATTACHMENT Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems In Light Water Nuclear Power Reactors" Annual Re ort Lar e Break IOCA LBLOCA By letter L-91-165 dated June 7, 1991'lorida Power and Light Company (FPL) reported a peak clad temperature of 2132'F in the event of a worst case large break loss of coolant accident (LBLOCA) transients This value included a calculated peak temperature of 2082'F plus 50 F increment due to containment purge coincident with a LBLOCA, increased steady-state pressurizer pressure uncertainty band, transition fuel core penalty, implementation of debris resistant fuel assemblies and stainless steel rods in fuel assemblies, and steam generator tube collapse during an earthquake.

Recent corrections to LBLOCA modelling have resulted in a decrease in the peak clad temperature for the worst case LBLOCA of 3'F for a total of 2129'F. This 3 F benefit is a result of a revision in the grid loss coefficients for the Optimized Fuel Assemblies (OFA) .

The LBLOCA analysis as de'scribed in the Updated Final Safety Analysis Report (UFSAR) was performed by Westinghouse in 1991 using the BART computer model with fuel assembly spacer grids.

Small Break LOCA SBLOCA By letter L-91-165, Florida Power and Light Company reported a peak clad temperature of 1749'F in the event of a worst case small break loss of coolant accident (SBLOCA) transient. This value was based upon a new Turkey Point SBLOCA analysis performed by Westinghouse in 1991 using the NOTRUMP digital computer code.

Recent plant changes and corrections in SBLOCA coding have resulted in a decrease in the peak clad temperature for the worst case SBLOCA of 33'F for a total of 1716'F. This value includes a 2'F increase due to the presence of stainless steel rods in fuel assemblies, and a 35'F benefit due to a NOTRUMP Bessel function correction.

C L-92-338 Attachment Page 2

~Summa+

The revised peak clad temperatures of 2129'F for the worst case LBLOCA and 1716'F for the worst case SBLOCA, correcting for the effects discussed herein and summarized in the enclosed Tables 1 and 2, are below the 10 CFR 50.46 acceptance limit of 2200'F.

L-92-338 Attachment Page 3 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record 2082'F Evaluations s ecified in FPL letter L-91-165 Effect of Containment Purging 9 F Pressurizer Pressure Uncertainty 8oF Implementation of Debris Resistant FA 3 F Transition Core Penalty 10 F Stainless Steel Rods in Fuel Assemblies 2 F Steam Generator Tube Collapse During an Earthquake 18oF Total LBLOCA PCT specified in FPL Letter L-91-165 2132'F Evaluations since issuance of FPL letter L-91-165 Increase Core Pressure Drop 3 F Total Estimated LBLOCA PCT 2129'F

L-92-338 Attachment Page 4 TABLE 2 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record 1749 F Evaluations since issuance of L-91-165 Stainless Steel Rods Cycle 12 Fuel 2'F NOTRUMP Bessel Function Correction -35'F Tota1 Estimated SBLOCA PCT 1716 F

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