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Boric Acid Concentration Reduction
	ML20153G092
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Site:	Saint Lucie
Issue date:	09/01/1988
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	CEN-365-(L), NUDOCS 8809080038
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i' ATTACID(ENT 4 ST. LUCIE UNIT 2

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Boric Acid concentration Reduction Report CEN - 365 (L) 9 eg P

PNU EJW/020.PLA L. . . . . . . . . .

l BORIC ACIO CONCENTRATION REOUCTION EFFORT CEN - 365 (L)

TECHNICAL BASES AND OPERATIONAL ANALYSIS t

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b Table of Contents l

Section Title Pace 1.0 Introduction 1-1

1.1 Purpose and Scope

1-1 1.2 Repor't Organization 1-2 1.3 Past vs. Present Methodology for 1-2 Setting BAMT Concentration '

2.0 Technical Bases for Reducing BAMT 2-1 ;

Concentration 2.1 Boric Acid Solubility 2-1 2.2 Method of Analysis and Assumptions 2-1 2.2.1 RCS Boron Concentration vs. Temperature 2-1 2.2.2 Impact of Various Cooldown Rates 2-5 i.

2.2.3 App 1tcability to Future Reload Cycles 2-6 2.2,4 Boron Mixing in the RCS and in the 2-6 Pressurizer !

2.3 Borated Water Sources - Shutdown 2-7 I (hodes 5 and 6)

.s 2.3.1 Soration Requirements for Mides 2-7 5 and 6 ;

2.3.2 Assumptio.is Used in the t,cdes 2-7 -

5 and 6 Andlysis 2.3.3 Modes 5 and 6 Analysis Results 2-8 i

d Table of Contents (cont.)

Section Title pace 2.4 Borated Water Source - Operating 2-16 (Modes 1, 2, 3, and 4) 2.4.1 Boration Requirements for Modes 2-16 1, 2, 3, and 4 2.4.2 Assumptions used in the Modes 2-16 1, 2, 3, and 4 Analysis 2.4.3 Modes 1, 2, 3, and 4 Analysis 2-17 Results 2.4.4 Simplification used Following 2'21 Shutdown Cooling Initiation 2.4.5 Refueling Water Tank Boration 2-22 Requirements-Modes 1, 2, 3 and 4 l

2.5 Boration Systems - Bases 2-24 i

2.6 Response to Typ,1 cal Review Questions 2-25 3.0 Operational Analysis 3-1 3.1- Introduction to the Operational 3-1 Analysts 3.2 Response to Emergency Situations 3-1 3,3 -- Fend-and-Bleed Operations 3-2 3,4 Blended Makeup Operations 3-4

l TableofContents(cont.)

Section Title Page 3.5 Shutdown to Refueling - Mode 6 3-5 3.6 Shutdown to Cold Shutdown - Mode 5 3-8 3.7 Long Tem Cooling and Containment 3-10 Sump pH ,

1 4,0 References 4-1 F

Appendix 1 Derivation of the Reactor Coolant ---

System Feed-and-Bleed Equation Appendix 2 A Froof that Final System Concentration ---

is Independent'of System Volume !

Appendix 3 Methodology for Calculating Dissolved ---

Boric Acid per Gallon of Water '

Appendix 4 Hetinodology for Calculating the --- -

Conversion Factor Between Weight ;

Percent Boric Acid and ppe Boron

.ippendix 5 Bounding Physics Data Inputs ---

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Boric Acid Concentration Reduction Effort Technical Bases and Operational Analysis CEN-365(L)

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1.0 INTRODUCTION

1.1 PURPOSE AND SCOPE This report defines the methodology and outlines the technical bases which allows a reduction in the boric acid makeup tank (BAMT) -

concentration to the point where heat tracing of the boric acid makeup 4

system is no longer required in order to prevent boric acid precipitation. The basic methodology or procedure used to set the minimum BAMT concentration and level for Modes 1, 2, 3, and 4 is derived ;

from the safe shutdown requirements of NUREG 0800 Branch Technical Position RSB 5-1, "Design Requirements for the Residual Heat Removal

. System",(BTP5-1). The St. Lucie Unit 2 plant has been classified as a l Class 2 plant. Two independent boration sources are provided to compensateforreactivitychangesandallexpectedtransientsthroughout core life. Thesesourcesaretheboricacidmakeuptanks(BAMT)andthe refuelingwatertank(RWT). This report reexamines the design basis used to establish BAMT boron concentration and volume requirements. In l addition, the minimum RWT volume requirements are recalculated.

Specifically, sufficient dissolved boric acid is maintained in these tanks in order to provide the required shutdown margin of Technical .

I Specification 3.1.1.1 for a cooldown from het standby to cold shutdown I conditions. In a'ddition, the minimus BAMT concentration and level for Modes S.pd 6 are based upon the ability to maintain the required f shutdown margin in Technical Specification J.1.1.2 following xenon decay ,

I and cooldown from 200 degrees to 135 degrees.

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1-1

The work detailed in this report was perfonied specifically for the St.

Lucie Unit 2 plant. Ths calculation perfcrmed herein and the values obtained should be applicaLle to future cycles. (See Section 2.2.3 below). The physics parameta?s used in this analysis were conservatively selected to bound core physics 7arameters for the remainder of plant

!1fe. Future cycle core php ics parameters will be compared to the data in Appendix 5 to ensure that this calculation is bounding. The curve in Figure 3.1-1 of Technical Specification 3.1.2.8 and the values in 3.1.2.7 may change slightly; however, there should not be a need to heat trace the majority of the boric acid system for the remainder of plant life.

1.2 REPORT ORGANIZATION This report has been organized into three general sections:

Introduction, Technical Bases, and Operational Analysis. The Technical Bases Section 2.0, outlines the methodology which allows a significant reduction in boric acid makeup tank concentration and pruents the results of the detailed calculations perfonned in support of the Technical Specifications. Separate calculations were perfonned for Specification 3.1.2.7 (Borated Water Source - Shutdown), Specification 3.1.2.8(BoratedWaterSource-Operating),andSpecificationB3/4.1.2 (BorationSystemsBases). For completeness, the volume requirements for the RWI have been recalculated to demonstrate that the bora: ton requirements fer reactivity control in Modes 1, 2, 3 and 4 are much less than the emergency core cooling requirements. Also it.cluded in Section 2.0 are the technical responses to typical questions asked by the NRC during review of similar submittals by other nuclear facilities. The OperationalAnalysisSection,Section3.0,outlinestheimpactonnormal operatJqns of a reduced boric acid makeup tank concentration. The types of operations evaluated in Se<: tion 3.0 include feed-and-bleed, blended makeup, shutdown to refueling, and shutdown to cold shutdown. All tables and figures are contained at the end of each section for easy reference.

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1.3 pAST vs. PRESENT METH00CLOGY OF SETTING DANT CONCENTRATION L

Prior to the development of the new methodology for setting BAMT concentration and level described in this report, the level and concentration specified in the plant Technical Specifications for Modes 1, 2, 3, and 4 were based upon the ability to perform a cooldown to cold shutdown in the absence of letdown. (Safe Shutdown requirements of NUREG-0800 BTP 5-1 event). The RC5 wts borated to the boric acid concentration required to provide a shutdown margin of 5000 pcm at 200 degrees prior to comencing plant cooldown. In the limiting situation where letdown was not available, this boration was accomplished by charging to the hCS while simultaneously filling the pressurizer. Since boron concentration typically had to be increased by 800 ppm or more prior to comencing cooldown, highly concentrated boric acid solutions were required due to the limited space that was available in the pressurizer.

Relatively recent advances have made it possible to develop new methodolyies for se.tting BAMT concentration and levels. The methodology for setting concentration and , level of Modes 1, 2, 3, and 4 described in this report differs from previous methodologies in that boration of the retetor coolant system is perfomed concurrently with plant cooldown, i.e., concentrated boric acid is added concurrently with cooldown as part of nonnal ~ inventory makeup due to coolant contraction. By knosiing the exact boren ce c7ntration required to maintain proper shutdown margin at each temperature during a plant cooldown, BAMT concentration can be decoupled from pressurizer volume. At a result, the concentration of boricacidrequiiedtobemaintainedintheboricacidmakeuptanksin order to perfonn a cooldown without letdewn to cold shutdown conditions can be lowered to a range of 2.5 to 3.5 wtt, where heat tracing of the boric acid systeve is no longer required, i.e., the amblent temperatures that nomally exist in the plant's auxiliary building are sufficient to prevent boric acid precipitation.

1-3

similarly, a new methodology was developed for setting the minimum concentration and level of the boration source required to be operational in Modes 5 and 6. Sin;e letdown is available in Mode 5 and 6 cooldown scenarics, a feed and bleed can be conducted to increase RCS koron concentration. Additionally boration can be conducted concurrently with cooldown as part of nonnal system reaksep. By insuring that the boron concentration is maintained greater than that required for proper shutdown margin at each temperature, the boric acid makeup tank concentration for Modes 5 and 6 can be lowered to 2.5 weight percent.

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2.0 TECHNICAL BASES FOR REDUCING BAMT CONCENTRATION 2.1 BORIC ACIO SOLUBILITY Figure 2-1 is a plot showing the solubility of horic acid in water for '

tetoperatures ranging from 32 to 160 degrees. (Data for Figure 2-1 was obtained from Reference 4.1 and is reprinted in Table 2-1.) Note that the solubility of boric acid at 32 degrees is 2.52 weight percent and at 50 degrees is 3,49 weight percent. At or below a concentration of 3.5 weight percent boric acid, the ambient temperature that normally exists in the auxiliary building will be sufficient to prevent precipitation within the boric acid makeup system.

2.2 METHOD OF ANALYSIS AND ASSUMPTIONS 2.2.1 RCS Boron Concentration vs. Temperature .

i 2.2.1.1 Operating Modes 1, 2, 3 and 4 :

As stated in Section 1.3 above, the methodology developed to allow a significant reduction in the boric acid concentration required to be maintair.ed in the SAMTs in Modes 1, 2, 3, and 4 differs from the previous i methodology in that boration of the reactor coolant system is performed concurrently with cooldown in order to insure proper shutdown margin, i.e., concentrated boron is added as part of normal system v.akeup during the cooldown process. To employ a methcdology allowing boration concurrent with cooldown, the exact boron concentration required to be present in the reactor coolant system must be known at any temperature ,

during.the cooldown process. In addition, in order to insure applicability for an entire cycle, a cooldown scenario must be developmi ,

which is conservative in that it places the greatest burden on an operator's ability to control reactivity, i.e., this scentrio must define the boration requirements for the most limiting time in core cycle. Such l a limiting scenario is as follows:. .

2-1

1. Conservative core physica parameters were used to determine the required boron concentration and the required Boric Acid Makeup Tank volum s to be added daring plant cooldown. End-of-cycle initial boron concentration is assumed to be zero. End-of-cycle moderator cooldown effects are used to maximize the reactivity change during the plant cooldown. Ent of-cycle (EOC) inverse boron worth data was used in combination with EOC reactivity insertion rates normalized to the most Negative Technical Specification Moderator Temperature Coefficient (MTC) limit since it was known that this yields results that are more limiting than the combination of actual MTC and actual IBW values at all periods through the fuel cycle prior to end-of-cycle. These assumptions assure that the required boron concentration and the Boric Acid Makeup Tank minimum volum requirements conservatively bound all plant cooldowns during core life.

2. The most retctive rad is stuck in the full out position.

3. prior to time zero, the plant is operating at 100% power with 100%

equilibrium xer.on. Zero RCS leakage.

4 At time zero, the plant is shutdown and held at hot zero power conditions for 25.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . (The xenon peak after shutdown will have t

, decayed back to the 100% power equilibrium xenon level. Further xenon decay will add positive reactivity to the core during the plant cooldown.) No credit was taken for the' negative reactivity ;

1 effects of the xenon concentration peak following the reactor ,

shutdown. N

.. I S. At 25.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , offsite power is lost and the plant goes into natural circulation. All non-safety grade plant equipment and components are lost. During the natural circulation the RCS average temperature rises 25DF due to decay heat in the core. The initial tercerature at the start c'f'the cooldown is 5570F, ,

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6. Approximately 0.5 hourt later, at 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months , the operators comence a cooldown to cold shutdown.

The scenario outlined above was used to generate the boration requirements for Modes 1, 2, 3, and 4 (Specification 3.1.2.8). It produces a situation where positive reactivity will be added to the reactor coolant system simultaneously from two sources at the time that a plant cooldown from hot shutdown is comenced. These two reactivity sources result from a temperature effect due to an overall negative isothermal temperature coefficient of reactivity, and c poison effect as the xenon-135 level in the core starts to decay below its equilibrium value at 100% power. This scenario, therefore, represents the greatest challenge to an operators ability to borate the reactor coolant system and maintain the required Technical Specification shutdown margin while cooling the plant from hot standby to cold shutdown conditions, i

2.2.1.2 Operating Modes 5 and 6 The methodology develcped for Modes 5 and 6 differs from the method used in previous rett., .g cycles to detennine boration requirements. In this new methodology boration of the reactor coolant system is perfonned concurrently with cooldown. Concentrated boric acid is added as part of normal system nakeup during the cooldown process. To employ a methodolo~gy allowing boration concurrent with cooldown, the exact boron concentration required to be present in the reactor coolant system must be known at any. temperature during the cooldown ptocess. The following scenario was developed to identify the most limiting cooldown transient for Modes 5 and'6.

1. End-of-cycle conditions.with the initial RC$ boron cencontration necessary to provide shutdown margins of 3000 pcm at 200 degrees and xenon free core. EOC moderator cooldown effects are used to maximize the reactivity change during the plant cooldown.

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End-of-cycle (EOC) inverse boron worth data was used in combination with EOC reactivity insertion rates no*malized to the Most Negative Technical Specification Moderator Temperature Coefficient (MTC) limit since it was known that this yields results that are more limiting than the combination of actual MTC and actual IBW values at all periods through the fuel cycle prior to end-of-cycle.

2. Most reactive rod is stuck in the full out position i

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3. Zero .CS a leakage. ,

l 4 RCS feed-and-bleed can be used to increase boron concentrattor,. :

5. RCS makeup is sur, plied either from the RWT alone or a combination of makeup from the BAMT and RWT.

, G. The most Ilmiting scenario for boration in Mode 5 requires that a 3000 pcm shutdown be maintained during the cooldown from 2000 F to ,

. 135C F. The baration requirements for Mode 6 only address ;

maintaining a previously established shutdewn margin. If the required shutdown margin for Mode 6 is not maintained, Technical l Specification 3.9.1 requires that the RCS be borated at 40 gallons l per minute from source of water 2 1720 ppe bc.'on. Technical ,

. Specification 3.1.2.7 provides three alternative sources to meet this requirement, either BAMT or the RWT.

The scenario outlined above was used to determine the bo ation i requirements for' Modes 5 and 6 (Spocification 3.1.2.7). It produces a i situation.where positive reactivity will be arided to the reactor coolant l l system due to the overall negative isothermal temperature coef ficient of reactivity. Since the core is already assumed to be xenon free there is I no contribution to core reactivity due to xenon decay.

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e i t 2.2.2 gactofVariousCooldownRates As discussed in the previous Section, a conservative cooldown scenario was selected for use in determining RCS boren concentration levels.

