L-76-190, Proposed Amendment to License No. DPR-067. Provides Additional Information to Supplement Letters of 04/27/1976 & 04/30/1976. Appendix a Contains Additional ECCS Information & Appendix B Contains Calorimetric Information

Proposed Amendment to License No. DPR-067. Provides Additional Information to Supplement Letters of 04/27/1976 & 04/30/1976. Appendix a Contains Additional ECCS Information & Appendix B Contains Calorimetric Information

ML18096B517
Person / Time
Site:	Saint Lucie
Issue date:	05/14/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-76-190
Download: ML18096B517 (14)

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0 50-335 FILE NVMOEA DATE OF OOCVMENT FLORIDA POWER 6 LIGHT COMPANY 5/14/76 MR. VOCTOR STELLO MIAMI>> FLORIDA OATC RECEIVED MR, ROBERT ED UHRXG: 5/19/76

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LTR e NOTORIZED 5/ 14/7 6 RE THEIR LTRS ~ OF r 4/27/76 6 4/30/76 TRANS THE FOLLOWING: APPENDIX A '. CONTAINS ADDITIONAL ECCS,INFO 1

APPENDIX B :,CONTAINS CALORXMETRIQ INFO.

L ACKNOWLEDGED

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FLORIDA POWER 8L LIGHT COMPANY May 14, 1976 L-76-190 Director of Nuclear Reactor Regulation Attention: Mr. Victdr Stello, Director Division of'perating Reactors U. S. Nuclear Regulatory Commission yq Pf//~i Washington DC 20555

Dear Mr. Stello:

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Re: St. Lucie Plant Unit, 1 Docket No. 50-335 Proposed Amendment to Facility Operating License DPR-67 This letter provides additional information to supplement I

our letters of April 27 and April 30, 1976.

Appendix A to this letter contains additional ECCS information.

Appendix B contains calorimetric information.

The detailed methodology for determining reactor coolant flow is in the public record in the "Reactor Coolant Pump (RCP)

Flow Test Report," which is a part of the Millstone Nuclear Power Station, Unit No. 2, Docket No. 50-336. This is applicable to the St. Lucie Plant.

Very truly yours, Robert E. Uhrig Vice President REU:tg Attachments cc: Mr. Norman C. Moseley Jack R. Newman, Esquire HELPING 8UILD FLORIDA

STATE OF FLORXDA )

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COUNTY OF DADE )

ROBERT E. UHRXG, being first duly sworn, deposes and says:

That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing instrument> and, that the statements made in this said instrument are true and correct to the best of his knowledge,,information, and belief< and that. he is authorized to execute the. instrument on behalf of said Licensee<. il Robert E. U r g Subscribed and sworn to before me this l day of l976.

Notary Pubs.ic n and for the County of Dade, State of Florida ROTARY Pllgf tr ~YATF AF pOp)pp A expires """

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APPENDIX A 1

St. Lucie educed Flovr ECCH Performance esults I. Introduction and Summary The results of a St. Lucie I break spectrum analysis, using the app oved Combustion Engineering large break'evaluation model, 'are reported in Refer-6 ence 1. This analysis, which employed a system flo>> rate of 139.44 x 10 lbs/hr,

- (3) demonstrated that the LOCA Acceptance Criteria were met at a peak linear heat generation rate (PLHGR) of 15.8 hv/ft.

Subsequent to the analysis reported in Reference 1, a conservative reanalysis has been performed to determine the allowable PLHGR when the system flow rate is reduced to 134.06 x 10 lbs/hr, which is 4: less than the flow rate used in Reference 1. The allowable. PLHGR at the reduced flow was found to be 15.6 hv/ft. In -order to determine sensitivity to linear heat rate, a second reduced flow case was examined, at a PLHGR of 14.2 1'/ft.

The results for this case,'s >>ell as those discussed above, are summarized below:

Worst Breaks: LOCA Results

+stem Flow (X10 lb/hr) 139.44 134.06 134.06 PLHGR (hv/ft) 15.8 15.6 14.2 Peak Clad Temperature ( F) 2192 2189 1956 Peak Local Clad Oxidation (:) 10.42 9.71 5.32

'eak Core-Wide Clad Oxidation (:) <.787 <.787 <.787 These results show that all JZCA acceptance. criteria are met at a PLHGR of 15.6 tw/ft,. and there is substantial margin at 14.2 kw/ft.

An analysis is presented in Reference 1 which demonstrates that one Safety Injection Tank can be isolated without. reducing core power or PLHGR.

The flow rate reduction will not alter this conclusion.

II. Discussion and Results In order to detexmine the sensitivity. of peak clad temperature to flev, the worst break (0.8 DEG/PD) identified in .Faference 1 was repeated at the lower floiv rate. As a conservative approximation, the CEFLA&-4A Q.ev The worst bre is t e '0;8 Double-Ended Guillotine at the Pump Discharge (0.8 DEG/PD)

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.rate determined for the worst break in Reference 1 was simply reduced 4';. and the STRIKIN-II calculation was repeated; the CFFLASH-4A calculation was not rerun at the. lower flow rate (or at a reduced core power).

If the CEFLASH-4A calculation had been rerun with a lnwer initial flow rate, the transient flow during blowdown would not have been as conservative as the flow obtained by uniformly reducing the reference flow by 4:.

