ML17354A420

Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR

ML17354A420
Person / Time
Site:	Turkey Point
Issue date:	02/24/1997
From:	Hovey R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17354A421	List: ML17354A420 ML17354A422
References
L-97-037, L-97-37, NUDOCS 9703040209
Download: ML17354A420 (13)

Text

CATEGORY 1 REGULATC INFORMATION DISTRIBUTION STEM (RIDE)

'CCESSION NBR:9703040209 DOC.DATE: 97/02/24 NOTARIZED: YES DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250

.k 50-25l Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.'NAME AUTHOR AFFILIATION HOVEY,R.J. Florida Power 6 Light Co.

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

SUBJECT:

Application for amends to Licenses DPR-31 a DPR-4l,modifying Tech Specs 6.9.1.7, "COLR" & adding best estimate large break loss of coolant accident analysis to COLR.

DISTRIBUTION CODE: AOOZD TITLE:.OR Submittal: General COPIES RECEIVED:LTR Distribution L ENCL 3 SIZE:

NOTES:'ECIPIENT 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 INTERNA FZI E CENTER 1 1 1 NRR/DE/ECGB/A 1 1 NRR/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 l 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

FEB 84 1997 L-97-037

%PL 10 CFR $ 50.36 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 In accordance with Title 10 Code of Federal Regulations $ 50.90 (10 CFR $ 50.90), Florida Power and Light Company (FPL) requests that Appendix A of Facility Operating Licenses DPR-31 and DPR-41 be amended to modify Turkey Point Units 3 and 4 Technical Specifications 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.

A description of the amendments request is provided in Attachment 1. FPL has determined the proposed license amendments do not involve a significant hazard pursuant to 10 CFR $ 50.92. The no significant hazards determination is provided in Attachment 2. The revised Technical Specifications are provided in .

In accordance with 10 CFR 550.91 (b) (1), a copy of these proposed license amendments are being forwarded to the State Designee for the State of Florida.

The proposed amendments have been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.'hould there be any questions on this request, please contact us.

Very truly yours,

'.

J. Hovey Vice President Turkey Point Plant JAH 04OOOS Attachments , g0 cc: L. A. Reyes, Regional Administrator, Region II, USNRC T. P. Johnson, Senior Resident Inspector, USNRC, Turkey Point W. A. Passetti, Florida Department of Health and Rehabilitative Services 9703040209 970224 PDR ADOCK 05000250 p PDR an FPL Group company i)II@161)llllllllltlllllljlllllllll

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I 97-037 STATE OF FLORIDA )

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COUNTY OF DADE )

RJ~gz~ 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. Hove Subscribed and sworn to before me this

~/ day of FWA~ , 1997.

,~~@"0"~., OLGA HANEK use MY C0MMISSIM6 CC662742 EXPIRES: Jimiti 18, 2000

%z;ti~" Boehxl lhu IIahuy Piste Unstsnssttee Name of Notary Public (Type or Print)

NOTARY PUBLIC, in and for the County of Dade, State of Florida N.~

My Commission expires tu<~ < < >>rrrr R. J. Hovey is personally known to me.

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Attachment 1 I 97-037 Page 1 of 4 Florida Power & Light Company (FPL) proposes to amend the Turkey Point Units 3 and 4 Technical Specifications (TS) 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 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.

In 1988, as a result of improved understanding of Loss of Coolant Accident (LOCA) thermal-hydraulic phenomena, the NRC amended the requirements of 10 CFR $ 50.46 and Appendix K "ECCS Evaluation Models." A realistic evaluation model may be used to analyze the performance of the Emergency Core Cooling System (ECCS) during a hypothetical LOCA.

Under the amended rules, best estimate thermal-hydraulic models may be used in place of Appendix K models. The rule change requires an assessment of the uncertainty associated with the best estimate calculations and that this analysis uncertainty be included when comparing the results of the calculations to the prescribed acceptance limits. Guidance for the use of best estimate codes is provided in Regulatory Guide 1.157.

A plant specific analysis, WCAP-14159 Revision 0, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for Turkey Point Units 3 & 4 Nuclear Plant for Power Uprate," dated October 1996, has been performed using the Westinghouse approved methodology. The approved methodology is documented in the following; (1) WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V, (2) Letter from N.J. Liparulo (E) to R.C. Jones, Jr. (USNRC), "Revisions to Westinghouse Best-Estimate Uncertainty Methodology," NTD-NRC-95-4575, dated October 13, 1995, and (3) USNRC Safety Evaluation Report, Letter from R. C. Jones (USNRC) to N. J. Liparulo QQ, "Acceptance for Referencing of the Topical Report WCAP-12945(P) 'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,' dated June 28, 1996. Allplant specific parameters used in the analysis are bounded by the models and correlations contained in the generic methodology. Therefore, the Turkey Point Units 3 and 4 specific BELOCA analyses conform to 10 CFR 50.46 and meets the intent of Regulatory Guide 1.157.

0; Attachment 1 L-97-037 Page 2 of 4 The conclusions of the analyses demonstrate there is a high level of probability that:

1) The calculated maximum fuel element cladding temperature willnot exceed 2200'F.