These concentration results were then used to define the minimum Technical Specification boric acid makeup tank inventory requirements.

In the scenario for Modes 1, 2, 3, and 4, positive reactivity was added simultaneously from two sources at the time that the plant cooldown from hot standby was coasr,enced. The component resulting from an overall negative isothennal ta.aperature coefficient of reactivity is independent of time, but it is directly dependent upon the amunt that the system has been cooled. In contrast, the component that results from the decay of xenon-135 below its equilibrium value at 100% power is independent of terperature, but directly dependent upon time. As a result, a slow cooldown rate will require more boron to be added to the reactor coolant system than a fast cooldown rat'e for a given ttmperature decrease since more positive reactivity must be eccounted for due to xenon decay. This effect is illustrated in 'igure 2-2 and is applicable to the Modes 1, 2, 3, and 4 analysis. Note that the bases for Technical Specification 3.1.2.7 require a cocidown following xenon decay. As a result, boration requirements are independent of cooldown rate for the Modes 5 and 6 analysis.

For the purpose of setting tt;e minimum Technical Specificatinn boric acid I makeup tank inventory requirements in Modes 1, 2, 3, and 4, reactor coolant system toron concentration data was used that was based upca en '

overall cooldown rate of 12.5 deg:ee per hour. This slow cooldown rate was chosen in ord'er to be consistent with the time frames specified in a

Section.5 2 of Referance 4.3 (natural circulation cooldown in ct NSSS) for reactor vessel upper head cooldown. Specifically, 23.07 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months was required in order to take the plant from hot standby conditions to cold shutdown as shown in Table 2-2. For additional cunservatism, 5.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months was added to this number to arrivo at a final total of 28.8 heurs. An overall cooldown rate, thereforet of 12.5, degrees per hour was required 2-5 L _ _ ~ l

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to cool the plant from an average coolant temperature of 557 degrees to an average coolant tempersture of 200 degrees in 28.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This cooldown scenario will conservatively bound cooldowns that occur sooner and/or at a higher cooldown rate. The above scenario bounds the reactivity affects of a STP 5-1 cooldown. It is assumed in the 8TP 5-1 scenario that the RHR will be capable of W inging the RCS to cold shutdown conditions within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . With respect to Xenco reactivity j , affects the scenario used in this report bounds the 36 %ur cooldown time I frame of BTP 5-1 (26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months to let Xenon return to 100% equilibrium level and 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months for a slow cooldown).

l 2.2.3 Applicability to Future Reload Cycles

, To ensure that the current eralysis would be valid for future cycles, data from St. Lucie Unit 2 Cycle 3 was conservatively bounded. Cycle 3 physics data was used because Unit 2 was in that operating cycle at the start of the Boric Acid Concentration Reduction Effort. The physics data used in this analysis should bound future fuel cycles of similar reload cores. The physics data used in the calculation does bound the physics data for St. L.ucie 2 Cycle 4 Appendix 5 contains bounding physics assumptions that were used to produce the required boron concentration vs. lues. As long as these inputs are more conservative than the reload cycle physics parameters, the values produced in this analysis will bound the boron concentration values for the future reload cycle'..

1 2.2.4 Boron M hi'ne in the RCS and in the pressurizer '

Throughout the pla'nt cooldowns performed in Section 2.3 and Section 2.4 below, agenstant pressurizer level was always assumed, i.e., plant operators charged to the RCS only as necessary to makeup for coolant cantraction. The driving force is small, in this situation, for the ratxing of fluid between the ' reactor coolant system and the pressurizer.

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l As a conservatisir., however, complete and instantaneous mixing was assumed between all makeup fluid added to the reactor coolant system through the loop charging nozzles and the pressurizer. Further, various pressure reductions were performed during the plant cooldown process as indicated to Section 2.4. These pressure reductions are necessary since the shutdown cooling system is a low pressure tystem and is normally aligned at or below an RCS pressure of 275 psia. Typically, such depressuriza> ions are performed using the auxiliary pressurizer spray system under conditions where the reactor coolant pumps are not running.

As an added conservatism in the Modes 1, 2, 3, and 4 analysis, any boron added to the pressurizer via the spray system was assumed to stay in the 1 pressurizer and not be available for mixing with the fluid in the remainder of the RCS.

2.3 BORATED WATER SOURCES - SHUTDOWN (MODES S AND 6) 2.3.1 Boration Requirementy_for Modes 5 and 6

As stated in the plant Technical Specifications, the boration capacity required below a reactor coolant system average temperature of 200 l degrees is based upon providing a shutdowr. margin of 3000 pcm following l xenon decay and a plant cooldown from 200 degrees to 135 degrees. From 6 this basis the requ'# red RCS boron concentrations were detemined using cens,ervet.ve core physics data. The results of these calculations are l contained.in Table 2-3. The results contained in Table 2-3 are plotted as the rtquired. shutdown curve in Figure 2 3. Note that a total boron i concentration increase of 46.0 ppm for St. Lucie 2 was required for the cooldown. N i

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c.3.2 Assumptions Used in the Modes 5 and 6 Analysis j

A complete list of assumptions and initial conditions used in calculating

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the minimum boric acid makeup tank inventory requirements for Modes 5 and l 6 is contained in Table 2-4 In the process of taking the plant from hot !

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f standbytocoloshutdown,theshutdowncoolingsystem(SDCS)will nonnally be aligned when the RCS temperature and pressure have been lowered to approximately 325 degrees and 275 psia for St. Lucie 2. As shown in the next Section, the total system volume, i.e., RCS volume plus PZR volume plus SDCS volume, is required to be known for the Modes 5 and 6 analysis. The exact volumes of the reactor coolant system and the pressurizer are known. The exact volun of the shutdown cooling system, however, is not known. (Best estimate calculations for this volume have yielded values from approximately 2500 ft3 to approximately 3000 ft3 ),

For the purpose of the analysis in the following Section, the volume of the shutdown cooling system will be chosen conservatively large, equal to the RCS volume, so as to yield conservative results with respect to minimum boric acid makeup tank inventory requirements.

The e' xact system volume used in the Modes 5 and 6 calculation is as follows:

2x(RCSvolume)+(PZRvolumeat0%pcwer),

or ,

3 3 3 2(9398ft)+(450ft)=J,9,246ft

, 2.3.3 , Modes 5 and 6 Analysis Results 4

As stated in Section 2.3.1, the boration capacity required below a reactor coolant system average temperature of 200 degrees is based upon providing shutdoin margins of 3000 pcm for St. Lucie 2 following xenon decay and a plant cooldown from 200 degrees to 135 degrees. The operating scenario that will be employed for the purpose of detennining reactor coolant system boron concentration and ensuring that proper shutdown margin will be maintained is as follcws:

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Option 1: Provide RCS Makeup From BAMT A. The systems are initially at 200 degrees and 275 psia. Initial concentration in the reactor coolant system, pressurizar, and in the -

shutdown cooling system is 570.3 ppm boron. (See Table 2-4 for a complete Itst of assumptions).

B. Perform a plant cooldown from an average temperature of 200 degrees to an average temperature of 135 degrees using makeup water from the BAMT (2.5 weight % boric acid solution at 70 degrees). Charge only as necessary to makeup for coolant contraction.

From Equation 2.0 of Appendix 3 and the conversion factor that 1.1 derived in Appendix 4, the initial boric acid mass in the system can be calculated as follows:

4 570,3 ppm 18,796 ft 3 , 450 ft 3 3 3 i 1748.34 ppm /wt. 5 _ D.01662 ft /lbe 0.018775 ft /1NL r "ba " Idd-(570.3 ppm)/(1748.34pfc/wt.3) or m

ba

= 3779.5 lbm boric acid j j

Knowing the initial mass of boron in the system, the exact concentration and makeuprequirementsianbecalculatedforeach10degreesofacooldownfrom 200 degrees to 135 deg,rees. These values are contained in Table 2-6.

Equations used to obtain the values shown in Table 2-6 are as follows:

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Shrinkage Mass =

18,796(1/vf-1/vg)

Water Vol. =

(Shrinkage Mass) / (8.329 lbm/ gallon (I)

Boric Acid Added =

(Water Vol.) x (0.21356 lbm/ gallon) 2)

Total Boric Acid =

(InitialBoricAcid)+(BoricAcidAdded)

Total System Mass = (TotalinitialMass)+(ShrinkageMass)+

(BoricAcidAdded)

Final Conc' = (Total Boric Acid)(100)(1748.34)(3) .

(Total System Mass)

Note that the initial total system mass of 1,158,674.2 lbm in Table 2-6 was obtainied as follows:

(!nitialBoricAcid)+(InitialSystemWaterMass)+

(PressurizerWaterMass) 3

= 3779.5 lba + (18,976 ft / 0.01662 ft 3/lbm) +

3 l

(450ft / 0.018775 ft 3/lba)

= 1,158,674.2 lbm 4

(1) Water density at 70 degrees.

(2) See Appendix 3 for values of dissolved beric acid in water.

(3) See Appendix.4 for the conversion factor between wt. % and ppm.

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The boration results from the system cooldown from 200 to 135 degrees are plotted as the actual concentration curve in Figure 2-4. As can be seen from this figure a shutdown margin of greater than the required 3000 pcm was maintained throughout the evaluation. A minimum concentration of 2.5 weight 1 boric acid was therefore specified in the plant Technical Specification 3.1.2.7. The minimum volume that should be specified in the Technical Specification is 3550 gallons. This volume was determined as follows: l Makeupvolume$4I 3049.0 gallons -

Arbitrary amount 500.0 gallons for conservatism

Total 3549.0 gallons

. Round up to nearest 3550 gallons 50 gallons l

i (4) Total of values in Water Voi, column of Table 2 6, l .

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OPTION 2: Feed and Bleed then Cooldown from RWT The RWT will not provide enough boric acid to compensate for the reactivity inserted during the cooldown if charging is restricted to makeup for coolant !

contraction only. A system feed-and-bleed must be perfonned to raise the RCS i concentration before the cooldowie is consnenced. The initial feed-and-bleed ensures that the actual RCS boron concentration is maintained above the required boron conctntration for a 3000 pcm shutdown margin while the plant is cooled down from 200 degrees to 135 degrees.

For St. Lucie 2, in order to calculate the initial increase in boron concentration during the 3200 gallon system feed-and-bleed, Equation 9.0 of ,

Appendix 1 will be used with values as follows:

C, a 570.3 ppm Cin = 1720 ppm 1

3 3 3 3 T=118,976ft/0.01662ft/1bm)(5)+C450ft/0.018775ft/1bm)(6) l

67) Ibn 40 gallons , 8.343 l min gallon i

T- = 3,493.1 min. l l

(5) Specific volume of compressed water at 200'F and 275 psia (6) Specific volume of saturated water at 275 psia :

1 (7) Density of water at 50'F l s ;

)

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If one charging pump at 40 gpm (as assumed in calculating the value of T above) is used to conduct the system feed-and-ble:d, 80 minutes are required (3200 gal /40gpm=80 min). Concentrations vs time for the feed-and-bleed from equation 9.0 of Appendix D is therefore:

Time, Cone 0 570.3 20 577.0 40 583.5 60 590.1 80 596.6 The feed-and-bleed portion of the cooldown process is indicated on Figure 2-4 as the vertical line. As shown, concentration was increased from 570.3 ppm to 596.6 ppm following the 3200 gallon feed-and-bleed.

From Equation 2.0 of Appendix 3 and the conversion . actor derived in Appendix 4, the mass of boric acid in the system corresponding to concentrations of 596.6 ppm can be calculated as follows:

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1 CM

=

M ba 100 - C

, C(596.6 com)/(1748.34pom/wt.%): (18.976ft 3/0.0L662ft /1bm+450ft 3 3

/0.018775ft 3/1bm) 100 - (L96.6 ppm)/(1748.34pps/wt.%)

= 3954.2 lbm boric acid Knowing the masses of boric acid in the system following the feed-and-bleed, the, exact concentrations and makeup requirements can be calculated for each 10 degress of cooldowns from 2000 F to 1350F. These values are contained in

Table 2-7. The cooldown assumes a constant pressurizer volume of 450 ft3 and a constant pressure of 275 psia. In addition, complete mixing between the RCS i

and the PZR is assumed as discussed in Section 2.2.4 above. Equations used to

[ obtain the values contained in Table 2-7 are as follows:

Shrinkage mass = 18,976 (1/vf - 1/vg )

{ Water Vol. = (Shrinkage mass) / (8.343 lbm/ gallon)

.i Boric acid added = (water vol.) (0.08289 lbm/ gallon) i i

Total boric acid = initial boric acid + boric acid added 1

T, -

j Total System mass = Total initial mass + shrinkage mass + boric acid added

Final concentration = (Total Boric Acid) (100) (1748.34)

Total System Mass s

I i

4 I

2-14 i

. ~ .

The results of the initial system feed-and-bleed plus the plant cooldown are plotted as Curve !! in Figure 2-4 Note that throughout the evaluation, a shutdown margin greater than 3000 pcm was maintained as required.

The initial total system mass in Table 2-7 was obtained as follows:

Initial boric acid mass + initial system water mass + initial PIR water mass =

3 3 3 3 3954.2 lbm + (18.976 f t ) / (0.01662 tt /lbm) + (450 ft ) / (0.018775 f t /lbm)

= 1,153,730.2 lbm RWT concentrations of 1720 ppm will therefore be specified in Technical Specification 3.1.2.7 since the proper shutdown margin could be maintained.

The minimum volume will be specified as follows for the RWT cooldown:

Feed-and-Bleed Volume 3200.0 gallons Makeup Volume 3043.1 gallons Total 6243.1 Round up to nearest 6750 gallons 50 + 500 gallons.

With 60,000 gallons of the RWT unusable, the actual required volumes in the RWT at 1720 ppm is 66,750 gallons for St. Lucie 2.

G g e

2-15

/

2.4 BORATED WATER SOURCES - OPERATING (MODES 1, 2, 3, and 4) 2.4.1 Boration Requirements for Modes 1, 2, 3, and 4 For this analysis a shutdown margin of 5000 pc2 is provided at all temperatures above a reactor coolant system average temperature of 200 degrees. For temperaturer at or below 200 degrees, a shutdown margin of 3000 pcm is provided after xenon decay and cooldown to 200 degrees. From this basis, the requ' red i RCS boron concentrations were determined using conservative core physics parameters and the limiting cooldown scenario outlined in Section 2.2.1 above. The results are plotted as the shutdown curve in Figure 2-5.

2.4.2 Assumptions Used in the Modes 1, 2, 3, and 4 Analysis A complete list of assumptions and initial conditions used in cal:ulating the minimum boric acid makeup tank inventory requirements for Modes 1, 2, 3, and 4 are contained in Table 2-5. Note that complete and instantaneous mixing between the reactor coolant system and the pressurizer was assumed as stated in Section 2.2.4 for all fluid added to the reactor coolant system via the loop charging nozzles. The mechanism used to implement this assumption in the analysis was to include the pressurizer water mass as part of the total system mass for the purpose of calculating boron concentration. Specifically, boron concentration in I terms of weight fraction is defined as follows:

1 1 .

l (mass of boron in system)

(total system mass) 4 t

2-16

where, if complete mixing is assumed between the RCS and the pressurizer, the total system mass is the sum of the boron mass in the system, the reactor coolant system wat..c mass, and the prcssurizer water mass.