's note'd,in Section, I, calculations, were performed at two PLHGR values:

'5."6 hv/ft and. 14.2 hv/ft., The core and 'system parameters"used for these calculations are the same as those reported in Reference 1; the only differences are the flow and parameters dependent on the PLHGR, which are tabulated in Table II-1; \

"Pertinent information for the ~vo cases are reported in. Table II-Z.

Since. the peak clad temperatures and peak local oxidation percentages for the .

reduced flow cases are less than the values reported in Reference'1, it follows that the core'-wide oxidation percentages would also be lower. Therefore, it was

'not necessary to recalculate the core-wide oxidation percentage; the value in Table II-2 is from Reference 1'..

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The results 'of the,low flow reanalysis are depicted graphically in Pigures II-1 and II-2, which. show peak clad 'temperature and, local clad oxida-percentage as -a function of time for the two PLHGR values considered.

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'E IXI REFERENCES

1. Safety Injection System Analysis of St. Lucie Unit.I for FSAR, Section 6.3.3.6 'as amended by Revision.855, 2-9-76.

2. CENPD-132, "Calculative >tethods for. the C-E Large Break LOCA Evaluation Model", August, 1974 (Proprietary) .

CENPD-132, Supplement 1, 'tJpdated Calculative Methods for the C-E Large Break IQCA.Evaluation Model", December,'1974 (Proprietary) .

CENPD-132, Supplement 2, "Calculational Methods for the C-E Large Break LOCA Evaluation Model", July, 1975.

4

'3. Acceptance Criteria for Emergency Core Cooling Systems for Light-Nater-

,Cooled Nuclear Power Reactors, Federal Register, Vol. 39, No. 3 - Friday, January 4, 1974.

4. CENPD-133, "CEFLASH-4A, A FORTRAN IV Digital Computer Program for Reactor Blowdown Analysis", April 1974 (Proprietary) .

CENPD-133, Supplement 2, "CEFLASH-4A, A FORTM D~ Digital Computer Program for Reactor Blowdown Analysis (Modification)", December, 1974 (Proprietary).

5. CENPD-135 - "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program", April, 1974 (Proprietary).

CENPD-135, Supplement 2, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program (Modification)", December, 1974 Proprietary) .

Table'I-1 Selected System Parameters Reduced Flow Study guantiti System Flow Rate (total) 134;06 x 10 1bs/hr Core Flow Rate 129.10 z 10 lbs/hr Peak Linear Heat Generation Rate 15.6 14.2 kw/ft Gap Conductance at PLHGR 806.3 725;7 Btu/hr-ft2 -0 F Fuel Centerline Temp. at PLHGR 4021. 6 3765. 9 F 2640.6 2513.3 oF Fuel Average Temp. at PLHGR

Table II-2 O.

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.. Times of Interest, Peak Clad Temperature, and Oxidation Percentages 0.8 DEG/PD with Reduced Flow PLHGR 15.6 kw/ft 14.2 lo /ft V

Hot Rod Rupture Time 9.97 sec. 10.2 sec.

Peak Clad Temperature 2188.5 F 1956.1 F Peak Local Clad Oxidation 9.71: 5.32$ .

Peak Core-1'fide: Clad Oxida- <0.787: <0.787>o tion

2.2.0 0 Figure II. 1 ST. LUCIE LAIT 1 REDUCED FLOh'.8 X DOUBLE ENDED GUILLOTINE BRE.K IN PPiP DISCHARGE LEG PEAK CLAD TBPER~1TURE 2.000 15.6 hv/f 2800 14.2 hv/W 3.4 00.

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APPENDIX B Calorimetric techniques are methods of measurementmea-employing basic NSSS heat balance equations. Easily sured parameters, such as temperature and pressure, are used in a system heat balance equation to estimate other parameters, which may be. difficult to measure directly.

Calorimetric techniques are used in power ascension test-ing to determine a variety of system parameters. The interim context in which calorimetrics are germane to the tech. specs. is limited to the extent that the subject tech. specs. allow ascension to the higher power levels

. which 'are prerequisite to accurate calorimetric determina-tions of flow.

The general form of the NSSS heat balance equation is as follows:

SG Core + Q other sources . losses i.e., the total heat output from the steam generators equals the sum of the sources (core, pumps, pressurizer heaters, etc.) minus the heat losses (to.containment, ambient com-ponent cooling water, etc.), where heat output of the steam generator '(Q SG ) is determined by measurement of the saturated steam pressure and the feedwater flow rate and temperature.

The feedwater flow is accurately measurable due to the calibrated nozzles in the feedwater lines. The heat output of the core (Q Core ) equals Whh, where W is the flow rate being derived'nd the enthalpy rise (hh) is derived from measured inlet and outlet coolant temperatures.

error Itdecreases should be noted that the enthalpy rise measurement with increasing power level. Q other th sources is obtained by applying known efficiencies and measurements of ele'ctrical power consumption of the R. C. pump motors and pressurizer heaters. Qllosses are measured during the post-core hot functional testing in conjunction with measurement of the other sources Solving this equation for flow yields an estimate which has an accuracy. equivalent to that of the pump hp flow mea-surement techniques. Calorimetrics provide a useful confirma-tory technique due to the use of totally independent and accurately measurable system parameters.