2) The calculated total oxidation of the cladding willnowhere exceed 0.17 times the total cladding thickness before oxidation.

3) The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam will not exceed 0.01 times the hypothetical amount that would be generated ifall of the metal in the cladding tubes surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react.

4) The calculated changes in core geometry are such that the core remains amenable to cooling.

5), After successful initial operation of the ECCS, the calculated core temperature will be maintained at an acceptable low value and decay heat willbe removed for the extended period of time required by the long-lived radioactivity remaining in the core.

Table 1 summarizes the results of the BELOCA analyses for Turkey Point Units 3 & 4. Table 2 shows the plant specific operating ranges for the main plant parameters used in the BELOCA analysis for Turkey Point Units 3 & 4. The range of variation of the operating parameters has been accounted for in the uncertainty evaluation.

'Attachment 1 L-97-037 Page 3 of 4 Table 1 TURKEY POINT UNITS 3 & 4 BEST ESTIMATE LARGE BREAK LOCA RESULTS Criteria 95th Percentile PCT ('F)

• 2067 s2200 Maximum Cladding Oxidation (%) <17 s17 Maximum Hydrogen Generation (%)

Coolable Geometry Core Remains Core Remains Coolable Coolable Long Term Cooling Core Remains Core Remains Cool In Long Cool In Long Term Te rill Includes a+27 'F PCI'penalty for a potentially lower containment backpressure due to Qow of air and steam out of the containment prior to the closure of the purge isolation valves (2067=2040+27).

Attachment 1 L-97-037 Page 4of 4 Table 2 TURKEY POINT UNITS 3 & 4 BELOCA ANALYSIS MAJOR PLANT PARAMETER ASSUMPTIONS Parameter Allowable Ran e Fuel T e 15X15 OFA DRFA Steam Generator Tube Plu in g20 Core Power MWt z 2346 Fg (Z) Z 2.50 FiLH z 1.73 Peak Assembl Burnu MWD/MTU z 75,000 MTC z0 atHFP Tang ( F) 562 7 < Ta<g < 585 7 Pressurizer Pressure (psia) 2180 Z PRCS Z 2320 Loo Flow( m > 85,000 Accumulator Tem erature z 130 Pressure (psia)'ccumulator 590ZP~z715 Accumulator Volume (gallons) 6007 z V~ z 7338 Minimum ECC Boron ( m > 1950 SITem erature g 105

'I Delay (seconds) ~ 23 (with offsite power) g35 withoutoffsite ower Offsite Power ON or OFF

'Attachment 2 L-97-037 Page 1 of 2 The Technical Specification Administrative Controls Section 6.9.1.7, Core Operating Limits Report willbe modified to reflect the use of Westinghouse BELOCA methodology for large break LOCA analysis.

The following references will be added to Section 6.9.1.7 of Turkey Point Units 3 and 4 Technical Specifications.

WCAP-12945-P, "Westinghouse Code Qualification Document For Best Estimate LOCA Analysis," Volumes I-V.

USNRC Safety Evaluation Report, Letter from R. C. Jones (USNRC) to N. J. Liparulo QQ, "Acceptance for Referencing of the Topical Report WCAP-12945(P) 'Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Analysis,' June 28, 1996.

Consistent with the requirements of 10 CFR $ 50.92, the enclosed application involves no significant hazards as demonstrated by the answers to the following questions.

Qzstiz~ Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

The plant conditions assumed in the analysis are bounded by the design conditions for all equipment in the plant. Therefore, there willbe no increase in the probability of a Loss of Coolant Accident (LOCA). The consequences of a LOCA are not being increased. That is, it is shown that the emergency core cooling system is designed so that its calculated cooling performance conforms to the criteria contained in 10 CFR $ 50.46 paragraph (b). No other accident is potentially affected by this change. Therefore, neither the probability nor the consequences of an accident previously evaluated is increased due to the proposed change.

QzsQg~ Does the proposed license amendment create the possibility of a new or different kind of accident from. any accident previously evaluated?

No new modes of plant operation are being introduced. The parameters assumed in the analysis are within the design limits of existing plant equipment. Allplant systems willperform as designed in response to a potential accident. Therefore, the proposed license amendment willnot create the possibility of a new or different kind of accident from any accident previously evaluated.

L-97-037 Page2of2 Qzgjg~ Does the proposed amendment involve a significant reduction in the margin of safety?

The analysis in support of the proposed license amendment realistically models the expected response of the Turkey Point Units 3 & 4 nuclear core during a postulated LOCA. Uncertainties have been accounted for as required by 10 CFR 550.46. A sufficient number of loss of coolant accidents with different break sizes, different break locations and other variations in properties have been calculated to provide assurance that the most severe postulated loss of coolant accidents were analyzed. It has been shown by the analysis that there is a high level of probability the criteria contained in 10 CFR 550.46 paragraph (b) would not be exceeded. Therefore, the proposed amendment does not involve a significant reduction in the margin of safety.

Based on the above, it can be concluded that the incorporation of the proposed changes; a) will not involve a significant increase in the probability or consequences of an accident previously evaluated; b) willnot create the possibility of a new or different kind of accident from any accident previously'evaluated; and c) will not involve a significant reduction in a margin of safety.