ML17354A474

Requests That Addl Ref Be Added to Turkey Point,Units 3 & 4 TS Section 6.9.1.7, Colr.

ML17354A474
Person / Time
Site:	Turkey Point
Issue date:	04/24/1997
From:	Hovey R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17354A476	List: ML17354A474 ML17354A477
References
L-97-108, NUDOCS 9705010342
Download: ML17354A474 (7)

Text

CATEGORY 1

",l REGULATO, INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION,NBR:9705010342E DOC.DATE: 97/04/24 NOTARIZED: YES DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 5Q-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH, NAME AUTHOR AFFILIATION HOVEY,R.J. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Requests addi ref be added to Units 3 & 4 TS Section 6.9.1.7 re COLR.

DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL t SIZE: 3 +.

TITLE: OR Submittal: General Distribution NOTES:

E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 LA

• 1 1 PD2-3 PD 1 1 CROTEAU,R 1 1 0 INTERNAL: 1 1 NRR/DE/ECGB/A 1 1 RR DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

F ~

h

L-97-108 10 CFR $ 50.36 PAN 10 CFR $ 50.90 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 Proposed License Amendments Large Break Loss of Coolant Accident Re-analysis On February 24, 1997, Florida Power and Light Company (FPL) submitted L-97-037, "Large Break Loss of Coolant Accident Re-analysis." I 97-037 requested that Appendix A of Facility Operating Licenses DPR-31 and DPR-41 be amended to modify Turkey Point Units 3 and 4 Technical Specifications Section 6.9.1.7, Core Operating Limits Report (COLR). This requested change will add Best Estimate Large Break Loss of Coolant Accident Analysis (BELOCA) to the COLR.

During the NRC review of WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V, revisions were made to the large break LOCA methodology. A number of plant specific analyses were performed prior to the final approval of the BELOCA methodology.

Turkey Point Units 3 and 4 were among the affected plants. In order to document the re-analyses performed as a result of these revisions, FPL requests an additional reference be added to the Turkey Point Units 3 and 4 Technical Specifications Section 6.9.1.7, Core Operating Limits Report. describes the basis for the reference addition and Attachment 2 provides the proposed Technical Specification page.

No changes have been made to the analyses or references described in L-97-037. Therefore, the conclusion of the No Significant Hazards Evaluation remains valid.

Should there be any questions on this request, please contact us.

Very truly yours, R. J. Hovey

~ ~

Vice Preside t Turkey Point Plant 97OSOXOim 970oee t PDR ADQCK 05000250 p PDR Attachments 'llllllllllllllllllllllllllllIIII.IIIIIII, CC: L. A. Reyes, Regional Administrator, Region II, USNRC T. P. Johnson, Senior Resident Inspector, USNRC, Turkey Point Plant W. A. Passetti, Florida Department of Health and Rehabilitative Services an FPL Group company

1 I0 I)

A

L-97-108 STATE OF FLORIDA )

) ss.

COUNTY OF DADE )

RJ~gzg. being first duly sworn, deposes and says:

That he is , of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.

R.J.Hov y Subscribed and sworn to before me this day of , 1997.

ggx% hj~, CHERYL A. STEVEMSog f

MY COMMISOM CCEQ017 Name of Notary Public (Type or Print) ~"

EXP!RES: tune19,2XO

"@iieet.

NOTARY PUBLIC, in and for the County of Dade, State of Florida My Commission expires Commission No.

R.J. Hovey is personally known to me.

I j!'~ ~

/

II t

L-97-108 Page 1 of 1 On February 24, 1997, Florida Power and Light Company (FPL) submitted L-97-037, "Large Break Loss of Coolant Accident Re-analysis." L-97-037 requested that Appendix A of Facility Operating Licenses DPR-31 and DPR-41 be amended to modify Turkey Point Units 3 and 4 Technical Specifications Section 6.9.1.7, Core Operating Limits Report. This requested change willadd Best Estimate Large Break Loss of Coolant Accident Analysis (BELOCA) to the list of approved analytical methods used in determining the Heat Flux Hot Channel Factor, F~ (Z);

Nuclear Enthalpy Rise Hot Channel Factor, Fz><', and the Normalized F< (Z) as a function of core height, K(Z) curve.

Die~ion During the NRC review of the generic WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V, revisions were made to the large break LOCA methodology. A number of plant specific analyses were performed prior to the final approval of the BELOCA methodology. Turkey Point Units 3 and 4 were among those plants affected by the methodology revisions.

An action plan to perform re-analysis of the affected plants was detailed in a letter dated June 13, 1996, from N. J. Liparulo (9?) to Frank R. Orr (USNRC), "Re-Analysis Work Plans Using Final Best Estimate Methodology."

I 97-037 referenced WCAP-14159, Revision 0, "Best-Estimate Analysis of the Large Break Loss of Coolant Accident for Turkey Point Units 3 8c 4 Nuclear Plant for Power Uprate," dated October 1996. Although not specifically referenced in WCAP-14159, Revision 0, the required re-analysis as described in the June 13, 1996 Re-Analysis Work Plans letter was incorporated.

Liparulo (E) to Frank R. Orr (USNRC), "Re-Analysis Work Plans Using Final Best

¹ The Technical Specification Administrative Controls Section 6.9.1,7, Core Operating Limits Report, willbe modified to include reference to the letter dated June 13, 1996, from J.

Estimate Methodology."