Therefore, the initial total system mass of 458,2.?8.7 lbm in Table 2-8 through Table 2-32 for St. Lucie 2 was calculated as follows:

Initial boron mass + Initial RCS water mass + Initial PZR water mass, or 3

0+ -

'398 ft +

600 ft 3

(8) 3 (9) 0.021567 ft /lbm 0.02669 ft /lbm 2.4.3 Modes 1, 2, 3, and 4 Analysis Results As stated in Section 2.4.1, the boration capacity required below a reactor coolant system average temperature of 200 degrees is based upon providing a 3000 pcm shutdown margin after xenon decay and a plant cooldown to 200 degrees from expected operating conditions. In addition, for this analysis a shutdown margin of 5000 pcm is provided at all temperatures above a reactor ceolant system average temperature of 200 degrees. In order to perform a plant cooldown from hot standby conditions to cold shatdown and maintain the above shutdown margin at each temperature above 200 degrees, the following operating scenario will be empl'oyed: .

(5) Specific volumei'of compressed water at 557 degrees and 2200 psia.

(9) Specific volume of saturated water at 2200 psia.

~~

e g' s

G 1

2-17

4 A. Assuming the initial conditiens outlined in Table 2-5, perform a plant cooldown starting from an initial RCS average temperature of 557 degrees to a final average system temperature of 200 degrees.

\

B. Charge to the RCS only as necessary to makeup for coolant contraction. Charge from the BMT initially until BMT is drained, then switch to the RWT for the remainder of the cooldown.

The exact reactor coolant system boron concentrations versus temperature for plant cooldowns and depressurizations from 557 degrees and 2200 psia to 200 degrees and 275 psia with a boric acid makeup tank concentration of 3.50 weight percent and a refueling water tank concentration of 1720 ppm boron is contained in Teble 2-8. These results are plotted as the actual concentration curve in Figure 2-5. (Theexacttemperatureat which charging pump suction was switched from the BMis to the refueling water tank was determined via an iterative process. In this process, the smallest boric acid makeup tank volume necessary to maintain the required shutdown margin was calculated for the given set of tank concentrations).

Note that at each temperature during the cooldown process, RCS boron concentration is greater than that required for the shutdown margin of 5000 pcm. Also note in Figure' 2-5 that the shutdown margin drops from 5000 pcm to 3000 pcm at an average coolant temperature of 200 degrees.

Following xenon decay the final con;entration required to be present in the, system at the most limiting time in core cycle is 570.3 ppm boron.

Using the scinario outlined on the previous page, the final system concentrations'will always be at least 64.6 ppm greater than these amounts.

s A detaile,d parametric analysis was performed for tne modes 1, 2, 3, and 4 Technical Specification (Specification 3.1.2.8). In this study BMT concentration was varied from 3.5 weight percent boric acid to 2.5 weight percent boric acid. Although St. Lucie Unit 2 Technical Specifications 2-18

allow only a maximum RWT concentration of 2100 ppm baron, this report provides analysis for the RWT concentration range from 1720 ppm boron to 2300 ppm boren. This was done to be consistent with the Boric Acid Concentration Reduction Reports provided to other units. The results are contained in Table 2-9 through Table 2-32. Equations used to obtain the values in these tables as well as Table 2-8 are as follows:

Shrinkage Mass =

9398(1/vf - 1/vg)

BAMT Vol. = (ShrinkageMass)/(8.3290lbm/ gallon)(10)

RWT Vol. = (Shrinkage Mass ) / (8.343 lbm/ gallon)IIII Boric Acid Added = (BAMTVol.)x(massofboricacid/ gallon)III}

or

= (RWT Vol.) x (rnass of boric acid / gallon)II2)

Total Boric Acid =

(InitialBoricAcid)+(BoricAcidAdded)

Total System Mass = (RCSwatermass)+(PZRwatermass)(13)+

(Total boric acid)

Final Conc. = (Total Boric Acid)(100)(1748,34)(14)

. (Total System Mass)

(10) Density of water at assumed tank temperature 70*F.

(11) Density of water at assumed tank temperature 50*F.

(12) See Appendix 3 for values of dissolved boric acid in water.

3 (13) PZR water nass = (600 ft ) / '(specific volume at indicated Psat)'

(14) See Appendix 4 for the conversion factor between wt. % and ppm.

2-19

Note that the value of the total system mass at any temperature and pressure in Table 2-8 through Table 2-32 can be obtained as follows:

RCS water mass + PZR water mass + total boric acid mass a total system mass.

As an example, the value of the total system mass At 200 degrees and 275 psia in Table 2-8 was obtained as follows:

3 3 9,398 ft 600 ft

+ + 2350.7 lbm 3 (15) 3 (16) 0.01662 ft /lbm 0.018775 ft /lbm

= 599,771.4 lbm.

In a similar manner as in the results of Table 2-8, the concentration results of Table 2-9 through Table 2-32 were compared to the required concentrations at each temperature for a plant cooldown from 557 degrees to 200 degrees which are contained in Table 2-33. In each case, the actual system boron concentrations were greater than that necessary"for the required shutdown margin as indicated in Figure 2-5. To set the minimum Technical Specification boric acid makeup tank volume corre;ponding to 4he various BAMT and RWT concentrations, the (15) Specific volume of compressed water at 200 degrees and 275 psia.

(16) Specific volume of saturated water as 275 psia.

2-20

makeup tank volumes from Table 2-8 through Table 2-32 were compiled into Table 2-34. The volumes contained in Table 2-34 are the minimum BAMT volumes needed to borate the RCS to the required shutdown margin. These volumes must be contained in the region of the BAMT above zero percent indicated level. These volumes are rounded up to the next 50 gallons and 500 gallons are added to provide conservatism. The resulting volumes after adjustment are contained in Table 2-35. These values are plotted in Figure 2-6. The cooldown scenario used assumes that V-2504 is opened remotely or manually and depressurization of the RCS is achieved by auxiliary spray from the RWT.

In a similar manner, the values at 1720 ppm in the RWT from Table 2-35 are plotted in Figure 3.1-1 of the St. Lucie 2 Technical Specifications.

This figure replaces the existing lechnical Specification Figure 3.1-1.

2.4.4 Simplification Used Following Shutdown Cooling Initiation in the cooldown and depressurization process assumed in Table 2-8 through Table 2-32, the plant operators must physically align the shutdown cooling systems an RCS temperature and pressure of approximately 325 degrees and 275 psia.. Following this alignment, the volume and mass of the system that the operator must contend with during any subsequent cooldown will obviously increase ty the volume and mass asscciated with the shutdown cooling system. Further, the total boron r. ass in the system that the operator is now dealing with will also have increased by the -

amount of boron in the SDCS prior to alignment. In Table 2-8 through 2-32, as a simpitfication, no attempt was made to factor into the equations the higher tatal volume and total boron mass that would result when t6e"shutdown cooling system is placed in service, The use of these simplificattuns in the Modes 1, 2, 3, and 4 calculations can be justified as follows: .

2-21

l

1. At the time that the shutdown cooling system is aligned, makeup is being supplied frem the refueling water tank. Therefore, additional makeup that would be required during the cooldown from 325 degrees to 200 degrees due to a larger system volume

{

will not affect the total BAM1 volume requirements. This assumption would affect the minimum volume requirement of the RWT in Modes 1, 2, 3, and 4. Since the RWT requirements for emergency core cooling are much greater than the requirements for this cooldown scenario, this simpli'ication does not impact RWT sizing requirements, i

2. In a cooldown process where an operato? is charging only as necessary to makeup for coolant contraction, the change in boron concentration within the system is independent of the total system volume, i.e., the final system boron concentration is not a function of total system volume. (Aproofofthis statement is contained in Appendix 2).

3. As stated in Table 2-5 boron concentration in the SOCS is assumed to be equal to reactor coolant system concentration at the time of shutdown' cooling initiation. This assumption is in fact a conservatism since the concentration in that system in most situations will be closer to refueling water tank

,

concentration at the time of initiation.

2.4.5 Refueling Water Tank Boration Requirements-Modes 1.2.3 and 4 The refueling water tank provides an independent source of borated water that can,be used to compensate for core reactivity changes and expected transients throughout core life. It should be noted that in Modes 1, 2, 3 and 4 the minimum RWT water volume is 417,100 gallons as required by emergency core cooling considerations. The purpose of this section is to demonstrate that the RWT minimum inventory requirements in modes 1, 2, 3 2-22

and 4 to compensate for these reactivity chances during a shutdown are much less than the emergency core cooling reouirements.

This calculation derives the minimum quantity of RWT water necassary to bring the plant from hot standby to cold shttdown while maintaining the plant at a 5000 pcm shutdown margin. Ali RCS makeup is supplied from the RWT at a boren concentration of 1720 ppm. inis cooldown is performed as described below.

A. Perform a RCS feed-and-bleed to raise RCS boron concentration from 0 ppm to 388.9 ppm boron. This is a 110 minute feed and bleed using 3 charging pumps.

B. Perform a plant cooldown from an initial RCS temperature and pressure of 557 degrees and 2200 psia to 325 degrees and 275 psig.

Charge only as required to makeup for coolant contraction.

C. Align the shutdown cooling system (SOCS) to the RCS. Assume that 3

the SOCS volume is 9398 ft . Assume that the concentration of the SOCS is equal to that of,the RCS at the time of shutdown cooling initiation.

O. Continue cooldown from 325 degrees and 275 psia to a final RCS condition of 200 degrees and 275 psia. Charge only as necessary to makeup for coolant contraction.

Table 2-38 centains the results of the calculated volumes in steps A j through 0. The 'RWT boration requirement for Modes 1, 2, 3 and 4 has been rounded.up to 35,000 gallons. Figure 2-11 shows the RCS boron concentration as the plant co'oldown progresses. As expected the boration requirements imposed a RWT sizing are much smaller than the minimum volume requirements placed on the RWT by emergency core cooling requirements (417,100 gallons)..

2-23

2.5 BORATION SYSTEMS - BASES The BASES section of the technical specifications was developed to demonstrate +.he boration system capability to maintain adequate shutdown margin frem all operating conditions. Section 1/4.1.2 of the plant Technical Specifications will be changed to state the following:

"The boration capability of either system is sufficient to provide a SHUTOOWN MARGIN from all operating conditions of 3.5% delta k/k after xenon decay and cooldown to 200'F. The maximum boration capability requirement occurs at EOL from full power equilibrium xer.on conditions. '

This requirement can be met for a range of boric acid concentrations in the BAMT and RWT. This range is bounded by 5350.0 gallons of 3.5 weight

% boric acid from the BAMT and 16,000 gallons of 1720 ppm borated water from the RWT to 8650.0 gallons of 2.5 weight % boric acid from the BAMT and 12,000 gallons of 1720 ppm borated water from the RWT. A minimum of i 35,000 gallons of 1720 p m boron is rdquired from the RWT if it is to be used to borate the RCS alone."

The 16,000 gallon RWT volume for St. Lucie 2 in Section 3/4.1.2 of the plant Technical Specifications'was obtained by assuming RCS makeup was provided from the BAMT and the RWT. Total RCS makeup due to the coolant t contraction during cooldown is calculated as descrPsed in A, B and C below. This yielded a contraction volume of 20,$16.1 gallons. From this volume the minimum BAMT volume for +he RWT at 1720 ppm boron from Table 2-35, 5350.0 gallons was subtracted yielding 15,166.1 gallons, which was rounded up to 16,000 gallons. As a result of the addition of 3.5 weight t boric acid fros the BAMT, a feed-and-bleed is not required to maintain l

the shutdown margin of 3.5% delta k/k. Table 2-36 shows how this RWT l volume was calculated.

The 12,000 gallon RWT volume was obtained in a similar manner. The total :

i makeup is the sama. From this volume, the maximum BANT volume for the RWT at 1720 ppm boron from Table 2-35, 8650.0 gallons was subtracted !

~

2-24

_ ,_____ .. _ , _ __---- ---- -- ~ - - -

yielding 11,866.1 gallons, which was rounded up to 12,000 gallons. As a result of the addition of 2.5 weight % boric acid from the 8AMT, a feed-and-bleed is not required to maintain the shutdown margin of 3.5%

delta k/k. Table 2-37 thew: how this AWT volume was calculated.

A plant cooldewn using water from the RWT alone is discussed in Section 2.4.5 of this report. This cooldown scenario provides the minimum RWT water volume requirement for plant cooldown considerations of 35,000 gallons. This number is contained in Technical Specification Bases 3/4.1.2.

2.6 RESPONSE TO REVIEW QUESTIONS This Section of the report details the responses to the typical quastions asked during the review of the Technical Specifications.

Question 1: What are the uncertainties and conservatism associated with the two curves shown in Figure 2-5 of this report?

Response to Question 1:

The lower curve in Figure 2-5 of this report rer'esents an upper bound on

! the minimum concentrations required to be present in the reactor coolant

system for a required shutdewn margin at the indicated temperatures. In the computer analyses that were performed to generate these curves, appropriate analytical and measurement uncertainties as well as appropriate conservati*9 were included to ensure that an upper bounding curve was obtained. The major uncertainties and conservatism that were factoredjntotherequiredshutdowncurveofFigure2-5wasasfollows

l 1. Initial scram is assumed to take place from the hot full power PO!L l (power dependent insertion limit) to all rods in, with the worst case rod stuck in the full out positica.

l

2-25 l

I

2. A bias of -9% and uncertainty of 13% was applied to the scram worth for the Unit 2 data.

3. A combined bias and uncertainty of 10% was applied to the moderator data.

4. A bias of 15% and an uncertainty of 15% was applied to the Doppler data. '

$. The assumption that the cooldown begins at 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months is conservative in relation to the buildup and decay of Xenon. !

Since appropriate analytical and measurement uncertainties as well as appropriate conservatism associated with the analysis were factored into the lower curve in Figure 2-5, it is not necessary to factor any i additional uncertainties or conservatism directly into the upper curve '

shown in that figure. Although no additional uncertainties were included t in the upper curse, the cooldown scenario followed by the operator was specifically chosen to be conservative such that the actual concentration curve in Figure 2-5 in effect represents a lower bound on the boron concentration that can be achieved by an operator given a certain boric acid makeup tank (BAMT) level and boron content. Specifically, '

conservatism in the cooldown scenario was insured in two ways. First, I the cooldown was conducted assuming a constant pressurizer level, i.e., [

plant operators charged to the reactor coolant system only as necessary !

to makeup for coolant contra.ction. As s result, boron concentration in i the reactor coolant system can be increased above the upper curve in Figure 2-5 by over-charging during the cooldown process, i.e., charae in excess of,the makeup required for coolant contraction by allowing pressurizer level to increaser. Second, the BAMT volumes obtained in >

Table 2-8 through Table 2-32 of this report were rounded up to the nearest 50 gallons and 500 gallons were added in order to g'ive the final ,

results that appear in Figure 2-6. Boron concentration in the reactor 2-26

coolant system, therefore, can be increased further since more inventory is available in the BAMis than that used to generate the actual concentration curve in Figure 2-3.

Question 2: What are the implications of a reduction in boric acid makeup tank concentrations with respect to plant emergency procedures and Combustion Engineering's Emergency procedure Guidelines?

Response to Question 2:

As stated in Section 3.2 of this report credit is not taken for boron addition to the reactor coolant system from the boric acid makeup tanks for the purpose of reactivity control in the accidents analyzed in Chapter 15 of the plant's Final Safety Analysis Report. The response of an operator, therefore, to such events as steam line break, overcooling, boron dilution, etc., will not be affected by a reduction in BAMT concentration. In particular, the action statements associated with '

Technical Specification 3.1.1.2 require that boration be commenced at greater than 40 gallons per minute using a solution of at least 1720 ppm boron in the event that shutdown margin is lost. Such statements are conservatively based upon the refueling water tank concentration and are therefore independent of the amount of boron in the BAMTs.

Similar to the Technical Specification action steos in the event of a '

loss of shutdown margin, the operator guidance in' Combustion Engineering's Emergency Procedure Guidelines (EPGs), CEN-152, Rev. 2, are ;

also independent'of specific boron concentrations within the boric acid makeup.t3mks. Specifically, the acceptance criteria developed for the i reactivity control section of the Functional Recovery Guidelines of I

CEN-152 are based upon a baron addition rate from the chemical and volume control system of 40 gallons per minute without reference to a particular I

2-27

P boration concentration. The reduction in boron concentration within the boric acid makeup tanks therefore has no impact on, and does not change, the guidance contained in the EPGs.

Question 3: Under natural circulation conditions, show that boron mixing in the reactor coolant system is rapid enough to ensure tn'at proper shutdown margin is maintained during a safe shutdown. What is the effect of various cooldown rates on the mixing process? If an operator charges only as necessary to makeup for coolant contraction, what is the impact of pressurizer level instrument errors on boron concentration?

Response to Question 3:

As discussed in Section 1.1 of this report the basic methodolo0y or procedure used to set the minimum boric acid makeup tank (BAMT) level and concentration for Modes 1, 2, 3, ad 4 is derived from the safe shutdown requirements of Branch Technical Position (R$8) 5-1. Specifically, sufficient dissolved boric acid is maintained in these tanks in order to provide the required shutdown' margin of Technical Specit. cation 3.1.1.1 for a cooldown from hot standby to cold shutdown conditions. Further, the methodology outlined in Section 2.0 of the report for Modes 1, 2, 3, and,4 was* developed by incorporating appropriate conservatiser to insure that the shutdown margin of 5.0% delta k/k would indeed be satisfied at each temperature during the cooldown process. '

The conservatism' includes a cooldown scenario that maximized the boration requir m nts due to xenon decay. In Section 2.0 the cooldown was not comenced until twenty-six hours after the reactor trip. This time interval allowed the post. trip xenon to peak and decay back to the pre-trip steady state value, Selecting the 100 cooldown rate of 12,5 2-28

9 degrees per hour maximized the xenon contribution to the boration requiremtnt by allowing more xenon decay during the cooldown than would have occurred if a more rapid cooldown had been conducted.

Boron mixing affects were eval uted for natural circulation cooldown conditions specified in the safe shutdown requirements of Reference 4.4. '

Just prior to event initiation, the plant is operating at 100% of rated thermal power. Previous operating history is such as to davelop the

, maximum core decay heat load. At time zero, event initiation occurs and offsite power is lost. The reactor coolant pumps deenergize causing a reactor trip, and the plant goes into natural circulation. All r non-safety grade equipment is lost, including letdown, and one diesel j

generator fails to start. The plant is held at these conditions in hot standby for four hours, at which time a cooldown to cold shutdown is !

cominced. (Section 5.4 of CEN-201(S), Supplement No. 1, contains a computer simulation of the safe shutdown scenario of Reference 4.3 and shows these events),

il l The exact boration requirements that give a 5.0% shutdown margin for

these scenarios are shown in F,igure 2-7. (These curves were obtained

] using conservative core physics parameters. Note that the above shutdown curves in these figures are based upon a 100 degree per hour cooldown

] rate. A cooldown rate of 100 degrees per hour was selected for the ,

{ foll.owing' reasons: First, a fast cooldown rate is more limiting than a l l

slow cooldown with respect to boron mixing since the slope of the r required boration curve is greater. The effect of the assumed mixing time (less than thirty minutes) would be more adverse than a cooldown at aslowercooldowhrate(seeFigure2-7). Second, a 100 degrees per hour cooldowrbrate is the maximum allowabla. For an added conservatism the l actual RCS boron concentration was derived by using BAMT concentrations {

of 2.5 weight percent. (BAMT concentrations of 2.5 weight % was selected

(

j since these are the lowest values that will be allowed by Technical

[

j Specification 3.1.2.8 and since it yields the slowest increases l

.l !

h 2-29

}

\'

in reactor coolant system concer.trations during the cooldown process).

The actual concentration curves were obtained using the methodology 1 outlined in Section 2.4 of this report and includes the following assumptions and conservatism:

1. No boron addition is credited prior to comencing plant cooldown.

(Note that one charging pump will operate imediately following plant trip in response to pressurizer level shrink as indicated in Section 5.4 of CEN 201(S), Supplement No. 1. Credit for boron '

addition, however, during this period will not be taken).

2. pressurizer volume at the start of plant cooldown equals 450 ft3 . !

2

3. Charging will be secured at the start of the plant cooldown and will i remain secured until pressurizer level has decreased by 10%. (In the methodology outlined in this report operators were assumed to ;

charge as necessary to maintain a constant pressurizer level. Note !

] that the error associated with pressurizer level is typically 1 2 percent, therefore allowing a 10 percent decrease in level before initiating charping is conservative).

i 4 Following the initial 10% decrease in pressurizar level, charging will be initiated and maintained as necessary to keep pressurizer

. 11vels constant for the remainder of the plant cooldown.

5. Complete 'and instantaneous mixing with all fluid added via the charging nozzles with the contents of the RCS and the pressurizer is assumed. (Notethatthisassumptioninrelationtoadelayinbaron r+1stng will be discussed below).

The conesntration curve that was obtained using these assumptions is show". in Figure 2-7. In order to account for the effect of a delay in t'.e boron mixing process under natural circulation conditions, the actual 2-30

i l

concentration curve in Figure 2-7 will be shifted to the right by 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . (Note that 30 minutes is consistent with the boron mixing time that was determined in CEN-259 and, in addition, is conservative since CEN-259 also indicates that significant mixing of added boron does occur prior to 30 minutes). The shift is shown in Figure 2 8. The relationship between the shifted curve and the required concentration curve is shown in greater detail in Figure 2-9 and Figure 2-10. As can be seen in Figure 2-8 to Figure 2-10, the concentrations within the I reactor coolant system for the 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months shift curves are above the '

required shutdown curve at each temperature during the cooldown.

Question 4: LP&L included boron measurement uncertainties in their ,

report. FP&L did not include them. Why?

Response to Question 4:

A baron measurement uncertainty was included in the LP&L physics data j when the natural circulation scenario assumed that the baronometer would be used to verify RCS boron concentration. A very conservative boronometer measurement uncertainty (50 ppm) was added to the RCS boran I

requirements. A review of the cooldown scenario shows that the addition ;

of boronometer measurement uncertainty to the RC3 boron requirements is

(

unaccessary. The cooldown scenario in CEN-365(L) identifies the minimum volume of BAMT water that must be addad to maintain the destred shutdown j margin throughout the cooldown. Oelivery of this quantity of BAMT water l

) will ensure that the RCS is adequately borated. The boronometer readings will not be used during the cooldown as a criteria to reduce the amount l t

of BAMT water delivered to the RCS during this cooldown. In conclusion,

(

l boronometpr measurement uncertainties need not be included in the boration requirement curves for either plant.

3 i

i i

i 2-31

1 Question 5: Explain the uncertainties and conservatism for the Scram Worth, Moderator Temperature Coefficient (MTC) and the Doppler Coefficient used in the FP&L boric acid makeup tank report.

Response to Question 5:

A bias of -9% and an uncertainty of 13% was applied to the Scram Worth data. No conservative correction was needed to the MTC curve since it was already consirtent with the Most Negative Technical Spectfication MTC limit. A combined bias and uncertainty of 10% was applied to the moderator data. The application of bias of 15% and an uncertainty of 15%

to the Doppler data is consistent with the licensing methodology used at other plants.

I Questien 6: Why is there a substantial difference between the boric acid requirements specified for St. Lucie Unit i and Unit 2?

Response to Question 6:

i The substantial difference is oue to the fact that the fuel vendors for the two units are different. C-E is the fuel vencor for Unit 2 and C-E provides the Reload Safety Analysis. C-E had all the physics cata required to determine the boration requirements, particularly the Inverse Boron Worth and the Cooldown curve.

In the case of S't. Lucie Unit 1 ANF is the fuel vendor and provides the Reload.Syfety Analysis. To perform the Unit 1 work FP&L, through AMF, provided the physics data inputs to C-E. In the analysis, it was nnted that the ANF Inverse Boron. Worth (ISW) values were significantly different than those that would be provided with C-E methodology. The ANF IBW values were conservative (i.e. the boron requirements were 2-32

greater than similar data C E w:uld generate). C-E also analyzed the Moderator Temperature Coefficient (MTC) curve provided by ANF and found it necessary to normalize the curve provided to the Most Negative Technical Specification MTC limit. This normalization was done in a very conservative manner, and it probably shows a much greater reactivity insertion due to cooldown than if the fuel vendor had done the evaluation. The normalized MTC values were conservative.

Question 7: What shutdown margin was used to generate the boron concentration requirements for Modes 5 and 67 Response to Question 7:

Although the Technical Specifications only required a shutdown margin of 3000 pcm in Modes 5 and 6, a shutdown margin of 3500 pcm was used in the calculations to generate the boron concentration requirements. The only effect is that the use of 3500 pcm changes both the initial and final concentration requirements by a constant amount. Since the difference between the initial and final requirements is due only to the moderator temperatv e coefficient, the use of 3500 pcm does not change the difference between the requirements. The requirements are conservative.

e %

s O MF e

9 2-33

t

, /.

l Table 2-1 Boric Acid Solubility in WaterIII Temperature (OegreesF) Wt, t H H l

3 3 32.0 2.52 41.0 , 2.94 50.0 3.49 59.0 4.08 68.0 4.72 77.0 5.46 86.0 - 6.23 95.0 7.12 l 104.0 8.08 1 113.0 9.12 l 122.0 10.27 l 131.0 11.55 140.0 4 12.97 149.0 14.42 154.0 15.75 167.0 . 17.91 176.0 19.10 (1) Solubility from h'echnical Data Sheet IC-14, US 8erax & Chemical CorporitTon, 3 83 J.W. .

9 9

2-,

l i _ _ - _ - - -

l i

Table 2-2 Time Frames for Determining an Overall #

AC$ Cooldwn Rate I l

Initial Hot Standby hold 4.0 hours0 days 0 hours 0 weeks 0 months !

period (*) . !

l Plant cooldown from 557 to 2.32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months 325 degrees (f) ;

i I

Hold period for cooling the 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months [

reactor vessel upper head i Plant cooldown from 325 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months j to200 degrees (f) l Additional cone 'vatism 5.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months !

Total 28.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months '

s I

l l

(*) Per the, [equirements of Iranch Technical Posittor, (ASO) 61.

i (f) Assvoe en average cooldown rate of 100 degrees per hour. I

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i Table 2 3 I 4 .

L Required Boron Concentration for a Cooldown l from 200 Degrees to 135 Degrees i

i Temperature Concentration I') I (DegreesF) (ppe boron) l 200 , 570.3 i

190 577.4

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.! i 180 584.5 i 1 i 170 591.6 l 160 598.4

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in the Modes 5 and 6 Calculation !

l a. Reactor coolant system volume = 9.394 ft3 .

b. Reactor coolant system pressure = 275 psia. !

c. Pressurizer volume = 450 ft3 . ,

i

d. Pressurizer is saturated.

l

e. Zero reactor coolant system leakage. I

f. Ooration source concentration = 2.5 weight i boron.

f l g. 8eration source temperature = 70 degrees.

h. Initial reactor coolant system concentration = 570.3 ppm t l

l 1. Initial pressurizer concentration = 570.3 ppm boron. !

j. Complete and instantaneous mining between the pressurizer and the reactor l

coolant system. (Refer to discussion on Section 2.2.4 above).

l t

k. Constant pressurizer level maintained during the plant cooldown, i.e., r charge only as necessary to makcup for coolant contraction. !

1. Total system volume (RCS + SDCS + PZR) = 19.246 ft3 . (See discussion in Section 2.3.2). }

(

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Table 2 5 (nitial Conditions and Assumptions Used in the Modes 1, 2, 3, and 4 Calculation L 1

a. Reactor coolant system volume = 9,398 ft3 .

r

b. Initial reactor coolant system pressure = 2200 psia. l

c. Pressuriter volume = 600 ft3(405 level).

1

d. Pressurizer is saturated,

e. Reactor coolant system depressurization performed as shown in Table 2-8 through Tabi? 2-32. t i

f. Zero reactor coolant system Technical Spe:ification leakage,

g. Initial reactor coolant system concentration = 0 ppe,

h. Initial pressurizer concentration = 0 ppe boron.

t

1. Complete and instantaneous mixing between the pressurizer and the reactor ;

coolant system. (Refer to discussion on Section 2.2.4 above). '

j. Constant pressurizer level maintained doeing the plant cooldown, i.e., h charge only as necessary to makeup # 1ent contraction. '

j k. Boron concentration in the SDC0 ' egos; J the boron concentration in the reactor coolant system at th :: tn, shutdown cooling initiation.

1

1. Letdown is not available.

m. RWT temperature = 50 degrees. t

n. RAMT temperature = 70 degrees.

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PLAmr Cootochar faae ssr f to 200 f; 8Asti Al s.co estt TORIC AClo; aWI AT 14so pga somos l {

[Avr. 5fs. ItseP. 1 r2a reE55 SPECIFIC WottmE SmalmEAGE tassi vot a aWI tot a s/A A80(1, lotAL S/6 ToIAL SYS. Ie455 fimE CXmC.l l *

(5) (pale) (cu.f t./ttm) senS5(Itm) ro f (set) so F (set) (Itm) ( tta) 4 In (Itm) (ppa leeren)l

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i 4as.aor.4 29r.6l sio 490 / zzee e.ezosz o.oiseo 9.763.5 i.irz.o c.o soi.9

'so i.ize.o 49s.aro.6 ses.1 I 'So zzoe e.oi9eo o.oi9m 4.r94.s sn.6 o.o isa.s su 3.2r7.5 soc. sis.4 44s.9 l l tao zzoo o.oi9in o.on944 4.430.1 o.o riz.o iss.9 s.476.t ser.442.4 i su ao 22eo e.oi944 o.otess 2.ros.s o.o ses.6i szs.s zs.9 i. sos.o 53o.372.4 I '*o 4so 22co a.oiess o.oivia 4. sis.a o.o sis.s sir.i u.i 1.s51.2 sis.ssz.s 3, oo uo 22co o.one n o.osseo 4.350.s o.o 495.i 527.1 1 44.2 1.s95.5 sia.ior.2 m i 44a . 4so 22co o.e 9eo o.oises o.o 557.7l s.92.i 4rs. 42.s i.63r.4 522.6as.4

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Table 2-16 l 5 . tuc E tas 2 l

l PLAuf CoutDonas f age 551 f IO 200 f; SANI At 2.n utt actIC ACIO; aWI AT 1850 ppe monen l

I l l awe.5T5.StuP. P2R PSE55 SPEttitC wattaeE SaRIssEAGE Sassi WOL 4 aWT WOL 4 l

l S/A ASSED 10lAL S/A TOIAL SYS. 00455 fileAL CipIC.l (f) (paio) (cu.f t.Itbe) Mass (Itse) FO f (get) 50 t (set) (the) (!he) l It li vs *

(the) (ppmheren)l vf lg.....................................................................................................................................ll 55F 55F 2200 1.00000 1.00000 0.0 0.0 0.e 0.0 0.0 454,2 2.7 l 557 510 2200 C.02157 0.02032 26.T41.7 3,210.7 0.0 85.8 l 7M.2 756.2 445,TM.5 l 510 490 ' 2200 S.82032 0.01990 9,T61.3 2T2.2 l 1.172.0 0.0 276.0 1,032.2 495,773.8 l 490 4a0 2200 0.e1990 c.s1970 4.r94.5 Sn.6 364.0 l 0.0 is).6 1,ur.s l 440 470 500.703.9 407.sl 2200 e.81978 C.01951 4,645.9 557.8 0.0 131.4 1,299.1

I '70 '60 505.481.2 449.3 l 2200 0.01951 o.01933 4,4a5.6 53a .5 0.0 iz6.a l 464 450 i.426.0 510,093.6 cas.s l 2200 0.01933 0.019 4 4,313.8 517.9 0.0 122.0 1,54a.0 l - 450 440 220G 0.01916 0.01900 514.529.3 526.0 l 4,130.5 0.0 495.1 44.2

( 1.592.1 514,704.1 SM.6 l ru l 440 433 2200 0.01900 0.01885 3,92.1 0.0 471.5

{ 1. 42.1 1,634.2 522.682.2

l 450 420 2200 0.0:ss5 0.01aro 3,999.2 546.6 l 0.0 4n.3 42.s 1.6rr.0 526,r24.2 I 420 410 2200 0.01aio 0.01 55 4.063.9 0.0 Sw.6 1 tar.1 43.5 1,r20.5 530 s31.5 l Sie 4o0 2200 0.01:55 0.0im2 3,5n.6 0.0 42s.6 3s.2 u6.7l 1,r5a.r 534.445.3 l a0 390 22ee 0.eia42 0.0iaza 3,907.5 0.0 44s.4 5n.3 l 4t.a 1,e0s.5 53s.3m.6 l 390 see 22a0 0.0ia2s 0.01:16 3,397.2 0.0 5m.7 l 407.2 m.3 1.au.a 541.s2s.2 l 3e0 370 2200 0.01su 0.01am 3,442.4 592.7l j 370 0.0 4t2.6 x.a 1,sr3.7 545.307.4 600.r l 360 2200 0.01a04 0.0in2 3,4as.5 0.0 41s.1 37.3 i,91i.0 54s,a33.3 l 360 350 2200 0.01n2 0.01781 3.239.1 0.0 60s.al 30s.2 34.6 1,945.6 552,10T.0 l 350 340 2200 0.011:1 0.01770 3,2n.4 0.0 3e3.1 35.1 64.1l 1,9ee.r 555.421.5 l 340 350 2200 0.0iriO 0.01no 3,320.4 0.0 ses.s 623.5 l 35.5 2,0n.2 55s.rrr.4 l 330 325 2200 0.01n'7 0.01n4 1,523.0 0.0 630.sl 182.6 M.3 l 325 310 2i5 0.01ns 0.01n4 2.032.5 M0.34.7 634.2 l 0.0 0.0 e.s 0.o 310 2.e32.5 56e.n3.s 623.6 l l 300 215 0.01154 0.01744 3.072.3 0.0 36s.2 32.9 2.065.3 572.80s.9 l 300 260 215 0.01744 0.01707 11,680.4 0.0 630.3 l 1.400.0 124.9 2,100.3 544,704.2 l 264 235 215 0.0170F 0 01687 6,527.0 0.0 654.9 l 7:2.3 69.4 2,260.1 591,301.0 l 235 210 2F5 0.01687 0.w1669 6.00s.1 0.0 T20.1 64.3 668.3 l 2,324.3 59T.373.4 680.3 ,

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l lAWG.5TS.ILW.

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. 5.956.i o.o s, m .5 y . l sso 42o 22co o.osses e.otaio 5.999.2 o.o 4ri.e 479.5 45.s u.s i.azs.6 522.627.5 526.672.s 52s.5 l 559.6 t 1 42o 4to 22eo o.oisio o.oisss 4.o65.9 o.o 4sr.: 47.o i.siz.6 sio.rss.r l 4to soo z2co a.otass o.oiss2 sso.9 l 5.sn.6 o.o sr..a 41.4 1 ri4.o 554.40s.4 56o.7l 1 soo sen zzoo o.oissz o.oiazs 3.9o7.5 o.o 4a.4 45.2 t.ne.2 ssa.sss.3 571.5 g l 590 sao 220o o.otazs o.oisi6 5.397.2 o.o 4er.2 59.5 i.79s.s

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Table 2-33 .

Required Boron Concentration for a Cooldown from 557 De9rees to 200 Degrees Temperature Concentration (Decrees F) (ppm boron) 557 -71.2 510 133.0 490 203.0 ;

480 235.5 470 262.3 460 289.8

450 314.1 i

440 338.0 430 360.6 420 382.0 410 403.4 400 423.9 390 443.0 380 461.2 370 474.5 ,

360 488.7 350 500.9 340 512.6 330 523.5 i

325 528.7

. 310 543.6 ;

300, 568.8 260 589.9 ;

235 N 608.7

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\

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Note: After Shutdcwn margth change from 5.0%, delta k/k to 3.51 delta k/k. f

- Note: The boracion requirement for a 3.51 shutdown margin and core is xer.on free, t

2-66 l

Table 2-34 r

i Minimum Boric Acid Makeup Tank Boration Volume vs. !

Stored Boric Acid Concentration for Modes 1, 2, 3, and 4

. Minimum Volume (callons)

BAMT RWT at RWT at RWT at RWT at RWT at Co, n,3, 1720com 1850 com 2000 com 2150 com L300 com 3.5 4.842.2 4,554.1 4,144.3 3,732.0 3,325.7 3.25 5,403.6 5,069.0 4,669.0 4,203.7 3,732.0 L 4

3.0 6,106.0 5,730.3 5,347.6 4,784.4 4,263.2 i

2.75 6,968.6 6,572.5 6,106.0 5,569.5 5,013.6 t

2.5 8,118.1 7,732.2 , 7.256.6 6,720.4 6054.6 P

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Table 2-35 Minimum Stored Boric Acid Makeup Tank Volume vs. Stored Boric Acid concentration for Modes 1, 2, 3, and 4 Minimum Volume (callons)

BAMT RWT at RWT at RWT at RWT at RWT at Cone 1720 com 1850 co_m 2000 com 2150 com 2300 com 3.5 5,350 5,100 4,650 4,250 3,850 3.25 5,950 5,600 5,200 4,750 4,250 3.0 - 6,650 6 250 5,850 5,300 4,800 2.75 7,500 7,100 6,650 6,100 5,550 2.50 8,650 8,250 7,800 7,250 6,600 1

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Table 2-35 ,

Calculation of the 16,0JO Gallor. Volume In Specification 3/4.1.2 12,281.0 gallons Cooldown to 325 degrees and 275 psia (Part A)

+B,235.1 Cooldown to 200 degrees on shutdown cooling (Parts 8 & C) 15.350.0 Smallest 8AMT inventory value for 1720 ppm Boron in the RWT from Table 2-35 15,166.1 gallons Total 16,000.0 gallcns Total rounded up to the nearest 1000

! gallons 4

S 1 e 2-69 i

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Table 2-37 Calculation of the 12,000 Gallon Volume :

In Specification 3/4.1.2 i

12,281.0 gallons cooldown to 325 degrees and 275 psia I (Part A)

+8235.1 Cooldown to 200 degrees on shutdown cooling (Parts B & C)

-8,650 Greatest BAMT inventory value for

~

t 1720 ppm Boron in the RWT from i Table 2-35 i i

i 11,866.1 gallons Total +

12,000 gallons Total rounded up to the nearest 1000 '

gallons {

t I

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4 2-70

f Table 2-38 Calculation of the 35,000 Gallon Volume j

In Specification 3/4.1.2 for St. Lucie 1 14,080 gallons System feed-and-bleed prior to cooldown '

+12.281.0 Cooldown to 325 degrees and 275 psia (Part A)

, + 8.235.1 Cooldown to 200 degrees on shutdown I

cooling (Parts B 4 C) t 4

l 34,615.1 gallons Total I Final volume rounded up to the 35,000 gallons nearest 1000 gallons.

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3.0 OPERATIONAL ANALYSIS ,

3.1 INTRODUCTION

TO THE OPERATIONAL ANALYS!$

The remaining Sections of this report present the results of an evaluation performed in order to demonstrate the general impact on plant operations of a reduction in beric acid makeup tank concentration. The s specific areas that will be discussed include operator response to '

emergency situations, typical plant feed-and-bleed c;,erations, typical plant blended makeup operations, plant shutdown to refueling, and plant shutdown to cold shutdown. Because it is obviously an impossible task to evaluate each of these five areas and consider all possible corbinations of plant conditions, initial plant parameters and analysis assumptions that were used in the evaluation were selected, where possiblet in a conservative manner in order to give worst case type answers. As a consecuence, the results, i.e., the volumes and final concentrations that were obtained, should in general be bounding for any event or any set of initial plant :enditions.

3.2 RESPONSE TO EMERGENCY $!TUATIONS In general, credit is 'not taken for boron addition to the reactor coolant system from the boric acid makeup tanks for the purpose of reactivity control in' the accidents analyzed in Chapter 15 of the plant's Final Safety Analysis Report. The response of an operator, therefore, to such events as steam'line break, overcooling, boren dilution, etc., will not be affected by a reduction in boric acid makeup tank concentration. In particular, the action statements associated with Technical Specification 3.1.1.1-ud Technical Specification 3.1.1.2 require that boration be connerced at greater than 40 gallons per minute using a solution of at least 1720 ppm boron in the event that shutdown margin is lost. Such statettents are conservatively based upon the refueling water tank 3-1 i

concentration and are therefore independent of the amount of boron in the BAMis. In addition, the acceptance criteria developed for the Reactivity Contrcl Section of the Functional Recovery Guidelines of Reference 4.2 are based upon a boron addition rate of 40 gallons per minute and are also independent of the exact boration source concentration.

3.3 FEED-AND-BLEED OPERATIONS During a feed-and-bleed operation to increase system boron content, the charging pumps are used to inject concentrated boric acid into the RCS with the excess inventory normally being diverted to the liquid waste system via letdown. The rate of increase in boron concentration is proportional to the difference between the system concentration at any given time and the concentration of the charging fluid. From this basic relationship, an equation describing feed-and bleed can be derived.

(Appendix 1 contains the derivation of the reactor i;oolant system feed-and-bleedequation). In general, if the concentration within the boric acid makeup tanks is reduced to the point where heat tracing is no longer required, the maximum rate of change of RCS boren concentration that an operator can expect to see during feed-and bleed will be less than currently achievable.

The purpose of the evaluation perfomed in this section of the report was to show the exact feed-and bleed rates that can be expected using boric acid makeup tanks having a reduced concentration. The analysis was done assuming hot zero power conditions with other key parameters and conditions shown in Table 3-1. Both a one charging pump and a two charging pump fee'd-and-bleed were evaluated from two initial system concentra3 tons: zero ppm and 800 ppm. The results are presented in 3-2

i Table 3 2 to Table 3 5. Equation 9.0 of Apper. dix 1 was used to generate the results in these tables. The value of the system mass used to obtain the time constant in Equation 9.0 was calculated as follows for St. l.ucie 2:

I*w)ACS*I*w) loops *I"w)PZR or 9,398 ft 3 450 ft 3 0.020854 ft.3/ iM 0.02669 ft3 /lbmW From this system mass (477,626.2 lbm), the value of the feed-and-bleed time constant for one charging pump is T 467.517.2 lbe 40 = 40 gpm x 8.329 lbm/ gallonW or T40 = 1.40).3 min.

and the value of the feed-and bleed time constant for two charging pumps is ,

467.517.2 lbe 84 84 gpa x'8.329 lbs/ gallon or

-- T 668.2 min.

84 =

(1) Specific volume of compressed water at 532 degrees and 2200 psia.

(2) Specific volume of saturated' water at 2200 psia.

(3) Water density it 70 degrees. ,

3-3

Several of the concentration results shown in Table 3-2 through Table 3-5 are plotted in Figures 3-1 and 3-2 for comparison. Note that significant feeJ-and-bleed rates will be achievable following the reduction in boric acid makeup tank concentration levels.

3.4 BLENDED MAKEUP OPERATIONS

. During typical plant blending operations, concentrated boric acid via FCV-2210Y is mixed with dominera112ed water via FCV-2210X at the blending l, tee and then added to the volume control tank. Since the ability to j blend and add makeup to the reactor coolant system and to other systems is important to plant operations, three different parametric studies were performed in crder to demonstrate the effect of a reduction in boric acid l makeup tank concentration. The studies performed were as follows:

1. Flow through FCV-2210Y is varied between 0.5 gpm and 15.0 gpm while l the flow through FCV-2210X is varied to give a total flow out of the blending tee of 44 gallons per minute.

l

) 2 Flow through FCV-2210Y is varied between 0.5 gpm and 15.0 gpm while l the flow through FCV-2210X'is varied to give a total flow out of the blending tee of 88 gallons per minute.

l l 3. Flow through FCV-2210Y is varied between 0.5 gpm and 15.0 gpm while the flow through FCV-2210X is varied to give a total flow out of the blending te'e of 132 gallons per minute.

1 In each of the thr'te studies, the temperature of the boric acid makeup tank and the temperature of the domineralized water supply was assumed to be 70 degrees. The results are shown in Table 3-6 through Table 3-8. The

{ final concentration out of the blending tee in each of these tables was

) obtained using the following' equation:

l 3-4 I

(F .C)

C out * (Fy . Cy ) { (F out . Dw)(100)(1748.34).

out is the concentration coming out of the blending In this equation C tee in ppm boron, Fjis the flowrate coming out of CH 0210Y in gr.11cns per minute, Cy is the concentration of the boric acid makeup tanks in Iba per gallon, Fout is the total flow coming out of the blending tee in gallons per minute. 0, is the density of water at 70 degrees in Ibm per gallon, and 1748.34 is the conversion factor between concentration expressed in terms of weight percent boric acid and concentration expressed in terms of ppm boron. (See Appendix 4 for a derivation of this conversion factor). The data contained in Tables 3-6, 3-7, and 3 8 is plotted in Figure 3-3 through Figure 3-5. Note that following the j reduction in BAMT concentration, a full rangt of flowrates and boron ,

concentrations are available for blended makeup operations.

3.5 SHUTDOWN TO REFUELING - MODES 6 The plant shutdown to the refueling is typically the most limiting evolution that an operator must perform with respect to system boration, ,

i.e., this evolution normally requires the mastmum amount of boron to be added to the reactor coolant system. A shutdown to refueling normally occurs at the end of core cycle when the critical boron concentration is low and requires an increase to the refueling boron concentration. In the most' limiting case, baron concentration must be raised from zero ppm to the present' refueling concentration of 1720 ppm.

This section presents the evaluation results of a plant shutdown to ;

refuet Tg. The evaluation was performed specifically to demonstrate the effect on rakeup inventory requirements of a reduction in boric acid storage tank concentration. A list of key parameters and conditions assumed in the analysis is' contained in Table 3-9. The evaluation was 3-5

cerformed for end-of-cycle conditions in order to maximize the amount of boron that must be added to the reactor coolant system. As a result, the boron concentration within the RCS was required to be increased from zero ppm to the present refueling concentration of 1720 ppm. The shutdown for refueling was assumed to take place as fo11ews:

1. The reactor is shutdown via red insertion to hot zero power condittons.

2. Following shutdown, at time zero, operators comence system feed-and-bleeds for both plants using three charging pumps and the boric acid makeup tanks. (BAMT concentration is assumed to be 3.5 weightpercentboricacid).

i

3. The feed-and-bleed is conducted for 40 minutes, after which time ,

it is secured.

4 A plant cooldown and depressurization is coerenced from an average coth nt temperature and system pressure of f32 degrees and 2250 psia to an average coolant temperature and systen pressure of 325 degrees and 275 pd a. An overall cooldown rate of approximately 100 degrees per hour is assumed. Makeup inventory is supplied from the boric acid makeup tanks.

5. The shutdown cooling system is placed in operation at 325 degrees and 275 psi'a, (Prior to initiation, the concentratt'n within the SDCS is assumed to be equal to the concentration Sri se reactor coolantsystem).

6. The plant cooldowns are c'ontinued follo. sing shutdown cooling initiation frem 325 degrees to 135 degrees at 275 psia. A rate of 100 degrees per hour is' assumed over the whole temperature range.

3-6

o Evaluation results showing the system concentrations as a function of time and total beric acio makeup tank inventory requirements are !

contained in Table 3-10. Loop average temperature and system baron !

concentration data from this table is plotted in Figure 3-6. I Concentrations during the initial feed-and bleed operation was calculated using the methodology discussed in Section 3.3 above. Concentrations i-during the subsequent plant cooldown were calculated in the same manner f

as the concentrations for the plant cooldowns in Section 2.4. Note that !

the boron content of the RCS was raised from Zero ppm at the start of the evaluation to greater than 1720 ppm by the time the plants had been '

cooled and depressurized to 135 degrees and 275 psia. A total volume of i 23,085.0 gallons of a 3.5 weight percent boric acid solution was required. Of this volume, 5120 gallons were used during the initial i forty minute plant feed and bleed operation, and 17,965.0 gallons were i I

charged into the system to compensate for shrinkage during the cooldown process.

As can be seen from the results in Table 3-10, the volume of a 3.5 weight percent boric acid solution that is required in order to perfom the shutdown to refueling is approximately 2.3 times the capacity ct one i beric acid makeup tank. Nott'that this result is conservative or f bounding, and therefore, represents the maximum volume that would be {

required to be available assuming a refueling concentration of 1720 ppm

{

boron an( a boric acid makeup tank concentration of 3.5 weight percent l boric acid. Since there are only two boric acid makeup tanks in each !

plant, with the combined capacities of approximately 19,950 gallons, additional provisions or operator actions are required in order to place the plant in Mode 6. These provisions could include some combination of the fo,ll,owing:

1. The initial plant feed-and-bleed and some portion of the plant cooldown eculd be performed using the refueling water tank. This would decrease the amount of inventory needed from the boric acid makeup tanks. -

3-7

2. Prior to conducting the evolution, both boric acid makeup tanks are full and available for use.

3. During the initial part of the evolution, charge from one boric acid makeup tank until depleted, then transfer to the second PAMT.

Concurrent with continued cooldown, replenish inventory in the first tank.

These provisions, or operator actions, would need to be considered only once during core cycle, just prier to conducting a shutdown for refueling. Note that they are relatively simple actions that should be well within the current plant operating procedures. In addition, they can be planned for in advance so as to have no impact on maintenance activities or the plant refueling schedule.

3.6 5HUTDOWN TO COLD SHUTDOWN - MODE 5 As di: cussed in the previous Section, the shutdown to refueling is the most limiting evolution that an operator must perfom with respect to system boration. This evolution is nomally performed once during a fuel cycle just prior to refueling. Situations (such as unscheduled plant maintenance, etc.) can occur during a fuel cycle, however, and require that an operator perform a plant shutdown to cold shutdown conditions.

Although not limiting with respect to boration requirements, it is-important for an operator to be able to perfom such a shutdown quickly and efficiently.'-

This section pres'ents the evaluation results of a plant shutdown to cold shutdowou.The analysis was performed specifically to demonstrate the effect on makeup inventory requirements of a reduction in boric acid storage tank concentration.. A list of key parameters and conditions assumed in the analysis is centained in Table 3 11. In addition to the parameters in Table 3-11, the evaluation was performed for end of-cycle 38

conditions assuming a cold shutdown concentration of 800 ppm boron. As a result, boron concentration had to be increased from zero ppm to 800 ppm boron. The operator scenario employed in the shutdown to cold shutdown t is as follows:

i

1. The reactor is shutdown to hot zero power conditions via rod insertion.

2. A plant cooldown and depressurization is imediately comenced from an average coolant temperature and system pressure of 532 degrees and 2200 psia to an average coolant temperature and system pressure of 325 degrees and 275 psia. An overall cooldown rate of approximately 100 degrees per hour is assumed. Makeup inventory is supplied from the boric acid makeup tanks.

3. The shutdown cooling system is placed in operation at 325 degrees and 275 psia.

4 The plant cooldown is continued following shutdown cooling l initiation from 325 degrees to 135 degrees at 275 psia. Makeup i inventory is supplied from the beric acid makeup tanks, i Evaluation results showing the system concentrations as a function of time and total boric acid makeup tank inventory requirements are contained in Table 3-12 and Table 3-13. Note that two cases were analyzed for coeparison. In Case I the concentration within the shutdown cooling system was assumed to be equal to the concentration of the t

reactor coolant systee) at the time of shutdown cooling initiation. In ;

Case !! the concentration within the shutdown cooling system was assumed '

to be equal to the cencentration of th:, refuelfng water tank at the time l

of shutdown cooling initiation. System boren concentration data from these two tables are plotted in Figure 3 7 and Figure 3-8. f Concentrations during the plant cooldown were calculated using the !

, [

3-9 i

r

methodology discussed in Section 2.4. During those portiens of the plant cooldown in which blended makeup was used, data was calculated using the methodology contained in Section 3.4.

A total volume of 10,243.7 gallons of a 3.5 weight percent boric acid solution were required in order to perfom the shutdown tu cold shutdown for the case in which the concentration of the fluid within the shutduwn cooling system was assumed to be equal to that of the reactor coolant system at the time of shutdown cooling initiation. In the case where the concentration within the shutdown cooling system was assumed to equal that of the refueling water tank at the time of shutdown cooling initiation, a total volume of 7248,1 gallons was required. Note that approximately 2995.6 gallons less of the boric acid makeup tank inventories were required to be used in the Case !! cooldown. Since the plant operating procedures require that the shutdown cooling system be operated via recirculation with the refueling water tank prior to initiation, the concentration within that system will nomally be very near that of the RWT any time that the shutdown cooling system is placed in operation.

l 3.7 LONG TERM COOLING AND CONTAINMENT SUMP pH l

The impact of the Boric Acid Reduction Effort on post LOCA long tem cooling and containment sump pH control was reviewed. Each analysis is discussed qualitatively below.

Perfomance of the Emergency Core Cooling System (ECCS) during extended periods of time following a loss-of-coolant accident (LOCA) was analyzed in Sectly 6.3.3.4 of the St. Lucie 2 FSAR. Long tem residual heat removal is accomplished by continuous boil-off of fluid in the reactor vessel. As borated water is delivered to the core region via safety injection and virtually pure water escapes is steam, high levels of boric acid may accumulate in the reactor vessel. As an input to this analysis, e

3-10

t l

f boricacidmakeuptank(BAMT)boronconcentrationwasassumedtobe12 !

weight percent. This calculation conservatively bounds the maximum boric l i

acid makeup tank boron concentration of 3.5 weight %.

i A detailed calculation will be perfomed by Florida Power and Light l Company to detemine the effects of boric acid concentration reduction on l

. the post LOCA sumpN P and containment sprayN P . This evaluation will be j conducted to determine if the hydrazine addition rate or total quantity injected by the containment spray system needs to be changed to maintain f the sump and containment spray within the NP ranges specified in the St. f Lucie Unit 2 FTAR. Two boundary cases are provided for this review and l 1 are listed below: (

i Minimum BAMT Boric Acid 4,850 gallons of 3.5 weight 5 i contribution boric acid solution i

Maximum BAMT Boric Acid 19,950 gallons of 2.5 weight 5 ;

contribution boric acid solution [

l !

l I

i i !

I l

i I s [

l t

I j

L l !

3-11 l

(

l I

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7 i

i Table 3-1 r

Key Plant Parameters and Conditions Assumed in Generating the Feed and-Bleed Curves

a. Reactor coolant system volume = 9.398 ft3 .

b. Reactor coolant system pressure = 2200 psia. '

c. Reactor coolant system average temperature = 532 degrees,

d. Pressurizer N1ume = 450 ft3 .

e. Pressurizer is saturated.

i

f. Zero reactor coolant system Technical Specification leakage,

g. Boric acid makeup tank temperature = 70 degrees.

h. Complete and instantaneous mixing between the pressurizer and the reactor coolant system.

i. . Constant pressurizer lavel maintained during the feed and bleed ,

process.

j. Letdown flowrate from one charging pump = 40 gpe, t s

i

k. Lejdyn flowrate from two charging pumps = 84 gpm.

l 3 12

'm .

Table 3-2 Feed-and.81eed using One Charging Pump from an

!altial RCS Concentratten of 0 ppm Beren

[.

5t. Lucie #2 ACS Boren Concentration (ppm boren) l SMT at BMT at SMT at SANT at RANT at SANT at Time (ein) 0.98 wt 1 2.58 wt 1 2.75 wt 1 3.00 wt 1 3.25 wt 1 3.50 wt Z 10' 12.2 31.0 34.1 37.2 40.3 43.4 w 20 24.3 61.9 68.0 74.2 80.4 86.6 0 30 36.4 92.5 101.7 110.9 120.2 129.4 40 44.3 122.8 135.1 147.4 159.7 172.0 '

50 60.2 153.0 168.3 183.6

. 198.9 214.2 60 72.0 182.9 201.2 219.5 237.8 256.1 70 83.7 212.1 234.0 255.2 276.5 297.7 80 95.3 242.2 266.4 290.6 314.9 339.1-90 106.5 271.5 298.7 325.8 353.0 300.1 100 118.3 300.6 330.7 360.9 390.4 420.9 110 129.7 329.5 362.5 395.4 425.4 #1.3 120 141.0 358.2 394.1 429.9 #5.7 501.5 9

Table 3-3 feed-anJ.31eed using Two Charging Pumps from an Initial RCS Concentration of 0 ppa Soron St. tweie #2 I. .

RCS Borne Concentration (ppm 6. roc)

SANT at SANT at BANT at SAMT at .M a t BANT at Time (min) 0.98 wt 1 2.50 wt 1 2.75 wt 1 3.00 wt 1 3.25 wt Z 3.50 wt 1 I

10 * ?$.5 64.9 71.4 77.9 84.4 90.9 y ~

20 50.7 128.9 - 141.8 154.7 167.5 180.4

% 30 75.5 191.9 211.1 230.3 249.5 268.6 40 99.9 254.0 279.4 304.8 330.2 355.5 50 124.0 315.1 346.6 378.1 409.7 441.2 1

60 147.7 375.4 412.9 450.4 488.0 525.5 l 70 171.1 434.7 478.2 521.7 565.1 608.6 80 194.1 493.2 542.5 591.8 641.1 690.4 90 216.7 550.8 605.9 660.9 716.0 771.I l 100 239.1 607.6 668.3 729.0 789.8 850.5 l 110 261.1 663.5 729.8 796.1 862.4 928.8 120 282.7 718.5 790.4 862.2 934.0 1005.9

I t

i Table 3-4 11 l

! Feed-and-Bleed Using One Chars 4 Pumps from an -

i Initial RCS Concentration of 800 ppe Boron i

St, Lucie #2 i

L. .

RCS Boron Concentration (ppa boron)

BMT at BMT at BAMT at BMT at BAMT at BMI at f Time (min) 0.98 wt % - 2.50 st % 2.75 wt 1 3.00 wt 1 3.25 wt % 3.50 wt 1 10 ' . 806.5 825.3 828.4 831.5 834.6 837.7 m 20 813.0 850.6' 856.7 862.9

' 859.1 875.3 h

30 819.5 675.6 884.8 394.0 903.3 912.5 40 825.8 900.3 912.6 924.9 937.2 949.5 50 832.2 925.0 940.3 955.6

~

9/'0.9 986.2 60 838.5 949.4 967.7 986.0 1004.3 1022.6 70 844.8 973.8 995.1 1016.3 1037.6 1058.8 80 851.0 997.9 1022.1 1046.3 1070.6 1094.8 90 857.1 1021.8 1049.0 1076.1 1103.3 1130.4 100 863.3 1045.6 1075.7 1105.8 1135.8 1165.9 110 869.4 1069.3 1102.2 1135.I 1168.I 1201.0 120 875.4 1092.6 1128.5 1164.3 1200.I 1235.9

. c Table 3-5 Fe M-and-Bleed using Two Charging Pumps from an Initial RCS Concentration of 800 ppe Boron St. Lucie #2 RCS Boron Concentration (ppm boron)

/

BAMT at BAMT at BAMT at BAMT at BAMT at BAMT at Time (min) 0.98 wt 1 2.50 wt % 2.75 wt % 3.00 wt % 3.25 wt % 3.50 wt %

10- ,

813.6 853.0 859.5 866.0 872.5' 879.0 m , 20 827.1 905.5 918.2 931.1 943.9

~ 956.8 k 30 840.4 956.9 976.0 995.2 1014.4 ' 1033.5 40 853.4 1007.5 1032.9 1052.3 1083.1 1109.0 50 866.3 1057.4 1088.9 1120.4 1152.0

. 1183.5 60 879.0 1006.7 1144.2 1161.7 1219.3 1256.8 70 891.5 1155.1 1198.6 1242.1 1285.5 1329.0 80 903.8 1202.9 1252.2 1301.5 1350.8 1400.1 90 915.9 1250.0 1305.1 1360.1 1415.2 1470.3 100 927.9 12 % .4 1357.1 1417.8 1478.6 1539.3 I 110 939.7 1342.1 1408.4 1474.7 1541.0 1607.4 120 951.2 1387.0 1458.9 1530.7 1602.5 1674.4 i

i

'I I

i

Table 3-6 Typical 81 ended Makeup Operations at 44 gpa out of Blending Tee L

Concentration Out of Tee (ppe boron)

Flow (gps) / BAMT at BAMT at BAMT at BAMT at BAMT at FCV-2210Y FCV-22101 2.50 wt % 2.75 wt % 3.00 wt % 3.25 wt % 3.50 wt %

O.5 43.5 50.9 56.2 61.4 66.7 72.0 1.0 ' -

43.0 101.8, 112.3 122.8 133.4 144.0 y .' 1 5 42.5 152.7 168.4 184.I 200.0 215.9 C 2.0 42.0 203.5 224.4 245.4 266.6 287.0 3.0 41.0 305.1 336.4 367.9 399.5 431.3

. 4.0 40.0 406.6 448.3 490.2 532.3 574.6 5.0 39.0 507.9 560.0 612.3 664.9 717.6 6.0 23.0 609.2 671.6 734.3 797.2 860.4 7.0 37.0 710.3 783.0 856.0 929.4 1003.0 8.0 36.0 811.3 894.3 977.6 1061.3 1145.4 9.0 35.0 912.2 1005.4 1099.1 1193.1 1287.5 10.0 34.0 1012.9 1116.4 1220.3 1324.7 1429.4 15.0 29.0 1515.0 1669.3 1824.2 1979.5 2135.4

. ~ , _

. T

'C Table 3-7 Typical Blended Makeup Operations at 88 gpm out of Blending Tee I. .

Concentration Out of Tee (ppe boron)

. Flow (gpm) / BAMT at BAMT at 8 ANT at BAMT at BAMT at

~

FCV-2210Y FCV-2210X 2.50 wt % 2.75 wt 1 3.00 wt % 3.25 wt % 3.50 wt 1 0.5 87.5 25.5 28.1 30.7 '83 . 4 36.0 1.0 ' 87.0 50.9 56.2 61.4 66.7 72.0 y ; 1.5 86.5 76.4 84.2 92.1 100.I 108.0 E 2.0 86.0 101.8 112.3 122.8 133.4 144.0 3.0 85.0 152.7 168.4 184.1 200.0 215.9 4.0 84.0 203.5 224.4 245.4 266.6 287.8 5.0 83.0 254.3 280.4 - 306.7 333.1 359.6 6.0 82.0 305.1 336.4 367.9 399.5 431.3 7.0 81.0 355.9 392.4 429.1 465.9 503.0 8.0 80.0 406.6 448.3 490.2 532.3 574.6 9.0 79.0 457.3 504.2 551.3 598.6 646.1 10.0 78.0 507.9 560.0 612.3 664.9 717.6 15.0 73.0 760.8 838.7 916.9 995.4 1074.2

Table 3-8 Typical Blended Makeup Operations at 132 gpm out of Blending Tee /

(~

Concentration Out of Tee (ppe boron)

Flow (gpm) / BAMT at BAMT at BAMT a t BAMT a t BAMT at

FCV-2210Y FCV-2210X 2.50 wt % 2.75 wt 1 3.00 wt %, 3.25 wt % 3.50 vt %

0.5 131.5 17.0 18.7 20.5 22.2 24.0 1.0' -

131.0 34.0 37.4 41.0 44.5

_ 48.0 y 2.0 130.0 67.9 74.9 81.9 88.9 96.0

< G 3.0 129.0 101.8 112.3 122.8 133.4 144.0 4.0 128.0 135.7 149.7 163.7 177.8 191.9

. 5.0 127.0 169.6 187.1 204.6 222.2 I

239.9 6.0 126.0 203.5 224.4 245.4 266.6 287.8

! 7.0 125.0 237.4 261.8 286.3 310.9 335.6 8.0 124.0 271.3 299.1 327.1 355.2 383.5 9.0 123.0 305.1 336.4 367.9 399.5 431.3 10.0 122.0 339.0 373.7 408.6 443.8 479.1 15.0 117.0 507.9 560.0 612.3 664.9 717.6

i Table 3-9

\ Key Plant Parameters and Conditions Assumed in the Shutdown to Refueling Evaluation

a. Reactor coolant system volume = 9.398 ft3 .

b. Initial RCS average 'oop temperature = 532 degrees.

c. Pressurizer volvg = 450 ft3 , .

d. Pressurizer is saturated.

e. Zero reactor coolant system leakage. '

f. Boric acid sakeup tank temperature = 70 degrees.

9 Complete and instantaneous mixing between the pressurizer and the reactor coolant system,

h. Constant pressurizer level maintained during the feed-and-bleed process.

f. Initial RCS concentration = 0 ppm boron.

j. BAMT concentration = 3.50 weight percer t boric acid.

k. RWT concentration = 1720 ppm boron.

1. Shutdown cooling system volume = 3000 ft3 .

m. Baron concentration in the shutdown cooling system is equal to the boron. concentration in the RCS at the time of shutdown cooling initiation,

n. h fueling concentration, Mode 6 = 1720 ppm. .

\

eg 4

9 4

3-20

Table 3-10 ,

Evaluation Results for Plant Shutdown to Refueling Temp Pressure Concentration Total BAMT (degrees) (psia) (ppt boron) Volume (cal) 532 2200 0 0 532 2200 138.0 1,280 532 2200 272.8 2,560 532 2200 404.6 3,840 532* 2200 533.4 5,120 500 2200 734.6 7,149.7 450 2200 985.4 9,903.8 400 2200 1183.0 12,269.6 350 2200 1345.9 14,367.7 325# 275 1359.1 15,632.8 325 275 1359.1 15,632.8 300 275 1427.3 16,862.8

. 250 275 1547.7 19,123.5 l 200 275 1646.7 21.073.9 l 150 275 1724.3 22,664.4 l 135 275 1744.4 23.085.0 1

Initial 40 minute feed-and-bleed complete, d Cooldown stopped for one hour for shutdown cooling system alignment.

l e

\

-d e

e 3-21

4 Table 3-11 s Key Plant Parameters and Conditions Assumed in the Shutdown to Cold Shutdown Evaluation

a. Reactor coolant system volume = 9,398 ft3 .

b. Initial RCS average loop temperature = 532 degrees.

c. Pressurizer volume = 450 ft3 .

d. Pressurizer is saturated,

e. Zero reactor coolant system leakage.

f. Boric acid makeup tank temperature = 70 degrees.

g. Demineralized water supply temperature = 70 degrees,

h. Complete and instantaneous mixing between the pressurizer and the reactor coolant system.

i. Constant pressurizer level maintained during the plant cooldown, J. Initial RCS concentration = 0 ppm boron,

k. BAMT concentration = 3.50 weight percent boric acid.

1. RWT concentration = 1720 p'pm boron.

m. Shutdown cooling system volume = 3000 ft3 .

n. Boron. concentration in the shutdown cooling system is equal to the

' boron concentration in the RCS at the time of shutdown cooling initiation for Case !.

o. Boron concentration in the shutdown cooling system is equal to the boron concentration in the RWT at the time of shutdcwn cooling initiation for Case !!.

o 3-22

.s I

a 1

, Table 3-12 Case I-Evaluation Results for Plant Shutdown to Cold Shutdown with SOCS Concentration Equal to RCS Concentration 4

at the Time of Shutdown Cooling Initiation Temp Blending Pressure Concentration Total 8AMT (degrees)' Ratio (*) (psia) ,

(ppm boron) Volume (gal) 532 --

2200 0 0 500 --

2200 221.0 2,029.7 450 --

2200 496.6 4.783.8 400 --

2200 713.5 7,149.6 350 0.85:1 2200 799.8 8,446.5 325 1.53:1 275 800.0 9,299.9 325d --

275 800.0 9,299.9 300 6.89:1 275 800.0 9,455.7 250 6.89:1 275 800.0 9,742.3 200 6.9:' . 275 800.0 9,989.2 150 6.9:1 275 800.0 10,190.5 135 6.9:1 275 800.0 10,243.7 Ratio of pure water to BAMT water at blending tee.

Af ter shutdown cooling system alignment.

e e

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e 3-23 t

i 4-Table 3-13 Case !!

Evaluation Results for Plant Shutdown to Cold Shutdown with SOCS Concentration Equal to RWT Concentration '

s at the Time of Shutdown Cooling Initiation Temp Blending Pressure Concentration Total BAMT (degrees) Ratio (*) (psia) "(ppm boron) Volume (gal) 532 --

2200 0 0 500 --

2200 221.0 2,029.7 '

450 --

2200 496.6 4,783.8 400 5.1:1 2200 516.7 5,171.6 350 '

11:1 2200 517.0 5,346.5 325 2.97:1 275 517.0 6.303.6 325# --

275 800.0 6,303.6 300 6.89:1 275 800.0 6,459.5 250 6.89:1 275 800.0 6,746.0 200 6.89:1 275 800.0 6,993.2 150 6.89:1 275 800.0 7,194.8 135 6.89:1 275 800.0 7,248.1 Ratio of pure water to BAMT water at blending tee.

After shutdown cooling system is aligned and circulated.

\

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4.0 REFERENCES

4.1 Technical Data Sheet IC-11, US Borax & Chemical Corporation, 3-83-J.W.

4.2 Combustion Engineering's Emergency Procedure Guidelines, CEN-152, Revision 2, May, 1984.

4.3 An Evaluation on the Natural Circulation Cooldown Test Performed at the San Onofre Nuclear Generating Station, compliance with the Testing Requirements of Branch Technical Position RSB 5-1, CEN-259, Combustion Engineering, January 1984.

4.4 U.S. Nuclear Regulatory Commission Standard Review Plan NUREG-0800 Section 5.4.7. "Residual Heat Removal (RHR) System

and Branch Technical Position (RSB) 5-1 "Design Requirements of the Residual Heat Removal System".

4.5 C-E Letter F2-CE-R-021, "St. Lucie Unit 2 Cycle 3 Physics. Data for FP&L's Non-LOCA Transient Evaluation", E. A. Trapp to J. L. Perryman, dated August 12, 1985.

4.6 C-E Letter F2-CE-R-078, "Transmittal of St. Lucie Unit 2 Cycle 3 Startup Test Predictions and Physics Data Book Information", E. A. Trapp to J. L. Per.ryman, dated May 1, 1986.

g e

b 0

4-1

Appendix 1 Derivation of the Reactor Coolant System Feed-and-Bleed Equation Purpose of Definitions This appendix presents the detailed derivation of an equation which can be used to compute the reactor coolant system (RCS) boron concentration change during a feed-and-bleed operation. For this derivation, the following definitions were used:

m = mass flowrate into the RCS in m = mass flowrate out of the RCS ut m

b

= boron mass flowrate w = water mass flowrate m

3

= boron mass m, = water mass C

in = baron concentration going into RCS out = boron concentration; going out of RCS C

C, = initial boron concentration C(t) = boren concentration as a function of time CRCS ". RCS boron concentration Simplifying Assumptions s

During a feed-and-bleed operation, the reactor

-> coolant system can be pictured as shown in the figure S

out as a close'd container having a certain volume, a ig c, C out certain' mass, and an initial boron concentration.

e Coolant is added at one end via the charging pumps.

Acs The rate of addition is dependent on the number of

herging pumps that are' running with the 1 of 5

concentration being determined by the operator. Coolant is removed at the other end via letdown at a rate that is approximately equal to the charging rate and at a concentration determined by fluid mixing within the reactor coolant system. The mass flowrate into the reactor coolant system is given by the following equation:

M in * ( b + w)in' For typical boron concentrations within the chemical and volume control system, m, is very much greater than mb . (For example, a 3.5 weight percent boric acid solution contains only 0.04 lbm of boric acid per lbm of water). Therefore the above equation can be simplified to the following:

,in , ( , w )in (1.0)

In a similar manner, the mass flowrate coming out of the reactor coolant system, given by

out = ($ b * $ w Iout' can be simplified by again realizing that m, is very much greater than mb or ,

out = I* w} out.

(2.0)

For a feed-and-bleed operation with a constant pressurizer level and a constant system temperature, the mass flowrate into the RCS will be equal to the mass flowrate out of the RCS, or A in = *out =, w}in=I*w}out. (3.0) l 2 of 5 t

Finally, if it is assumed that the boren which is added to the reactor coolant systcm mixes completely and instantly with the entire RCS mass, the concentration of the fluid coming out of the system will be equal to the system concentration, or Cout = CRCS. (4.0)

Derivation The rate of change of boron mass within the reactor coolant system is equal to the mass of baron being charged into the system minus the mass of boron leavin) via letdown. In equation form, this becomes d(mb ) RCS = 'hinC in' *out Cout' dt From Equation 3.0, d(mb )RCS = #i n IC in Cbuk"I"w)inICin- Cout). (5.0) dt The concentration of boron in the reactor coolant system, i.e.. the weight fraction of boron, is defined as follows:

C -

s b RCS =

i , , . *b * "w RCS Since m j mb '

C RCS = _b

w RC$r ,

3 of 5 1

i

Where (m,) RCS is a constant for a constant system temperature. The rate of -

change of the RCS concentration is therefore d(m)RCS b '

dC d RCS = .

(6.0) dt (m dCS 1

Substituting Equation 5.0 into Equation 6.0 yields the following:

dcRCS=I#)in(Cinw - Cout} ,

dt (m,)RCS and from Equation 4.0, dCRCS = (*w I in 50in - CRCS I . (7.0) i dt (m,) RCS 1

Solving Equation 7.0 for concentrai, ion yields:

dC RCS , I"w)in dt' Cin

CRCS I

(*w RCS or C(t) t

- P dC

RCS I* w) in dt .

J C in' C RCS ("wI RCS 0 0 l 0 Integrating from ume initial concentration C, to some final concentration C(t) and mulliblying through by a minus one gives the following:

C(t)

In(CRCS - CIN) = I*w)in t.

I RCS C

o <

or 4 of 5

[

s i

d In C(t) -C in IAh

= in t.

G ~

o *in 5"wI RCS Continuing to solve for C(t), this equation becomes:

C(t) - Cin e w in "w ,105 ,

C ~C o in or C(t) = Cin

IC o - Cin)' '

If we define the time constant T to be as follows:

T = I'w) RCS ,

(mw )in then Equation 8.0 becomes C(t) = C, e- t/T + C in (1 , , -t/T) . (9.0) e s

4

=#

4 4

4 9

5 of 5

f Appendix 2 A Proof that Final System Concentration is Independent of System Volume Purpose of Definitienj This appendix presents a detailed proof that during a plant cooldown I where an oper& tor is charging only as necessary to makeup for coolant contraction, the final system concentration that results using a given l boration source concentration will be independent of the total system i volume. For this proof, the following definitions were used:

i i

cy = initial boron concentration Plant 1 l m bi = initial boron mass Plant 1 l mg = initial water mass Plant 1 c = final boron concentration Plant 1 f

c, = boron concentration of makeup solution Plant 1 m

ba = mass of boron added Plant 1 m, = mass of water added, Plant 1 l m bf = final boren mass Plant 1 C, = initial boron concentration Plant 2 j Mbi = initial boren mass Plant 2 1

Mg = initial water mass Plant 2 C

f = final boron concentration Plant 2 C, = boron concentration of makeup solution Plant 2 M = mass of boron added Plant 2 ba M = mass of water added Plant 2 Proof For this proof, consider two' plants at the same initial temperature, the same initial pressure, and the same initial boron concentration. One plant, Plant 2, has exactly twice the system volume as the other plant, 1 of 4

Plant 1. Initially, boron concentration Plant 1 = boron concentration Plant 2, or M N c,=C,= bi = bi .

(1.0)

M

bi*

wi "bi

wi Since the volume of Plant 2 is twice that of Plant 1 M,9 = 2m g.

Substituting this relationship into Equation 1.0 and solving yields the following:

bi "bi '

bi * "wi "bi * #wi

bi bi

2*b i*wi " *bi b i * "wi b i '

and Mbi = 2*bi . (2.0)

Therefore, the initial boron mass in Plant 2 is exactly twice the initial boron mass in Plant 1.

During the cooldown process for Plant 1, the final boron mass in the system will equal the . initial boron mass plus the added boron mass, or

. m (3.0) bf ' *bi *

ba .

If, during this.cooldown process, operators charge only as necessary to makeup for coolant contraction, water and baron will be added only as space is made available in the system due to coolant shrinkage. The final boron concen'tration from Equation 3.0 can therefore be er. pressed as follows F ,

m bf * *bi * *ba ***wi *

w bf .

' ~

,

bi*

ba* "wi *

wa 2 of 4

If concentration is expressed in terms of weight percent, this last '

equation becomes m

bf ' . *bi * *ba

wi + "wa C

f. (4.0)

Similarly, the remaining two components of Equation 3.0 become M

bi ' *bi * "wi C i (5.0) and "ba "p*ba * *wa C a (6.0)

Substituting Equa*, ions 4.0, 5.0, and 6.0 into Equation 3.0 and solving for the final concentration yields the following:

C f= *bi + "wi C i + E=ba + =w] ca (7.0)

bi * *ba *

wi' *wa For Plant 2, Equation 7.0 becomes O

f= .bi*N'i]C,+

N w ,,M b a

N wa. ,Ca (8.0)

"bi * "ba * "wi * "wa During a cooldown, the shrinkage mass, i.e., the mass of fluid that must be added to the system in order to keep pressurizer level constant, is calculated by dividing the system volume by the change in specific volume, or .

m,js , System Volume Plant 1 (9.0) a specTfic volume

~~

and

.M,, , System. Volume Plant 2 ,

(10.0) a spec 4 fic volume where System Volume Plant 1 = (1/2) System Volume Plant 2.

3 of 4

For a given cooldown, dividing Equation 9.0 by Equation 10.0 gives the following:

M,, = 2m,, (11.0)

In addition, if the charging source for both plants is at the same concentration and temperature, C, = c, , (12.0) and Mba " 2*ba . (13.0)

Substituting Ecuations 2.0, 11.0, 12,0, and 13.0 into Equation 8.0 yields the following:

O f= "bi + Mw C 4 + hm ba + ba] C a D bi l *Dba

Mwi

Dwa Since the initial concentrations are the same, C, = c,, and since Plant 2 l 1s twice as large as Plant 1. M,9 = 2m,g, C f,(2mbi + 2@i i +

Ia + 2g,] g , c f ,

~

' D bi

A"ba + Zgg +zg, p

Cf = cf . (14.0) i Therefore, for a cooldown where pressurizer level is maintained constant, the finii' boron concentration for Plant 2 is equal to the final boron concentration for Plant 1, i.e., the change in boron concentration is independant of the exact system volume.

4 of 4

i Appendix 3 P

Methodology for Calculating Dissolved Boric Acid per Gallon of Water Furpose The purpose of this appendix is to show the methodology used to calculate the mass of boric acid dissolved in each gallon of water for solutions of various boric acid concentrations. Two solution tetrperatures were used corresponding to the minimum allowable refueling water tank temperature of 5 degrees and a boric acid makeup temperature of 70 degrees in the absence of tank heaters.

Methodoloqy and Results 1

Boric acid concentration expressed in tems of weight percent is defined as follows:

g , mass of boric acid x 100, total solution mass or C = mass of boric acid x 100. (1.0)

(mass of boric acid) + (mass of water)

If we define a bi.to be the Mass of boric acid and m, to be the mass of water, and if we substitute these defined tems into Equition 1.0 and '

solve for the mass of boric acid we have the following:

s

,ba C =

x 100 , '

ba * *w '

or l m = .

, (2.0) ba 100 - C !

1 of 2 l

t

From Appendix A of the Crane Company Manual (Flow of Fluids Through Valves, Fittings, and Pipe, Crane Co.,1981, Technical Paper No. 410),

the density of water at 70 degrees is 8.3290 lbm / gallon and at 50 degrees is 8.343 lbm / gallon. Using these water masses and Equation 2.0 above, .e mass of boric acid per gallon of solution is as follows:

Mass of acid per gallon Concentration of solution at source wt. % boric acid opm boron 50 degrees 70 degrees RWT 0.98379 1720 0.08289 lbm --

t RWT 1.05815 1850 0.08923 lbm --

RWT 1.14394 2000 0.09654 lbm --

RWT 1.22974 2150 0.10187 lbm --

RWT 1.31553 21'00 0.11121 It.m --

BAMT 2.50 4371 --

0.213L6 lbm BAMT 2.75 4808 --

0.23552 lbm BAMT 3.00 5245 --

0.25760 lbm s

BAMT .. 3.25 5682 --

0.27979 lbm BAMT 3.50 6119 -- 0,30209 ite 2 of 2

Appendix 4 Methodology for Calculating the Conversion Factor Between Weight Percent Boric Acid and apn Boron Purpose The purpose of this appendix is to show the methodolcgy used to derive the conversion factor between concentration in terms of weight percent boric acid and concentration in terms of parts per millicn (ppm) of naturally occurring boron.

Results For any species (solute) dissolved in some solvent, a solution having a concentration of exactly 1 ppm can be obtained by dissolvina 1 lbm of

solute in 999,999 lbm of solvent. An aqueous solutfon having a concentration of 1 ppm boric acid, therefore, can be obtained by dissolving 1 lbe of boric acid in 999,999 lbm of water, or 1 ppm , 1lbeboricacih , 1 lbe boric acid ,

1 lbe borte acid + 999,999 lbe water 10' lbm solution For any species (solute) dissolved in some solvent, a solution having a concentration of I weight percent (wt. %) can be obtained by dissolving 1 lbm of solute in 99 lbs of solvent. An aqueous solution having a concentration of 1 wt. % boric acid, therefore, can be obtained by i dissolving 1 lba of boric acid in 99 lbra of water, or 1 wt. 5 , 1 lhe boric.Leid ,1 lbm boric acid

100 1 lbe boric acid + 99 lbe water 10 N solution Dividing these last two equations yields a ratio of 104 , or 1 wt. % boric acid = 1' 0,000 ppm boric acid. (1.0)

1 cf 2 l

l

_ - . _ - - - -._-__ .--,-_ -.-_-_-.- - -a

To convert from ppm boric acid (weight fraction) to ppm boron (weight '

fraction), multiply Equation 1.0 by the ratio of the molecular weight of boric acid (naturally occurring H3803 ) to the atomic weight of naturally occurring boron. From the Handbook of Cheraistry and Physics, CRC Press, 10.81 I wt. % boric acid = (10,000) ITTI p.m boron ,

or _

l 1 wt. % boric acid = 1748.34 ppm boron.

1 i

1 1

, r l-i i

i

\

b o

2 of 2 l

Appendix 5 Bounding Physics Data Inputs The following Physics Data Inputs for St. Lucie Unit 2 are provided to facilitate review of this effort. The e:onservatism, uncertainties, and biases incorporated in the BAMT Boric Acid Concentration Reduction effort for !

St. Lucie Unit 2 are contained in Table 1. The St. Lucie Unit 2 EOC Physics Data Inputs are contained in References 4.5 and 4.6. During future cycles, the new core parameters must be compared with these inputs to ensure that they are still bounding, i

The purpose of this section is to describe the methodology used to compute the f core reactivity during the cooldown. This method has been devised to conservatively bound the reactivity affects of the natural circulation.

cooldown described in Section 2.2.1.1 of this report. The cooldown scenario and the method used to compute core reactivity are discussed in detail in the following paragraphs.

A description of the core reactivity affects is provided. In addition a brief !

description is provided to show that these assumpticns conservatively bound I all similar cooldowns at any time d6 ring tha fuel cycle, j

1. Conservative core physics parameters were used to determine the required <

boron concentration and the required Boric Acid Makeup Tank volumes to be added during plant cooldown.

End-of-cycle (E0C) initial boron concentration is assumed to be l zero, s End-qf-cycle mc.derator cooldown r.ffects are used to maximize the reactivity changes during plant cooldown. End-of Cycle moderator cooldown effects are used at the most Negative Technical Specification MTC. -

1 of 7

Positive reactivity is added to the core a3 the moderator temperat';re is lowered during the cooldown. The moderator temperature effects on core reactivity vary over the fuel cycle. The moderator temperature effect at beginning-of-cycle (BOC) is very small while the moderator temperature effect EOC provides the maximum reactivity insertion.

EOC Inverse Boron Worths (Table 2) were extracted from Reference 4.6. ,

End-of-cycle (EOC)inverseboronworthdatawasusedincombinationwith t EOC reactivity insertion rates nonnalized to the most Negative Technical ,

Specification Moderator Temperature Coefficient (MTC) limit since it was

{

known that this yields results that are more limiting than the combination of actual MTC and actual IBW values at all neriods through the fuel cycle prior to end-of-cycle.

2. Scram Worth A conservative scram worth was used in this calculation. The available scram worth was computed utilizing the hot zero power scram worth for all rods in minus the worst rod stuck full out. From this value the Power Dependent Insertion Limit worthi were subtracted to obtain a net

~

available scram worth. A Bias of -95 and Uncertainty of 131 was subtracted from the available scram worth for added conservatism. This scram worth is further reduced by subtracting an EOC reactivity value associated with the Full Power Defect.

3. Determination of Excess Scram Worth Excess scram worth was determined by comparing the available scram worth at zero p,ower and subtracting the required technical specification shutdown margin. Required Sh'.tdown Margin:

T,y, SM

> 200'F > 5000 pcm

< 200'F >_ 3000 pcm j 2 of 7 1

I

It was determined by this method that there was a 0.08 ok/k excess scram worth available for temperatures above 200*F and an excess scram worth of 1.58 ok/k for temperatures below 200*F.

l 4 Core Reactivity Effects l

A reactivity calculation has been perfonned to account for positive reactivity insertion due to the decay of xenon and the positive reactivity oye to the cooldown of +he moderator and fuel. Uncertainties and biases were applied to all resetivity affects. Table 1 delineates the biases and uncertainties used in this calculation.

Xenon Reactivity Effects As shown in Reference 4.6 of the xenon worth peaks at its most negative reactivity worth around eight hours after the reactor is shutdown. Xenon decay reduces the negative reactivity of the xenon back to its steady state operating value at approximately 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months after shutdown. At times after 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months the plant must be borated to compensate for the further reduction in xencn concentration. As an added conservatism this calculation never credited the extra negative reactivity inserted by the xenon peak that occurs'after shutdown. Instead the plant was maintained at hot standby for 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months to allow xenon to return to the 100% steady state.value and further xenon decay to add reactivity simultaneously with.

"he plant cooldown effects. Reference 4.6 was used to determine the positive reactiv'ity inserted into the core for tips af ter 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months at '

discreet time intervals. Note that a slow cooldown rate will prolong the time required to reach Mode 5 where the shutdown margin drops from 5.0% Ak/,k ,to 3.5% Ak/k and therefore would require a larger boron concentration to counteract xthon decay during the cooldown. A 12.5 degree per hour cooldown rate has been utilized in this calculation. It 4

should be notsd that this muhod accounts f or xenon decay for a full 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months which is a much longer time frame than is expected to achieve cold shutdown. -

3 of 7

I i

i Reactor Cooldown Effects The affect of the reactor cooldown was calculated by cetermining the fuel temperature and moderator temperature reactivity effects for each !

incremental temperature decreate. Data from Reference 4.5 was utilized ,

to determine these effects. It should be noted that these reactivity effects are independent of time and solely dependent on the change in ;

temperature of the core.

Boration Requirements '

1 Having determined the reactivity effects due to xenon, moderator cooldown and f..el temperature cooldown for discreet time intervals af ter the plant is shutdown, the necessary boron concentration to compensate for this reactivity cbrnge is determined. The Inverse Boron Worth values of i Reference 4.6 wort: used to determine the ppm boron necessary in the RCS i to compensate for the positive reactivities determined above. All the

! conservatism, uncertainties and biatos applied to this calculation are included in Tab 1e 1. i l

i

, l h

I + f I

i l N

l _,- i

(

i

(

i i 4 of 7 l l i

i i )

r Table 1 Conservatism, Uncertainties and Biases Incorporated in the BAMT Boric Acid Concentration Reduction Effort for St. Lucie Unit 2

1. The initial scram is assumed to proceed from the hot full power p0!L (power dependent insertion limit) to the all rods in, with the worst case rod stuck in the full out position conditions.

2. A bias of -94 and uncertainty of 13% was applied to the scram worth data.

3. A esabined bias and uncertainty of 10% was applied to tha moderator data.

4 A bias of 15% and an uncertainty of 15% was applied to the Doppler data.

5. The assumption that the cooldown begins at 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months is conservative in relation to the buildup and decay of Xenon.

t 4

\

i e .g e

4 1

5 of 7 i

s, i

l Table 2 s

Inverse Boron Worth TEMP IBW 557.0 80.0 544.5 80.0 532.0' 80.0

, 507.0 80.0 482.0 78.1 457.0 76.3 432.0 74.6 407.0 73.0 382.0 71.4 357.0 70.2 332.0 69.0 307.0 67.8 282.0 66.7 257.0 65.6 232.0 64.5 207.0' 63.7 200.0 63.3 200.0 63.3 200.0 63.3

'130.0 60.9 s

=#

9 e

9 6 of 7

/

Table 3 Required Boron Concentration for a Cooldown from 557'F to 135'F Temperatures Concentration (Degrees,F) (ppm boron) 557 -71.2 510 133.0 490 203.0 480 235.5 470 262.3 460 289.8 450 314.1 440 338,0 430 350.6 420 382.0 410 403.4 400 423.5

) 390 443.0 380 461.2 370 474.5 360 488.7 350 500,9 340 512.6 330 523.5 325 528.7 310 , 543.6 285 568.8 260 589.9 235 608.7 210 627.6

- 200 {

' 634.9 199.9* 539.9 199.9** 570.3 190 577.4 180 584.5 170 591.6 160 598.6 150 605.7

... 140 612.8 135 -

616.3 Af ter shutdown margin change from 5.05 delta k/k to 3.5% del *.4 k/k

" The boration requirement for a 3.55 shutdown margin and core is xenon free 7 of 7

ML20153G092

Text

1.1 Purpose and Scope

1.0 INTRODUCTION

3.1 INTRODUCTION

4.0 REFERENCES

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